WorldWideScience

Sample records for anl zero power research reactor-9

  1. EPRI [Electric Power Research Institute]/ANL investigations of MCCI [molten core-concrete interactions] phenomena and aerosol release

    International Nuclear Information System (INIS)

    A program of laboratory investigations has been undertaken at Argonne National Laboratory, under sponsorship of the Electric Power Research Institute, in which the interaction between molten core materials and concrete is studied, with particular emphasis on measurements of the magnitude and chemical species present in the aerosol releases. The experiment technique used in these investigations is direct electrical heating in which a high electric current is passed through the core debris to sustain the high-temperature melt condition for potentially long periods of time. In the scoping experiments completed to date, this technique has been successfully used for corium masses of 5 and 20 kg, generating an internal heating rate of 1 kw/kg and achieving melt temperatures of 2000C. Experiments have been performed both with a concrete base and also with a cooled base with the addition of H2/CO sparging gas to represent chemical processes in a stratified layer. An aerosol and gas sampling system is being used to collect aerosol samples. Test results are now becoming available including masses of aerosols, x-ray diffraction, and scanning electron microscope analyses

  2. Zirconium-hydride solid zero power reactor and its application research

    International Nuclear Information System (INIS)

    The Zirconium Hydride Solid Zero Power Reactor built at China Institute of Atomic Energy is introduced. In the reactor Zirconium-hydride is used as moderator, plexiglass as reflector and U3O8 with enrichment of 20% as the fuel, Since its initial criticality, the physical characteristics and safety features have been measured with the result showing that the reactor has sound stability and high sensitivity, etc. It has been successfully used for the personnel training and for the testing of reactor control instruments and experiment devices. It also presents the special advantage for the pre-research of some applications

  3. Zero Gravity Research Facility (Zero-G)

    Data.gov (United States)

    Federal Laboratory Consortium — The Zero Gravity Research Facility (Zero-G) provides a near weightless or microgravity environment for a duration of 5.18 seconds. This is accomplished by allowing...

  4. Determination of the theoretical and experimental zero-power frequency response of Ghana Research Reactor-1

    International Nuclear Information System (INIS)

    The frequency response measurements of a reactor at low power help in determining the kinetic parameters of a reactor and ultimately in investigating its stability with respect to small perturbations in reactivity. In this report, we present the results of the zero-power frequency response measurements of GHARR-1 by rod method and its analytical analogue. The comparison in calculated and measured values is reasonably good in the frequency range used (author)

  5. High power test results of the first SRRC/ANL high current L-band RF gun.

    Energy Technology Data Exchange (ETDEWEB)

    Ho, C. H.

    1998-09-11

    A joint program is underway between the SRRC (Synchrotrons Radiation Research Center, Taiwan) and ANL (Argonne National Laboratory, USA) for developing a high current L-band photocathode rf guns. We have constructed an L-Band (1.3 Ghz), single cell rf photocathode gun and conducted low power tests at SRRC. High power rf conditioning of the cavity has been completed at ANL. In this paper we report on the construction and high power test results. So far we have been able to achieve > 120 MV/m axial electric field with minimal dark current. This gun will be used to replace the AWA (Argonne Wakefield Accelerator)[l] high current gun.

  6. Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois

    International Nuclear Information System (INIS)

    Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory's Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007). Argonne National Laboratory-East (ANL-E) is owned by the U.S. Department of Energy (DOE) and is operated under a contract with the University of Chicago. Fundamental and applied research in the physical, biomedical, and environmental sciences are conducted at ANL-E and the laboratory serves as a major center of energy research and development. Building 315, which was completed in 1962, contained two cells, Cells 5 and 4, for holding Zero Power Reactor (ZPR)-6 and ZPR-9, respectively. These reactors were built to increase the knowledge and understanding of fast reactor technology. ZPR-6 was also referred to as the Fast Critical Facility and focused on fast reactor studies for civilian power production. ZPR-9 was used for nuclear rocket and fast reactor studies. In 1967, the reactors were converted for plutonium use. The reactors operated from the mid-1960's until 1982 when they were both shut down. Low levels of radioactivity were expected to be present due to the operating power levels of the ZPR's being restricted to well below 1,000 watts. To evaluate the presence of radiological contamination, DOE characterized the ZPRs in 2001. Currently, the Melt Attack and Coolability Experiments (MACE) and Melt Coolability and Concrete Interaction (MCCI) Experiments are being conducted in Cell 4 where the ZPR-9 is located (ANL 2002 and 2006). ANL has performed final

  7. Towards zero-power ICT

    Science.gov (United States)

    Gammaitoni, Luca; Chiuchiú, D.; Madami, M.; Carlotti, G.

    2015-06-01

    Is it possible to operate a computing device with zero energy expenditure? This question, once considered just an academic dilemma, has recently become strategic for the future of information and communication technology. In fact, in the last forty years the semiconductor industry has been driven by its ability to scale down the size of the complementary metal-oxide semiconductor-field-effect transistor, the building block of present computing devices, and to increase computing capability density up to a point where the power dissipated in heat during computation has become a serious limitation. To overcome such a limitation, since 2004 the Nanoelectronics Research Initiative has launched a grand challenge to address the fundamental limits of the physics of switches. In Europe, the European Commission has recently funded a set of projects with the aim of minimizing the energy consumption of computing. In this article we briefly review state-of-the-art zero-power computing, with special attention paid to the aspects of energy dissipation at the micro- and nanoscales.

  8. The Texts of the Instruments relating to a Project for a Joint Agency-Norwegian Program of Research with the Zero Power Reactor 'NORA'

    International Nuclear Information System (INIS)

    The text of the Supply Agreement between the Agency and the Governments of Norway and of the United States of America, and the text of the related Project Agreement between the Agency and the Government of Norway concerning an Agency project for cooperation in carrying out a joint program of research in reactor physics with the zero power reactor 'NORA', are reproduced in this document for the information of all Members of the Agency

  9. For zero maintenance in nuclear reactors and power plants

    International Nuclear Information System (INIS)

    The goals of 'zero maintenance' in nuclear reactors and power plants can be achieved by implementing on line condition monitoring along with concepts of predictive maintenance, quality control, maintainability, reliability, human engineering, zero defect, operations research, tribology and good maintenance management system. Instruments for condition monitoring are also listed. (author)

  10. Review of ANL research on lithium--hydrogen chemistry and tritium-containment technology

    International Nuclear Information System (INIS)

    Experimental data on the thermodynamic properties of solutions of protium, deuterium, and tritium in liquid lithium are reported. The significance of the results is discussed with regard to problems that are pertinent to the development of controlled thermonuclear fusion reactors. Values are given for the equilibrium constants, free energies of formation, plateau dissociation pressures, and Sieverts' constants in the Li-LiH, Li-LiD, and Li-LiT systems. The observed isotope effects in these systems appear to reside predominantly in the gas phase. Results of studies of the distribution of tritium between liquid lithium and selected molten salts indicate that molten-salt extraction has potential utility as a means of recovering tritium from liquid lithium fusion reactor blankets. Other recent work at ANL has given evidence that multilayered bonded-metal composites could be useful in reducing tritium permeation rates through thermally hot structures (e.g., steam generator tubes) in fusion devices and power reactors. Hydrogen permeation data are presented for three bonded-metal composites (i.e., 316-SS/Cu/316-SS, 304-SS/Nb, and 304-SS/Cu/Nb) as well as for 304-SS and 316-SS. The data are compared to calculated permeabilities for the bonded-metal composites based on an electro-analog model. (auth)

  11. ZERO EMISSION POWER GENERATION TECHNOLOGY DEVELOPMENT

    Energy Technology Data Exchange (ETDEWEB)

    Ronald Bischoff; Stephen Doyle

    2005-01-20

    Clean Energy Systems (CES) was previously funded by DOE's ''Vision 21'' program. This program provided a proof-of-concept demonstration that CES' novel gas generator (combustor) enabled production of electrical power from fossil fuels without pollution. CES has used current DOE funding for additional design study exercises which established the utility of the CES-cycle for retrofitting existing power plants for zero-emission operations and for incorporation in zero-emission, ''green field'' power plant concepts. DOE funding also helped define the suitability of existing steam turbine designs for use in the CES-cycle and explored the use of aero-derivative turbines for advanced power plant designs. This work is of interest to the California Energy Commission (CEC) and the Norwegian Ministry of Petroleum & Energy. California's air quality districts have significant non-attainment areas in which CES technology can help. CEC is currently funding a CES-cycle technology demonstration near Bakersfield, CA. The Norwegian government is supporting conceptual studies for a proposed 40 MW zero-emission power plant in Stavager, Norway which would use the CES-cycle. The latter project is called Zero-Emission Norwegian Gas (ZENG). In summary, current engineering studies: (1) supported engineering design of plant subsystems applicable for use with CES-cycle zero-emission power plants, and (2) documented the suitability and availability of steam turbines for use in CES-cycle power plants, with particular relevance to the Norwegian ZENG Project.

  12. The research of application with crystal transfer function of reconstruction in the value of neutron decay exponential constant on zero power assembly

    International Nuclear Information System (INIS)

    The value of transfer function of unorganic-crystal, CeF3, is measured by the method of pluse of laser radiation. It is applied that the mathematics convolution of neutron-decay exponential constant on zero power assembly is processed. At the same time, the effect is assumed that the dual-exponential type transfer function deals with the value of neutron-decay on zero power assembly in the convolution of input function. (authors)

  13. Current research using the ANL High Voltage Electron Microscope-Tandem Accelerator Facility

    International Nuclear Information System (INIS)

    Recent work at the Argonne National Laboratory, (ANL), HVEM-Tandem Accelerator user facility is summarized: direct observation of cluster defects formed by in-situ ion irradiation at low temperature using the ion-beam interface has led to important fundamental results on defect production processes. Results on solute segregation at elevated temperatures induced by electron and ion irradiation are reported. Other published work is briefly summarized and/or referenced

  14. Current research using the ANL High Voltage Electron Microscope-Tandem Accelerator Facility

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, A.; Ryan, E.A.

    1984-11-01

    Recent work at the Argonne National Laboratory, (ANL), HVEM-Tandem Accelerator user facility is summarized: direct observation of cluster defects formed by in-situ ion irradiation at low temperature using the ion-beam interface has led to important fundamental results on defect production processes. Results on solute segregation at elevated temperatures induced by electron and ion irradiation are reported. Other published work is briefly summarized and/or referenced.

  15. Research Toward Zero Energy Homes

    Energy Technology Data Exchange (ETDEWEB)

    Robert Hammon

    2010-12-31

    This final report was compiled from the detailed annual reports that were submitted for efforts in 2008 and 2009, and from individual task reports from 2010. Reports, case studies, and presentations derived from this work are available through the Building America website. The BIRA team is led by ConSol, a leading provider of energy solutions for builders since 1983. In partnership with over fifty builders, developers, architects, manufactures, researchers, utilities, and agencies, research work was performed in California, Colorado, Utah, New Mexico, Washington, Oregon, and Hawaii and five (5) climate regions (Hot-Dry, Marine, Hot-Humid, Cold, and Hot/Mixed Dry). In addition to research work, the team provided technical assistance to our partners whose interests span the entire building process. During the three year budget period, the BIRA team performed analyses of several emerging technologies, prototype homes, and high performance communities through detailed computer simulations and extensive field monitoring to meet the required climate joule milestone targets.

  16. Power Challenges of Large Scale Research Infrastructures: the Square Kilometer Array and Solar Energy Integration; Towards a zero-carbon footprint next generation telescope

    OpenAIRE

    Barbosa, Domingos; Márquez, Gonzalo Lobo; Ruiz, Valeriano; Silva, Manuel; Verdes-Montenegro, Lourdes; Santander-Vela, Juande; Maia, Dalmiro; Antón, Sonia; van Ardenne, Arnold; Vetter, Matthias; Kramer, Michael; Keller, Reinhard; Pereira, Nuno; Silva, Vitor; Consortium, The BIOSTIRLING

    2012-01-01

    The Square Kilometer Array (SKA) will be the largest Global science project of the next two decades. It will encompass a sensor network dedicated to radioastronomy, covering two continents. It will be constructed in remote areas of South Africa and Australia, spreading over 3000Km, in high solar irradiance latitudes. Solar Power supply is therefore an option to power supply the SKA and contribute to a zero carbon footprint next generation telescope. Here we outline the major characteristics o...

  17. ZERO SET OF SOBOLEV FUNCTIONS WITH NEGATIVE POWER OF INTEGRABILITY

    Institute of Scientific and Technical Information of China (English)

    姜惠强; 林芳华

    2004-01-01

    Here the authors are interested in the zero set of Sobolev functions and functions of bounded variation with negative power of integrability. The main result is a general Hausdorff dimension estimate on the size of zero set. The research is motivated by the model on van der waal force driven thin film, which is a singular elliptic equation.After obtaining some basic regularity result, the authors get an estimate on the size of singular set; such set corresponds to the thin film rupture set in the thin film model.

  18. Power Challenges of Large Scale Research Infrastructures: the Square Kilometer Array and Solar Energy Integration; Towards a zero-carbon footprint next generation telescope

    CERN Document Server

    Barbosa, Domingos; Ruiz, Valeriano; Silva, Manuel; Verdes-Montenegro, Lourdes; Santander-Vela, Juande; Maia, Dalmiro; Antón, Sonia; van Ardenne, Arnold; Vetter, Matthias; Kramer, Michael; Keller, Reinhard; Pereira, Nuno; Silva, Vitor

    2012-01-01

    The Square Kilometer Array (SKA) will be the largest Global science project of the next two decades. It will encompass a sensor network dedicated to radioastronomy, covering two continents. It will be constructed in remote areas of South Africa and Australia, spreading over 3000Km, in high solar irradiance latitudes. Solar Power supply is therefore an option to power supply the SKA and contribute to a zero carbon footprint next generation telescope. Here we outline the major characteristics of the SKA and some innovation approaches on thermal solar energy Integration with SKA prototypes.

  19. Zero CO2 emission SOLRGT power system

    International Nuclear Information System (INIS)

    A novel hybrid power system with zero CO2 emission (ZE-SOLRGT) has been proposed and analyzed in this paper. It consists of a high temperature Brayton-like topping cycle and a high pressure-ratio Rankine-like bottoming cycle, integrated with methane-steam reforming, solar heat-assisted steam generation and CO2 capture and compression. Water is selected to be the working fluid. Solar heat input enhances the steam generation and power output, and reduces fossil fuel consumption. Besides CO2 capture with oxy-fuel combustion and cascade recuperation of turbine exhaust heat, the system is featured with indirect upgrading of low-mid temperature solar heat and cascade release of fossil fuel chemical exergy, which is described by the energy level concept. With nearly 100% CO2 capture, the system attains a net energy efficiency of 50.7% (including consideration of the energy needed for oxygen separation). The cost of generated electricity and the payback period of ZE-SOLRGT are found to be $0.056/kWh and 11.3 years, respectively. The system integration accomplishes the complementary utilization of fossil fuel and solar heat, and attains their high efficiency conversion into electricity. -- Highlights: ► A novel hybrid power system ZE-SOLRGT has been proposed and analyzed. ► The system integrates power generation with methane-steam reforming, solar heat driven steam generation and CO2 capture. ► The system is featured with indirect upgrading of solar heat and cascade release of fossil fuel chemical exergy. ► The system thermodynamic and economic performances have been investigated.

  20. The Swedish Zero Power Reactor R0

    International Nuclear Information System (INIS)

    The reactor R0 is a critical facility built for heavy water and natural uranium or fuel of low enrichment,, The first criticality was achieved September 25, 1959. During a first period of more than two years the R0 will be operated as a bare reactor in order to simplify interpretation of results. The reactor tank is 3. 2 m high and 2. 25 m in diameter. The fuel suspension system is quite flexible in order to facilitate fuel exchange and lattice variations. The temperature of the water can be varied between about 10 and 90 C by means of a heater and a cooler placed in the external circulating system. The instrumentation of the reactor has to meet the safety requirements not only during operation but also during rearrangements of the core in the shut-down state. Therefore, the shut-down state is always defined by a certain low 'safe' moderator level in the reactor tank. A number of safety rods are normally kept above the moderator ready for action. For manual or automatic control of the reactor power a specially designed piston pump is needed, by which the moderator level is varied. The pump speed is controlled from the reactor power error by means of a Ward-Leonard system. Moderator level measurement is made by means of a water gauge with an accuracy of ± 0. 1 mm

  1. The Swedish Zero Power Reactor R0

    Energy Technology Data Exchange (ETDEWEB)

    Landergaard, Olof; Cavallin, Kaj; Jonsson, Georg

    1961-05-15

    The reactor R0 is a critical facility built for heavy water and natural uranium or fuel of low enrichment,, The first criticality was achieved September 25, 1959. During a first period of more than two years the R0 will be operated as a bare reactor in order to simplify interpretation of results. The reactor tank is 3. 2 m high and 2. 25 m in diameter. The fuel suspension system is quite flexible in order to facilitate fuel exchange and lattice variations. The temperature of the water can be varied between about 10 and 90 C by means of a heater and a cooler placed in the external circulating system. The instrumentation of the reactor has to meet the safety requirements not only during operation but also during rearrangements of the core in the shut-down state. Therefore, the shut-down state is always defined by a certain low 'safe' moderator level in the reactor tank. A number of safety rods are normally kept above the moderator ready for action. For manual or automatic control of the reactor power a specially designed piston pump is needed, by which the moderator level is varied. The pump speed is controlled from the reactor power error by means of a Ward-Leonard system. Moderator level measurement is made by means of a water gauge with an accuracy of {+-} 0. 1 mm.

  2. Magnet powering with zero downtime - a dream?

    CERN Document Server

    Zerlauth, Markus

    2012-01-01

    Despite a number of improvements already applied in the course of the year, the magnet powering system of the LHC still accounts for around 50% of the premature beam dumps. This number might even further increase when moving to higher beam energies in the next years. With mitigations of radiation effects and the prospects for beam induced magnet quenches being discussed elsewhere, we aim at identifying possible mid- and long-term improvements within the various equipment systems to further reduce the number of equipment failures leading to a loss of the particle beams. Amongst others, this includes the sensitivity of equipment to external causes such as electromagnetic perturbations or perturbations on the electrical network. To conclude, the gain of the identified mitigations will have to be balanced against the potential impact on schedule and cost.

  3. A User Guide to PARET/ANL

    Energy Technology Data Exchange (ETDEWEB)

    Olson, A. P. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Marin-Lafleche, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-01-01

    PARET was originally created in 1969 at what is now Idaho National Laboratory (INL), to analyze reactivity insertion events in research and test reactor cores cooled by light or heavy water, with fuel composed of either plates or pins. The use of PARET is also appropriate for fuel assemblies with curved fuel plates when their radii of curvatures are large with respect to the fuel plate thickness. The PARET/ANL version of the code has been developed at Argonne National Laboratory (ANL) under the sponsorship of the U.S. Department of Energy/NNSA, and has been used by the Reactor Conversion Program to determine the expected transient behavior of a large number of reactors. PARET/ANL models the various fueled regions of a reactor core as channels. Each of these channels consists of a single flat fuel plate/pin (including cladding and, optionally, a gap) with water coolant on each side. In slab geometry the coolant channels for a given fuel plate are of identical dimensions (mirror symmetry), but they can be of different thickness in each channel. There can be many channels, but each channel is independent and coupled only through reactivity feedback effects to the whole core. The time-dependent differential equations that represent the system are replaced by an equivalent set of finite-difference equations in space and time, which are integrated numerically. PARET/ANL uses fundamentally the same numerical scheme as RELAP5 for the time-integration of the point-kinetics equations. The one-dimensional thermal-hydraulic model includes temperature-dependent thermal properties of the solid materials, such as heat capacity and thermal conductivity, as well as the transient heat production and heat transfer from the fuel meat to the coolant. Temperature- and pressure-dependent thermal properties of the coolant such as enthalpy, density, thermal conductivity, and viscosity are also used in determining parameters such as friction factors and heat transfer coefficients. The code

  4. Prospects for vitrification of mixed wastes at ANL-E

    International Nuclear Information System (INIS)

    This report summarizes a study evaluating the prospects for vitrification of some of the mixed wastes at ANL-E. This project can be justified on the following basis: Some of ANL-E's mixed waste streams will be stabilized such that they can be treated as a low-level radioactive waste. The expected volume reduction that results during vitrification will significantly reduce the overall waste volume requiring disposal. Mixed-waste disposal options currently used by ANL-E may not be permissible in the near future without treatment technologies such as vitrification

  5. Prospects for vitrification of mixed wastes at ANL-E

    Energy Technology Data Exchange (ETDEWEB)

    Mazer, J.; No, Hyo

    1993-12-01

    This report summarizes a study evaluating the prospects for vitrification of some of the mixed wastes at ANL-E. This project can be justified on the following basis: Some of ANL-E`s mixed waste streams will be stabilized such that they can be treated as a low-level radioactive waste. The expected volume reduction that results during vitrification will significantly reduce the overall waste volume requiring disposal. Mixed-waste disposal options currently used by ANL-E may not be permissible in the near future without treatment technologies such as vitrification.

  6. Measurement of prompt neutron multiplication on the zero power

    International Nuclear Information System (INIS)

    Using a set of ST-PMT detector, the prompt neutron multiplication on the zero power is measured by the reliable and effective shielding methods. The results are compared with the results of Rossi-α method and 252Cf fission chamber technique. (authors)

  7. Ground zero: AIDS research in Africa.

    Science.gov (United States)

    Cohen, J

    2000-06-23

    More and more European and North American AIDS researchers are coming to sub-Saharan Africa, which is home to a whopping 70% of all HIV-infected people. These investigators are collaborating with local researchers on projects that aim to slow both HIV's spread and the course of disease in the millions already infected. But most African countries--constrained by limited resources, weak infrastructures, social mores, and political inaction--have grave difficulties translating research insights into prevention and treatment strategies. PMID:10896592

  8. 发电机零功率保护在300MW机组发变组保护中的应用%Research on zero power protection applied in 300MW unit generator-transformer protection

    Institute of Scientific and Technical Information of China (English)

    庄颖慧

    2014-01-01

    简要阐述了发电机零功率保护的原理以及在实际运行中的案例分析,说明发变组保护中增设发电机零功率保护的必要性。%The principle of zero power protection had been described briefly and analysis of the actual operation in the case.The neG cessity of adding zero power protection to the generator-transformer protection had been illustrated.

  9. A simulated test of physical starting and reactor physics on zero power facility of PWR

    International Nuclear Information System (INIS)

    The core neutron economics has been verified through experiments conducted at a zero power reactor with baffles of various thickness. A simulated test of physical starting of Qinshan PWR has been introduced. The feasibility and safety of the programme are verified. The research provides a valuable foundation for developing physical starting programme

  10. Local, zero-power void coefficient measurements in the ACPR

    International Nuclear Information System (INIS)

    Changes in reactivity may be stimulated in the ACPR by the local introduction of voids into the reactor coolant. The local void coefficients of reactivity which describe this effect are of interest from a reactor safety point-of-view, and their determination is the subject of this presentation. Bottled nitrogen gas was used to produce the voids. The gas was forced out of a small diameter tube which was positioned vertically in the core lattice with its open end below the fuel. The gas was passed through a pressure regulator, a valve, and a flowmeter to establish a steady flow condition, following which a delayed-critical (zero-power) reactor state was established. Correlation of the average volume of core void created by the nitrogen flow with the reactivity worth of the delayed-critical control-rod bank position produced the values of the zero-power void coefficients of reactivity. The void coefficients were determined at various core positions from ∼6 mm to 142 mm beyond the central irradiation space and for three different flow rates. For the range of void fractions investigated, these coefficients are negative, with values ranging between -$0.02 and -$0.12. Tabular and graphical results of the measurements are presented, and details of the coefficient determination are explained. (author)

  11. Recent activities at the zero-power teaching reactor CROCUS

    International Nuclear Information System (INIS)

    CROCUS is a zero-power critical facility used mainly for educational purposes at the Swiss Federal Institute of Technology (EPFL) in Lausanne, Switzerland. It is a low-enriched-uranium fuelled, light-water moderated reactor, with the fission power limited to 100 W. The presentation will discuss the crucial role of CROCUS in teaching -- both as framework for reactor practicals offered to physics students at EPFL and as key educational tool in the recently established Swiss Master of Science in Nuclear Engineering. Regular development work is needed for the various instruments and components associated with the facility. As illustration, the recently completed refurbishment of the control rod system and the related calibration experiments will also be discussed.

  12. Future coordinated researches by ANL (USA), INP AS RUz and INP NNC RKaz on the nuclear reactions and astrophysics

    International Nuclear Information System (INIS)

    should be peripheral and one-step mechanism of the particle transfer should dominate. In addition, the first excited states of outgoing 12C or 16O particles lie rather high (4.44 and 6.05 MeV respectively), so the interference of their excited states with the low lying states of final nuclei B will not take place. The reactions A(3He,d)B (ε3He→d+p=5.49 MeV) and A(t,d)B (ε3H→d+n=6.257 MeV) can be used also, but the energy of proton separation is somewhat more. The alpha transfer reactions A(6Li,d)B, A(7Li,t)B and A(7Be,3He)B is supposed to be used for obtaining ANCs B→ A+α because the projectiles are nuclei with weakly bound α - cluster. The possibility of implementation such experiments on ATLAS (ANL, USA) and U-150M (INP, Kazakhstan) accelerators is discussed

  13. Zero-Net Power, Low-Cost Sensor Platform

    Energy Technology Data Exchange (ETDEWEB)

    Hardy, J.E.

    2005-04-15

    Numerous national studies and working groups have identified very low-power, low-cost sensors as a critical technology for increasing energy efficiency, reducing waste, and optimizing processes. This research addressed that need by developing an ultra low-power, low-cost sensor platform based on microsensor (MS) arrays that includes MS sensors, very low-power electronics, signal processing, and two-way data communications, all integrated into a single package. MSs were developed to measure carbon dioxide and room occupancy. Advances were made in developing a coating for detecting carbon dioxide and sensing thermal energy with MSs with a low power electrical readout. In addition, robust algorithms were developed for communications within buildings over power lines and an integrated platform was realized that included gas sensing, temperature, humidity, and room occupancy with on-board communications.

  14. Preliminary investigation of the 317 Area, ANL-E

    International Nuclear Information System (INIS)

    The 317 Area at Argonne National Laboratory-East (ANL-E) is scheduled to undergo a Resource Conservation and Recovery Act (RCRA) Facility Investigation, Act or RFI. Prior to the formal RFI, a voluntary, preliminary characterization of the 317 Area was conducted by ANL-E. The characterization results were used to formulate the RFI work plan and provided a better focus for the formal investigation. This site presents a difficult engineering challenge. The nature of the waste disposed at this site in the past includes both liquid chemicals and radioactive waste. The 317 Area is classified as a radiologically controlled area because of operations currently performed there. Present Department of Energy policy stipulates that waste material from such an area must be considered radioactive. The possible presence of hazardous constituents in the soil and groundwater would require the investigation-derived waste generated at the site be disposed as radioactive mixed waste. Besides the nature of the waste possibly contaminating this site, the geology of the site poses an equally enigmatic situation. The ANL-E site is located in a region of recessional glacial moraine deposits

  15. Cell heterogeneity problems in the analysis of zero power experiments

    International Nuclear Information System (INIS)

    Methods are described for treating plate and pin cell heterogeneity in the preparation of broad group cross-sections used in the analysis of zero power fast reactor experiments. Methods used at Karlsruhe and Winfrith are summarised and compared, with particular reference to the treatment of resonance shielding, the calculation of broad group spatial fine structure, the treatment of leakage and the calculation of anisotropic diffusion coefficients. The problems of cells near boundaries such as core-breeder interfaces and of singularities such as control rods are also considered briefly. Numerical studies carried out to investigate approximations in the methods are described. These include tests of the accuracy of one-dimensional cell modelling techniques, and the validation by Monte Carlo of methods for treating streaming in the calculation of diffusion coefficients. Comparisons are shown between the heterogeneity effects calculated by the Karlsruhe and Winfrith methods for typical pin and plate cells used in the BIZET experimental programme, and their effect in a whole reactor calculation is indicated. Comparisons are given with measurements which provide tests of the heterogeneity calculations. These include reaction rate scans within pin and plate cells, and reaction rate measurements across sectors of pin and plate fuel, where the flux tilt is determined by the relative reactivity of the pin and plate cells. Finally, the heterogeneity problems arising in the interpretation of reaction rate measurements are discussed. (author)

  16. Research, development, and demonstration of zero-VOC wood coatings

    Energy Technology Data Exchange (ETDEWEB)

    Huang, E.W. [California Univ., Riverside, CA (United States). Center for Environmental Research and Technology

    1994-12-31

    A new zero-VOC wood coating technology was evaluated. The performance characteristics of a two-component, water-based epoxy coating were determined, application and emissions testing were conducted, and the cost benefit for energy conservation and air pollution reduction was assessed. Composition variations of the basic polymer in combination with each of several curing agents were determined. The resulting top coat showed excellent performance characteristics. The VOC contents of both the clear top coat and the white pigmented top coat were less than 10 g per l. Critical areas for product improvement, market development plan, and projected future research were reviewed. 6 refs., 4 tabs.

  17. ENPEP model enhancements at ANL

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) has been involved in energy and electricity planning analyses for almost 20 years. Their activities include the development of analytical tools and methodologies along with their application to a wide variety of national energy planning studies. The methodologies cover all aspects of energy planning. In response to a request by the US Department of Energy (USDOE) to integrate existing tools into a package that could be distributed to developing countries for their own use, the ENergy and Power Evaluation Program (ENPEP) was developed. The USDOE wanted an all purpose tool that would allow the user to do a complete energy analysis, from demand forecast through primary energy resources allocation to electricity generation system expansion plan and environmental analysis. Since its original development, the ENPEP modules have been improved and enhanced to incorporate advancements in computer hardware and software technology, as well as to correct bugs that were identified in the programs. In cooperation with other organizations (e.g. The World Bank - IBRD - and the International Atomic Energy Agency - IAEA -), the ENPEP package has been used at national, regional and inter-regional training courses, as well as in the conduct of national energy/electricity planning studies. This paper reviews the development of the ENPEP package and the proposed enhancements to the package. (author). 1 fig., 2 tabs

  18. Electrolysers as a load management mechanism for power systems with wind power and zero-carbon thermal power plant

    Energy Technology Data Exchange (ETDEWEB)

    Troncoso, E. [School of Industrial Engineering, Universidad Las Palmas de Gran Canaria (Spain); Newborough, M. [ITM Power Research Ltd., Mill House, Royston Road, Wendens Ambo, Saffron Walden CB11 4JX (United Kingdom)

    2010-01-15

    For an isolated power system the deployment of a large stock of electrolysers is investigated as a means for increasing the penetrations of wind power plant and zero-carbon thermal power plant. Consideration is given to the sizing and utilization of an electrolyser stock for three electrolyser implementation cases and three operational strategies, installed capacity ranges of 20-100% for wind power and 10-35% for zero-carbon thermal power plant (as proportions of the power system's maximum electrical demand) were investigated. Relative to wind-hydrogen alone, hydrogen yields are substantially increased especially on low-wind days. The average load placed on fossil-fuelled power plant is substantially decreased (while achieving a virtually flat load profile) and the carbon intensity of electricity can be reduced to values of <0.1 kg CO{sub 2}/kWh{sub e}. The trade-offs between the carbon intensity of the electricity delivered, the carbon intensity of the hydrogen produced and the daily hydrogen yield are explored. For example (on the variable wind day for Strategy C with respective wind power and zero-carbon thermal power penetrations of 100% and 35%), if the carbon intensity of hydrogen is relaxed from 0 to 3 kg CO{sub 2}/kg H{sub 2}, the hydrogen yield can be increased from 435 tonnes to 1115 tonnes (which is the energy equivalent of 120% of consumer demand for electricity on that day). The findings suggest that the deployment of electrolysers on both the supply and demand-side of the power system can contribute nationally-significant amounts of zero or low-carbon hydrogen without exceeding the power system's current maximum system demand. (author)

  19. ANL's electric vehicle battery activities for USABC

    Science.gov (United States)

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides advanced battery R&D technology transfer to industry; technical analyses, assessments, modeling, and databases; and independent testing and post-test analyses of advanced batteries. These capabilities and services are being offered to the US Advanced Battery Consortium (USABC) and Cooperative Research and Development Agreements (CRADA) are being negotiated for USABC-sponsored work at ANL. A small portion of DOE's cost share for USABC projects has been provided to ANL to continue R&D and testing activities on key technologies that were previously supported directly by DOE. This report summarizes progress on these USABC projects during the period of April 1 through September 30, 1992. In this report, the objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: 1.0 Lithium/Sulfide Batteries; 2.0 Nickel/Metal Hydride Support 3.0 EV Battery Performance; and Life Evaluation.

  20. Research in electric power

    CERN Document Server

    Sporn, Philip

    2013-01-01

    Research in Electric Power comprises the lectures presented in the Cornell University Lecture in 1965, which focuses on the research and development of electric energy or technology. The lectures compiled in this book are divided into three chapters. Chapter I traces the dramatic and exciting history of growth of the electric power industry and important contribution of a series of great technological developments. The second chapter examines in great detail the problems demanding research in the main areas of planning, design, and construction of the physical facilities; in successfully and e

  1. High Power Zero-Voltage and Zero-Current Switching DC-DC Converters

    Directory of Open Access Journals (Sweden)

    Jaroslav Dudrik

    2005-01-01

    Full Text Available The paper presents principles and properties of the soft switching PWM DC-DC converters. The attention is focused mainly on high power applications and thus the full-bridge inverters are used in DC-DC converters. Considerations are also given to the control methods and principles of the switching and conduction losses reduction.

  2. Scenario analysis of the nuclear power's role in future zero-carbon electricity system in Japan

    International Nuclear Information System (INIS)

    The realization of a zero-carbon electricity system is of vital importance to a future zero-carbon energy system and society, and nuclear power is expected to contribute to this much more than intermittent, complicated and costly renewald energies in the future in Japan. Therefore, in the present study, the role of nuclear power in Japan's future zero-carbon electricity system was studied using scenario analysis methods. Furthermore, technical feasibility analysis was conducted for electricity systems of the proposed scenarios in terms of reliability for the fluctuations of both daily and seasonal electrical demand and supply using an hour by hour simulation. The results show that nuclear power will contribute at least 60% of electricity production, and the whole systems were proven to be technically feasible with the help of EV batteries and hydrogen for daily and seasonal electricity storages respectively, operated based on smart gird control technologies. (author)

  3. A user's guide to the PLTEMP/ANL code

    International Nuclear Information System (INIS)

    PLTEMP/ANL V4.1 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of-Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

  4. ANL Advanced Photon Source crotch absorber design

    International Nuclear Information System (INIS)

    The ANL 7-GeV Advanced Photon Source storage ring crotch absorber will be subjected to a very high photon loading power density, approximately 750 W/mm2 at normal incidence. To accommodate this high heat load, two designs were studied: one is a V-type compound angle absorber and the other is a horizontally rotated plate absorber. For both models, thermal and structural analyses have been carried out using 3-D finite element analysis. The analysis indicates that the V-type compound angle absorber controlled the peak temperatures effectively within the given geometric constraints. Test samples made of GlidCop AL 15 (alumina dispersion strengthened copper) were evaluated with an electron beam welder. The predicted and measured temperatures were in reasonable agreement. The overall absorber design includes a perforated screen in the positron beam area of the storage ring vacuum chamber to reduce RF impedance and to provide pumping access for the high local gas load

  5. Measures of the zero power nuclear reactor's kinetic parameters with application of noise analysis

    International Nuclear Information System (INIS)

    The purpose of this work was to establish an experimental technique based on noise analysis for measuring the ratio of kinetic parameters β/ Λ and the power of the Zero Power Nuclear Reactor IPEN-MB 01. A through study of the microscopic and macroscopic noise analysis techniques has been carried out. The Langevin technique and the point kinetic model were chosen to describe the stochastic phenomena that occur in the zero power reactor. Measurements have been made using two compensated ionization chambers localized in the water reflector at symmetric positions in order to minimize spatial effects on the neutron flux fluctuation. Power calibrations based on the low frequency plateau of the cross-power spectral density has also been carried out. (author)

  6. Measurements of the Reactivity Properties of the Aagesta Nuclear Power Reactor at Zero Power

    International Nuclear Information System (INIS)

    The moderator level and temperature coefficients of reactivity and control rod differential reactivity worths have been determined at zero power by means of period measurements. The moderator level coefficient and the corresponding critical level have been measured for the 32, 68 and 136 fuel assembly cores at room temperature for cores with and without control rods. From these results the worths of control rods have been derived. HETERO calculations give up to 15 % lower values than the experimental results. The cold fresh core has an excess reactivity of 9.0 ± 0.2 %. The temperature coefficient and differential control rod worths were measured for the fully loaded core with filled tank in the temperature range between 30 and 210 deg C. Critical positions as a function of temperature were obtained for the corresponding control rod groups. No relevant calculations of the temperature coefficient for comparison with the experimental values have yet been made, but the experimental results together with measured critical control rod positions give good opportunities to check calculational programs. HETERO has been shown in these cases to reproduce differential control rod worths and critical positions fairly well. However, a certain underestimation of the rod effectiveness is quite noticeable. The relative increase in control rod effectiveness with a temperature change from 20 to 220 deg C has been estimated to be 0.29 ± 0.06

  7. Design of the zero power reactor core of Instituto de Energia Atomica, SP, Brazil

    International Nuclear Information System (INIS)

    The main characteristics of a graphite moderated core of a critical assembly to be installed in the zero power reactor of the Instituto de Energia Atomica have been defined. Several simple geometric configurations have been selected and criticality studies have been made. The necessary quantity of fissile uranium has been calculated. (author)

  8. Zero Power Physics Test by using Core Simulator(Co Si) for OPR1000

    International Nuclear Information System (INIS)

    Core management staff performs ZPPT at least every one and half year. So periodic training for ZPPT should be required to minimize human error in that test and to be well acquainted with test procedures. Co Si could provide environments for readiness of all test procedure of initial OPR1000 core. Co Si has been developed for the training of core management staff in the area of zero power physics test in order to enhance the capacity of core management personnel in OPR1000. Through this training, reactor parameters in zero power physics test are determined as the same way as commercial nuclear power plant's test procedure before real reactor physics test. Training test consists of confirming initial critical approach, point of adding heat, boron end point and measuring isothermal temperature coefficient and rod bank worth in a various way

  9. Ground Zero in the Debate over Stem-Cell Research.

    Science.gov (United States)

    Southwick, Ron

    2001-01-01

    Describes how political, legal, and ethical battles over embryonic stem-cell research are focused on the University of Wisconsin at Madison, where the cells were first isolated. Addresses the issue of access to the university's stem cells and a recent presidential decision regarding funding for stem-cell research.(EV)

  10. Modeling of a double fission chamber using MCNPX for power calibration at the zero-power teaching reactor CROCUS

    International Nuclear Information System (INIS)

    MCNPX-2.5 simulations and experiments were performed to improve the power prediction of the zero-power teaching reactor CROCUS at the Ecole Polytechnique Federale de Lausanne (EPFL) using a calibrated double fission chamber (DFC). The CROCUS facility is a zero-power critical reactor used for educational purposes. Traditionally, the core power is determined by irradiating thin gold foils placed along the core centre and by measuring the 411 keV γ-rays on HPGe detectors. The average 197Au(n,γ) self-shielded macroscopic cross-section obtained with the deterministic BOXER code (1σ - 10%) is employed to determine the flux and the reactor power. To benchmark the BOXER calculations, a DFC containing known amounts of enriched 235U and 239Pu deposits was installed within the reflector core and simulated with MCNPX-2.5/JEF-2.2. Particular care was taken to model the fissile deposits allowing to reduce the power uncertainty to 2% compared to the gold foil technique. A code-to-code comparison (BOXER vs. MCNPX) was performed and the results have shown a good agreement (2 to 5%) for most of the quantities calculated (flux, reaction rates). However, the normalization factor differed by 17% (flux-to-power ratio). Consequently, the core power was overestimated by 17% until now. Finally, the current investigations lead to an improved fission power determination and contribute to better core safety standard. (author)

  11. Analysis of gamma-ray dosimetry experiments in the zero power MINERVE facility

    International Nuclear Information System (INIS)

    The objective of this study is to develop nuclear heating measurement methods in zero power experimental reactors. These developments contribute to the qualification of photonics calculation schemes for the assessment of gamma heating in the future Jules Horowitz Material Testing Reactor. This paper presents the analysis of thermoluminescent detector (TLD) experiments in the UO2 core of the MINERVE Research Reactor at the French Alternative Energies and Atomic Energy Commission center in Cadarache. The experimental sources of uncertainty in the gamma dose have been reduced by improving the measurement conditions and the repeatability of the calibration step for each individual TLD. The interpretation of these measurements needs to take into account the calculation of cavity correction factors related to calibration and irradiation configurations, as well as neutron correction calculations. These calculations are based on Monte Carlo simulations of neutron-gamma and gamma-electron transport coupled particles. The comparison between calculated and measured integral gamma-ray absorbed doses in the aluminum material surrounding the TLD shows that calculations slightly overestimate the measurement, with a calculated versus experimental ratio equal to 1.04 ± 5.7 % (k=2). (authors)

  12. Analysis of gamma-ray dosimetry experiments in the zero power MINERVE facility

    Energy Technology Data Exchange (ETDEWEB)

    Amharrak, H.; Di Salvo, J.; Lyoussi, A.; Roche, A.; Masson-Fauchier, M.; Bosq, J. C. [CEA, DEN, DER, F-13108 Saint-Paul-lez-Durance (France); Carette, M. [Aix-Marseille Univ., LCP UMR 6264, 13397, Marseille (France)

    2011-07-01

    The objective of this study is to develop nuclear heating measurement methods in zero power experimental reactors. These developments contribute to the qualification of photonics calculation schemes for the assessment of gamma heating in the future Jules Horowitz Material Testing Reactor. This paper presents the analysis of thermoluminescent detector (TLD) experiments in the UO{sub 2} core of the MINERVE Research Reactor at the French Alternative Energies and Atomic Energy Commission center in Cadarache. The experimental sources of uncertainty in the gamma dose have been reduced by improving the measurement conditions and the repeatability of the calibration step for each individual TLD. The interpretation of these measurements needs to take into account the calculation of cavity correction factors related to calibration and irradiation configurations, as well as neutron correction calculations. These calculations are based on Monte Carlo simulations of neutron-gamma and gamma-electron transport coupled particles. The comparison between calculated and measured integral gamma-ray absorbed doses in the aluminum material surrounding the TLD shows that calculations slightly overestimate the measurement, with a calculated versus experimental ratio equal to 1.04 {+-} 5.7 % (k=2). (authors)

  13. Development and Optimization of Nuclear Heating Measurement Techniques in Zero Power Experimental Reactors

    International Nuclear Information System (INIS)

    The objective of this study is to develop nuclear heating measurement methods in Zero Power experimental reactors. This paper presents the analysis of Thermo- Luminescent Detectors (TLDs) and Optically Stimulated Luminescent Detectors (OSLDs) experiments in the MINERVE research reactors at the French Atomic Energy and Alternative Energies Commission center in Cadarache. The experimental sources of uncertainties on the dose have been reduced by using the optimum conditions of charged particle equilibrium (CPE) of the calibration step and reactor measurement for each detector types; by improving the process of the TLDs/OSLDs reading and calibration processes. The interpretation of these measurements needs to take into account several correction factors related to both the environment of calibration step and the type of detectors used. Similarly, the correction due to the neutrons contributions to the total dose integrated by the detectors is evaluated with Monte Carlo calculation methods. These calculations are based on MCNP simulations of neutron-gamma and gamma-electron transport coupled particles using ENDF/B-VI nuclear data library. TLDs and OSLDs are positioned inside aluminum or hafnium pillboxes. Comparisons between calculated and measured integral gamma-ray absorbed doses by TLDs in these new experiments are carried out in the MINERVE reactor in the surrounding aluminum material. They show that calculations slightly overestimate the measurements by about 8 %. By using OSLDs, the calculation slightly overestimates the measurement by about 6 %. (authors)

  14. Performance analysis of a near zero CO2 emission solar hybrid power generation system

    International Nuclear Information System (INIS)

    Highlights: • A novel solar hybrid power system with near zero CO2 emission has been proposed. • The system integrates fuel reforming, solar-driven steam generation and CO2 capture. • Solar heat upgrading and high-efficiency heat-to-power conversion are achieved. • The system accomplishes near zero CO2 emission with oxy-fuel combustion. • The system thermodynamic performances have been investigated and compared. - Abstract: A novel solar hybrid power generation system with near zero CO2 emission (ZE-SOLRGT) has been proposed in the previous work, which is based on a GRAZ-like cycle integrating methane–steam reforming, solar-driven steam generation and CO2 capture. Solar heat assistance increases power output and reduces fossil fuel consumption. Besides near zero CO2 emission with oxy-fuel combustion and cascade recuperation of turbine exhaust heat, the system is featured with indirect upgrading of low-mid temperature solar heat and its high efficiency heat-to-power conversion. A performance analysis of ZE-SOLRGT cycle has been carried out using ASPEN PLUS code to explore the effects of key parameters on system performances. It is concluded that ∼54% exergy efficiency can be attained with ∼100% CO2 capture. The net solar-to-electricity efficiency can reach up to 34.7% in the base case. Steam-to-methane molar ratio of 2–3 is suitable for system performance improvement. High system efficiency can be obtained as the HPT pressure ratio is in the range of 15–18. The system integration achieves the complementary utilization of fossil fuel and solar heat, as well as their high-efficiency conversion into electricity

  15. ANL-W 779 pond seepage test

    International Nuclear Information System (INIS)

    The ANL-W 779 sanitary wastewater treatment ponds are located on the Idaho National Engineering Laboratory (INEL), north of the Argonne National Laboratory -- West (ANL-W) site A seepage test was performed for two Argonne National Laboratory -- West (ANL-W) sanitary wastewater treatment ponds, Facility 779. Seepage rates were measured to determine if the ponds are a wastewater land application facility. The common industry standard for wastewater land application facilities is a field-measured seepage rate of one quarter inch per day or greater

  16. An Innovative Test Platform for Hydrogen Production and Zero Emission Power Generation from Coal

    International Nuclear Information System (INIS)

    The ZECOMIX project, conceived by ENEA in the framework of Italian National Hydrogen Project, is aimed at studying an integrated process that produces both hydrogen and electricity from coal, with zero emissions and very high efficiency. The key element is the integration of a gasification process, characterized by coal hydro-gasification technology and carbon dioxide sequestration, with the power island, where an oxy-combustion occurs. Many optimization analysis and simulations have been carried out demonstrating the possibility to achieve very high net efficiencies (higher than 50% LHV) and very low (quasi-zero) emissions. The project schedule consists of the design, already started, the construction and the operation of an experimental facility finalized to demonstrate the feasibility of the described reference process. The facility will be realized in the ENEA Research Center of Casaccia, near Rome. It consists of a very flexible plant, in which more components can be tested separately or connected together. The plant is provided with a 50 kg/h coal atmospheric fluid bed gasifier, a fluid bed decarbonator/calcinator reactor filled with calcium oxide pellets, a pressurized hydro-gasifier reactor characterized by a pressure variable from 30 to 100 bar, a 100 kWe micro-turbine test bench, with the combustor chamber modified because of de-carbonized syngas fuelling and finally an oxygen/hydrogen combustor test bench, for experimental activities about the definition of stability limits, operative conditions (dilution, temperature pattern, chemicals) and combustion control. Other auxiliary components are mixing station for hydrogen-based syngas production, and an ordinary steam generator. The first part of the research project is aimed at testing the single component, in particular the main preliminary design criteria adopted for hydro-gasification reactor and carbonator reactor are presented in this paper. The second part of the Project is focused on the integration

  17. Major accident analyses for experimental zero-power fast reactor assemblies

    International Nuclear Information System (INIS)

    A study has been made of the possibility, mechanism, and consequence of melt-down and other major nuclear accidents for a ZPR-III type experimental zero-power fast reactor of the two-half type. This study has been supplemented by an evaluation of the importance of the Doppler effect for a wide range of nuclear reactor assemblies for such a reactor. A melt-down event is highly improbable because of the restricted sequence of events which must be postulated. A discussion of the mechanism of the collapse is followed by the results of coupled neutronics-hydrodynamic s calculations for two zero-power assemblies. A 1200-l core has been examined because it represents a relatively large reactor of common core composition. A smaller core with a high-void fraction has been examined as a potentially more dangerous system. Very different time-wise behaviour has been found for the two systems. For sharp accidents in zero-power assemblies, the U235-atoms, separated as plates of enriched uranium, will heat very rapidly while the remainder of the core remains essentially cold, so that a gas of U235-vapour will provide the disassembly pressure. The adaption of the neutronics-hydrodynamic s code AX-I to the use of a Van der Waals gas is described. Another important change in the equation of state used in the code is to employ a Mie-Griineisen type equation derivable from solid state theory. This change provides a more satisfactory way to evaluate the pressure term for cores of variable composition. Because the highly enriched U235 plates of a zero-power assembly will heat much more rapidly than the depleted uranium plates, the possibility of a net positive Doppler effect is much larger for an experimental assembly than for the equivalent power breeder reactor. This hazard has been examined for a range of possible assemblies. These calculations indicate that the Doppler coefficient for a zero-power assembly does not become important as a hazard until one approaches systems with the

  18. The control-and-instrumentation system of the IEA zero power reactor and its reliability calculation

    International Nuclear Information System (INIS)

    The control-and instrumentation system for the Instituto de Energia Atomica Zero Power Reactor is described and the design criteria are presented and discussed. The reliability analysis for the reactor protection system was performed using the fault tree method. This was done using a computer code based on the Monte Carlo simulation. That code is an adaptation of the SAFTE-I, for the IBM 360/155 IEA Computer. (Author)

  19. Experimental estimation of the delayed neutron fraction βeff of the MAESTRO core in the MINERVE zero power reactor

    International Nuclear Information System (INIS)

    A method for determining the effective delayed neutron fraction βeff using in-pile reactivity oscillations and Fourier analysis is presented. This method is based on measurements of the reactor's power response to small periodic in-pile reactivity perturbations and utilizes Fourier analysis for reconstruction of the reactor zero power transfer function. This approach enables the estimation of βeff using multi-parameter nonlinear weighted least-squares fit. The method extends previous works by accounting for higher harmonics excitation in the frequency domain by the trapezoidal reactivity signal, both in the reactivity perturbation and in the reactor power response. We show that by using this new approach it is possible to obtain the reactor transfer function in a wide range of frequencies, using only a single oscillation frequency. This method is applied to a set of measurements of the MAESTRO core configuration in the MINERVE zero power reactor (ZPR) located at the Cadarache Research Center. The derived value of βeff, using this method, is 711 ± 17 pcm. (author)

  20. Future zero-carbon energy systems in Japan with different nuclear power development scenarios

    International Nuclear Information System (INIS)

    An integrated scenario analysis has been conducted toward zero-carbon energy system from 2010 to 2100 in Japan, wherein the effect of Fukushima nuclear accident happened in March, 2011 is more or less taken into account. In the study, various service demands are firstly estimated based on social-economic data and then best technology and energy mixes are obtained using the optimization model to meet the service demand. On the conductance of integrated scenario analysis towards the year 2100 when zero-carbon energy system will be attained, three different scenarios of nuclear power development are taken, i.e., (1) no further introduction of nuclear, (2) fixed portion and (3) no limit of nuclear. The results show that, in the end user side, zero-carbon energy scenario can be attained at 2100 with electricity supplies 75% of total energy utilization. And for the electricity supply, three different power generation scenarios are proposed: (Scenario 1) 30% renewable and 70% gas-CCS (Carbon Capture and Storage), (Scenario 2) every one third by nuclear, by renewable and by gas-CCS, and (Scenario 3) 60% nuclear power, 20% renewable and 10% gas-CCS. Lastly by the inter-comparison of the three scenarios from the four aspects of cost, CO2 emission, risk and diversity, Scenario 2 is rated as the most balanced scenario among the three by putting emphasis on the availability of diversified electric source of nuclear, renewable and gas-CCS. (author)

  1. Electrometallurgical treatment demonstration at ANL-West

    International Nuclear Information System (INIS)

    Electrometallurgical treatment (EMT) was developed by Argonne National Laboratory (ANL) to ready sodium-bonded spent nuclear fuel for geological disposal. A demonstration of this technology was successfully completed in August 1999. EMT was used to condition irradiated EBR-II driver and blanket fuel at ANL-West. The results of this demonstration, including the production of radioactive high-level waste forms, are presented

  2. Electrometallurgical treatment demonstration at ANL-West

    Energy Technology Data Exchange (ETDEWEB)

    Goff, K. M.; Benedict, R. W.; Johnson, S. G.; Mariani, R. D.; Simpson, M. F.; Westphal, B. R.

    2000-03-20

    Electrometallurgical treatment (EMT) was developed by Argonne National Laboratory (ANL) to ready sodium-bonded spent nuclear fuel for geological disposal. A demonstration of this technology was successfully completed in August 1999. EMT was used to condition irradiated EBR-II driver and blanket fuel at ANL-West. The results of this demonstration, including the production of radioactive high-level waste forms, are presented.

  3. MEASUREMENT ERROR EFFECT ON THE POWER OF CONTROL CHART FOR ZERO-TRUNCATED POISSON DISTRIBUTION

    Directory of Open Access Journals (Sweden)

    Ashit Chakraborty

    2013-09-01

    Full Text Available Measurement error is the difference between the true value and the measured value of a quantity that exists in practice and may considerably affect the performance of control charts in some cases. Measurement error variability has uncertainty which can be from several sources. In this paper, we have studied the effect of these sources of variability on the power characteristics of control chart and obtained the values of average run length (ARL for zero-truncated Poisson distribution (ZTPD. Expression of the power of control chart for variable sample size under standardized normal variate for ZTPD is also derived.

  4. Programmatic Need for a Zero Emission Steam Technology (ZEST) Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Meltzer, M; Followill, F; Johnson, J

    2001-06-30

    Lawrence Livermore National Laboratory (LLNL) is proposing to construct an on-site research facility for a novel electric power generation system that exploits clean-burning fossil fuels. This system, termed Zero Emission Steam Technology (ZEST), offers unique economic and environmental benefits, including: (1) Highly efficient power generation using the most advanced combustion and turbine technologies. (2) Ability to burn a range of fossil fuels, including natural gas, synthetic gas from coal (''coal syngas''), and coal-bed methane. (3) No oxides of nitrogen generated that would contribute to air pollution. (4) No greenhouse gases emitted. (5) Secure geologic sequestration of the carbon dioxide (CO{sub 2}) combustion product. (6) Use of the CO{sub 2} combustion product to enhance oil recovery in mature fields. The proposed research facility will provide a necessary step toward commercialization of ZEST. Despite the technology's promise, it will not be implemented by the U.S. electric power industry unless an agency such as DOE takes on the task of demonstrating its scientific and economic viability. The U.S. electric power industry typically requires 50,000 hours of operational data--nearly six years of continuous duty--before investing in a major new technology. Hence, there is a strong programmatic need for DOE to provide such data for ZEST, to accelerate commercial investment in this technology. The ZEST combustion process is based on rocket engine technology. It burns pure oxygen with a hydrocarbon fuel under stoichiometric conditions to produce power with virtually no oxides of nitrogen generated. The flexibility of ZEST's gas generator, which has independent temperature and pressure control, will allow modular upgrading of turbine systems as new, more efficient technology becomes available. It is envisioned that the ZEST research facility will serve as a testing laboratory for new turbine technology being designed by the U

  5. System zeros

    OpenAIRE

    Smagina, Ye. M.

    2006-01-01

    The present book is the first publication in English considered the modern problems of control theory and analysis connected with a concept of system zeros. The previous book by Ye.M. Smagina (1990) had been written in Russian and it is inaccessible to English speaking researchers. The purpose of the offered book is to systematize and consistently to state basic theoretical results connected with properties of multivariable system zeros. Different zeros definitions and different types of zero...

  6. ANL Advanced Photon Source crotch absorber design

    International Nuclear Information System (INIS)

    The ANL 7-GeV Advanced Photon Source storage ring crotch absorber will be subjected to a very high photon loading power density, approximately 750 W/mm2 at normal incidence. To accommodate this high heat load, two designs were studied: one is a V-type compound angle absorber and the other is a horizontally rotated plate absorber. For both models, thermal and structural analyses have been carried out using 3-D finite element analysis. The analysis indicates that the V-type compound angle absorber controlled the peak temperatures effectively within the given geometric constraints. Test samples made of GlidCop Al 15 (alumina dispersion strengthened copper) were evaluated with an electron beam welder. The predicted and measured temperatures were in reasonable agreement. The overall absorber design includes a perforated screen in the positron beam area of the storage ring vacuum chamber to reduce rf impedance and to provide pumping access for the high local gas load. 3 refs., 4 figs., 2 tabs

  7. Electric Power Research in 1994

    International Nuclear Information System (INIS)

    This book of contents are development of coal combustion computer program, practical application of solar powered generation of electricity in islands, development of reduction technique of amount of radiation in the primary system in nuclear plant, study on master plan for installation of simulator in electric power system, application and the development of surveillance system of transmission of electricity facility with light sensor, research on the influence over marine environments caused power plant and study on maintenance and safety assessment of dams.

  8. RESEARCH ACTION: IMPLEMENTATION ZERO BASED BUDGET (ZBB) IN THE PROVIDER SERVICE LEASING EQUIPAMENTS OF CARGO HANDLING.

    OpenAIRE

    Levi Gimenez; Antonio Benedito Silva Oliveira

    2013-01-01

    This article aims to present the implementation of zero-based budgeting in a rental service provider of cargo handling equipment using the action research methodology. The goal was to examine the possibility of concomitant use of this instrument in service providers in need of accurate information that enables targeting at the best result in a setting avid for quick decisions and actions. Action research was used as research method. It was concluded that it is suitable for this branch, con...

  9. Automatic Meter Reading using Power Line Signaling and Voltage Zero-crossing Detection

    Directory of Open Access Journals (Sweden)

    C.L. Vasu

    2015-06-01

    Full Text Available In India, the electric power transmission and distribution loss is very high, about 7% in transmission and 26% in distribution. Though deployment of automated meter reading system will reduce losses, particularly in distribution, penetration of automated meter reading is low due to high costs involved. World over, the Two-Way Automatic Communications System (TWACS is the most widely used power line communications technology offering two-way communication between substation and end users. The TWACS introduces disturbance on the power system voltage for short durations near zero-crossing to generate the outbound (from substation to end user signal. To generate the inbound (from end user to substation signal, short duration current pulses are introduced, near voltage zero-crossings. Information is generated as a sequential combination of voltage disturbances for the outbound signal and current pulses for the inbound signal. The current study proposes a low-cost modification of the TWACS to reduce voltage and current harmonics. The proposed system has been modelled and simulated using SIMULINK/SIMPOWER Systems. The simulation results show that there is a reduction in voltage harmonics from 0.84 to 0.17% and in current harmonics from 2.07 to 1.10%.

  10. Single-switch three-phase zero-current-transition rectifier with power factor correction

    OpenAIRE

    Gatari?, Slobodan

    1994-01-01

    A novel, zero-current-transition (ZCT) topology of the single-switch three-phase boost PFC rectifier is proposed. The soft transition is achieved with a low-power auxiliary circuit employing an additional switch. The circuit can be used with an IGBT at switching frequencies up to 50. Its operation is analyzed in detail, and design guidelines are provided. The small signal model of the circuit is developed, and voltage mode control is designed. The results are verified on a 4 kW...

  11. Fabrication of zero power reactor fuel elements containing 233U3O8 powder

    International Nuclear Information System (INIS)

    Oak Ridge National Laboratory, under contract with Argonne National Laboratory, completed the fabrication of 1743 fuel elements for use in their Zero Power Reactor. The contract also included recovery of 20 kg of 233U from rejected elements. This report describes the steps associated with conversion of purified uranyl nitrate (as solution) to U3O8 powder (suitable for fuel) and subsequent charging, sealing, decontamination, and testing of the fuel elements (packets) preparatory to shipment. The nuclear safety, radiation exposures, and quality assurance aspects of the program are discussed

  12. New Whole-House Solutions Case Study: New Town Builders' Power of Zero Energy Center - Denver, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    None

    2014-10-01

    New Town Builders, a builder of energy efficient homes in Denver, Colorado, offers a zero energy option for all the homes it builds. To attract a wide range of potential homebuyers to its energy efficient homes, New Town Builders created a "Power of Zero Energy Center" linked to its model home in the Stapleton community. This case study presents New Town Builders' marketing approach, which is targeted to appeal to homebuyers' emotions rather than overwhelming homebuyers with scientific details about the technology. The exhibits in the Power of Zero Energy Center focus on reduced energy expenses for the homeowner, improved occupant comfort, the reputation of the builder, and the lack of sacrificing the homebuyers' desired design features to achieve zero net energy in the home. This case study also contains customer and realtor testimonials related to the effectiveness of the Center in influencing homebuyers to purchase a zero energy home.

  13. Building America Case Study: New Town Builders' Power of Zero Energy Center, Denver, Colorado (Brochure)

    Energy Technology Data Exchange (ETDEWEB)

    2014-10-01

    New Town Builders, a builder of energy efficient homes in Denver, Colorado, offers a zero energy option for all the homes it builds. To attract a wide range of potential homebuyers to its energy efficient homes, New Town Builders created a 'Power of Zero Energy Center' linked to its model home in the Stapleton community of Denver. This case study presents New Town Builders' marketing approach, which is targeted to appeal to homebuyers' emotions rather than overwhelming homebuyers with scientific details about the technology. The exhibits in the Power of Zero Energy Center focus on reduced energy expenses for the homeowner, improved occupant comfort, the reputation of the builder, and the lack of sacrificing the homebuyers' desired design features to achieve zero net energy in the home. The case study also contains customer and realtor testimonials related to the effectiveness of the Center in influencing homebuyers to purchase a zero energy home.

  14. Spent fuel treatment at ANL-West

    International Nuclear Information System (INIS)

    At Argonne National Laboratory-West (ANL-West) there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Cycle Facility at ANL-West to produce stable waste forms for storage and disposal. The treatment operations will employ a pyrochemical process that also has applications for treating most of the fuel types within the Department of Energy complex. The treatment equipment is in its last stage of readiness, and operations will begin in the Fall of 1994

  15. Design and Analysis of the Power Control System of the Fast Zero Energy Reactor FR-0

    International Nuclear Information System (INIS)

    This report describes the power control by means of the fine-control rod and the design of the control system of the fast zero energy reactor FR-0 located in Studsvik, Sweden. System requirements and some operational conditions were used as design criteria. Manual and automatic control is possible. Variable electronic end-stops for the control rod have been designed, because of the special construction of the reactor and control rod. Noise in the control system caused by the reactor, detector and electronics caused disturbances of the control system at the lower power levels. The noise power-spectrum was measured. Statistical design methods, using the measured noise power spectrum, were used to design filters, which will reduce the influence of the noise at the lower power levels. Root Loci sketches and Bode diagrams were used for stability analyses. The system was simulated on an analogue computer, taking into account even nonlinearities of the control system and noise. Typical cases of reactor operation were simulated and stability analysis performed

  16. A zero-voltage switching technique for minimizing the current-source power of implanted stimulators.

    Science.gov (United States)

    Çilingiroğlu, Uğur; İpek, Sercan

    2013-08-01

    The current-source power of an implanted stimulator is reduced almost to the theoretical minimum by driving the electrodes directly from the secondary port of the inductive link with a dedicated zero-voltage switching power supply. A feedback loop confined to the secondary of the inductive link adjusts the timing and conduction angle of switching to provide just the right amount of supply voltage needed for keeping the current-source voltage constant at or slightly above the compliance limit. Since drive is based on current rather than voltage, and supply-voltage update is near real-time, the quality of the current pulses is high regardless of how the electrode impedance evolves during stimulation. By scaling the switching frequency according to power demand, the technique further improves overall power consumption of the stimulator. The technique is implemented with a very simple control circuitry comprising a comparator, a Schmitt trigger and a logic gate of seven devices in addition to an on-chip switch and an off-chip capacitor. The power consumed by the proposed supply circuit itself is no larger than what the linear regulator of a conventional supply typically consumes for the same stimulation current. Still, the sum of supply and current-source power is typically between 20% and 75% of the conventional source power alone. Functionality of the proposed driver is verified experimentally on a proof-of-concept prototype built with 3.3 V devices in a 0.18 μm CMOS technology. PMID:23893206

  17. Numerical extension of the power law Jc(B) to zero field in thin superconducting films

    International Nuclear Information System (INIS)

    Numerical simulations of the current and field distribution in thin superconducting films are carried out for a given material law Jc(B) and as a function of the applied field H, taking the sample's self-field into account. The dependence of the critical current density on the applied field Jc(H) is computed for comparison with experiment, considering the geometry of transport measurements. We show that extrapolating the high-field power law Jc∝B-α to the lowest fields results in a finite critical current at zero applied field Jc(H=0), despite the singularity of Jc(B). Moreover, particular features of the experiment, such as a low field plateau in Jc(H), are reproduced and found to be determined by the self-field.

  18. Passive and Active Radiation Measurements Capability at the INL Zero Power Physics Reactor (ZPPR) Facility

    International Nuclear Information System (INIS)

    The Zero Power Physics Reactor (ZPPR) facility is a Department of Energy facility located in the Idaho National Laboratory's (INL) Materials and Fuels Complex. It contains various nuclear and non-nuclear materials that are available to support many radiation measurement assessments. User-selected, single material, nuclear and non-nuclear materials can be readily utilized with ZPPR clamshell containers with almost no criticality concerns. If custom, multi-material configurations are desired, the ZPPR clamshell or an approved aluminum Inspection Object (IO) Box container may be utilized, yet each specific material configuration will require a criticality assessment. As an example of the specialized material configurations possible, the National Nuclear Security Agency's Office of Nuclear Verification (NNSA/NA 243) has sponsored the assembly of six material configurations. These are shown in the Appendixes and have been designated for semi-permanent storage that can be available to support various radiation measurement applications.

  19. Argonne National Laboratory – IAEA Coordinated Research Project on Developing Techniques for Small-Scale Indigenous 99Mo Production Using LEU Fission or Neutron Activation [Country report: United States of America - ANL

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) in the United States was active in the Consultancy Meeting that defined the scope of this CRP and has been involved from the beginning as an Agreement Holder. ANL’s major role in the CRP was providing two technologies free of charge, namely: (1) the annular LEU-foil target and, (2) the LEU-Modified Cintichem process. In addition to providing a range of documents describing the fabrication, irradiation history, and disassembly of the LEU-foil target; procedures and QC for the LEU-Modified Cintichem process; and guides describing handling of radioactive materials and gamma and alpha counting of radioactive samples, ANL also worked with Indonesia to hold a workshop demonstrating all aspects of the technology for the two technologies

  20. Electric Power Research in 1991

    International Nuclear Information System (INIS)

    This book of contents are a study of desalination by Kim, Young Bu, a study on efficiency test for nuclear power security by Jo, Sung Je; Ann, Nam Sung; Kim, Ho Gi, augmentation of EMS and RYU by Jung, Tae Hoe; Shin, Young Chuel, research on application for electric cars by Yu, Ann Gue, practical use oft robot for nuclear industry by Woo, He Gone; Shin, Hen Beom, a study on the characteristics of coolant structure in generator by Choi, Beng Hwan; Song, Young Chel; Kim, Jong Hark, and research of penetration rate of appliances by Park, Hong Ho; Kim, Beng Cheal; Kim, Dong Hwen.

  1. EVALUATION OF ZERO-POWER, ELEVATED-TEMPERATURE MEASUREMENTS AT JAPAN’S HIGH TEMPERATURE ENGINEERING TEST REACTOR

    Energy Technology Data Exchange (ETDEWEB)

    John D. Bess; Nozomu Fujimoto; James W. Sterbentz; Luka Snoj; Atsushi Zukeran

    2011-03-01

    The High Temperature Engineering Test Reactor (HTTR) of the Japan Atomic Energy Agency (JAEA) is a 30 MWth, graphite-moderated, helium-cooled reactor that was constructed with the objectives to establish and upgrade the technological basis for advanced high-temperature gas-cooled reactors (HTGRs) as well as to conduct various irradiation tests for innovative high-temperature research. The core size of the HTTR represents about one-half of that of future HTGRs, and the high excess reactivity of the HTTR, necessary for compensation of temperature, xenon, and burnup effects during power operations, is similar to that of future HTGRs. During the start-up core physics tests of the HTTR, various annular cores were formed to provide experimental data for verification of design codes for future HTGRs. The experimental benchmark performed and currently evaluated in this report pertains to the data available for two zero-power, warm-critical measurements with the fully-loaded HTTR core. Six isothermal temperature coefficients for the fully-loaded core from approximately 340 to 740 K have also been evaluated. These experiments were performed as part of the power-up tests (References 1 and 2). Evaluation of the start-up core physics tests specific to the fully-loaded core (HTTR-GCR-RESR-001) and annular start-up core loadings (HTTR-GCR-RESR-002) have been previously evaluated.

  2. A MICRO ZERO HEAD TURBINE POWER GENERATION FOR BUILDING’S WATER TANK OVER FLOW & ROOF RAIN WATER FLOW SYSTEM

    OpenAIRE

    Pasupuleti Sreenivasulu*, Dr. G. Prasanthi

    2016-01-01

    Energy is a major input for overall socio-economic development of any society. Hydel energy is the fastest growing renewable energy. From Decades man has been trying to convert Hydel power to mechanical &, more recently, electric power. Hydel technology has improved significantly over the past two decades, and Hydel energy has become increasingly competitive with other power generation options. A zero head water turbine can be used as a Hydro-Electricity device referring to generate the e...

  3. Optimal Power Distribution Control for Multicode MC-CDMA with Zero-Forcing Successive Interference Cancellation

    Directory of Open Access Journals (Sweden)

    Yeheskel Bar-Ness

    2005-04-01

    Full Text Available Multicarrier CDMA (MC-CDMA has become a promising candidate for future wireless multimedia communications for its robustness to frequency-selective fading and its flexibility for handling multiple data rates. Among different multirate access schemes, multicode MC-CDMA is attractive for its high performance, good flexibility in rate matching, and low complexity. However, its performance is limited by self-interference (SI and multiuser interference (MUI. In this paper a zero-forcing successive interference cancellation (ZF-SIC receiver is used to mitigate this problem for multicode MC-CDMA. Furthermore, optimal power distribution control (PDC, which minimizes each user's bit error rate (BER, is considered. Our results show that, in correlated Rayleigh fading channels, the ZF-SIC receiver integrated with the optimal PDC dramatically improves the performance of the multicode MC-CDMA system in comparison to other receivers proposed in the literature. Moreover, the optimal PDC significantly outperforms the PDC based on equal BER criterion, particularly under a short-term transmit power constraint.

  4. Two-dimensional heterogeneous transport theory hot zero-power benchmarks for the WWER-1000 reactors

    International Nuclear Information System (INIS)

    The Mariko code, based on the method of characteristics, has been used to calculate several two-dimensional full core heterogeneous 23-group transport theory solutions for hot zero power states of the WWER-1000 reactor. The initial loading for the three-year fuel cycle is considered. Helios-1.5 has been used to prepare 23-group cross-section data. The benchmarks differ by the positions (up or down) of the control rods groups. The asymptotic assembly-averaged and cell-averaged two-group diffusion parameters for all assembly types, the group-to-group albedo son the radial reflector boundary, and the effective diffusion parameters, including reference discontinuity factors, for the radial reflector nodes are all calculated by Mariko. The accuracy of the SPPS-1.6 and DYN3D nodal diffusion codes and the HEX2DA pin-by-pin diffusion code have been tested. The benchmark with all control rods down poses a great problem for the modal diffusion codes, the maximum error in the relative assembly-wise power distribution reaching 18% for SPPS-1.6. The pin-by-pin code performs well in all cases (Authors)

  5. Initial RattleSnake Calculations of the Hot Zero Power BEAVRS

    Energy Technology Data Exchange (ETDEWEB)

    M. Ellis; J. Ortensi; Y. Wang; K. Smith; R.C. Martineau

    2014-01-01

    The validation of the Idaho National Laboratory's next generation of reactor physics analysis codes is an essential and ongoing task. The validation process requires a large undertaking and includes detailed, realistic models that can accurately predict the behavior of an operational nuclear reactor. Over the past few years the INL has developed the RattleSnake application and supporting tools on the MOOSE framework to perform these reactor physics calculations. RattleSnake solves the linearized Boltzmann transport equation with a variety of solution meth­ ods. Various traditional reactor physics benchmarks have already been performed, but a more realistic light water reactor comparison was needed to solidify the status of the code and deter­ mine its fidelity. The INL team decided to use the Benchmark for Evaluation and Validation of Reactor Simulations, which was made available in early 2013. This benchmark is a one­ of-a-kind document assembled by the Massachusetts Institute of Technology, which includes two cycles of detailed, measured PWR operational data. The results from this initial study of the hot zero power conditions show the current INL analysis procedure with DRAGON4 cross section preparation and using the low order diffusion solver in RattleSnake for the whole core calculations yield very encouraging results for PWR analysis. The radial assembly power distributions, radial detector measurements and control rod worths were computed with good accuracy. The computation of the isothermal temperature coefficients of reactivity require further study.

  6. The investigation of the zero temperature coefficient point of power MOSFET

    Science.gov (United States)

    Bowen, Zhang; Xiaoling, Zhang; Wenwen, Xiong; Shuojie, She; Xuesong, Xie

    2016-06-01

    The paper investigates the zero temperature coefficient (ZTC) point of power MOSFET, based on the output characteristic of power MOSFET, the temperature coefficient of threshold voltage and the carrier mobility. It is found that the gate voltage has a big effect on the ZTC point. The result indicates that there are three types of temperature coefficient under different gate voltage. When the gate voltage is near the threshold voltage, both the linear region and saturation region shows a large positive temperature coefficient. With the increase of gate voltage, the temperature coefficient of the linear region changes from positive to negative, when the saturation region still remains positive, giving rise to the ZTC point. When the gate voltage is high enough, the negative temperature coefficient is present on both the linear and saturation region, resulting in no ZTC point. According to the experimental result, the change of ZTC point as a function of temperature is larger when the gate voltage is higher. The carrier mobility is also discussed, displaying a positive temperature coefficient at low gate voltage due to the free charge screen effect.

  7. Nuclear power research and development

    International Nuclear Information System (INIS)

    Research in the nuclear field must change, at least in the sense that more attention must be devoted to questions raised by non-specialists. This is necessary in order to convince society that nuclear energy can be applied safely and economically. Special attention must be paid to the prevention of accidents. There are several ways of approaching this aspect. One is the further development of the boiling-water reactor with natural circulation, such as operated by KEMA and GKN at Dodewaard. If communication with the non-specialists is improved, society will accept nuclear power, thus increasing the potential for nuclear growth throughout the world. (author)

  8. New dynamic method to measure rod worths in zero power physics test at PWR startup

    International Nuclear Information System (INIS)

    To measure and validate the worth of control (or shutdown) bank in zero power physics test at PWRs, a dynamic control rod reactivity measurement (DCRM) technique has been developed and applied to six startups of Westinghouse plants as well as Korea Standard Nuclear power Plants based on the Combustion Engineering System 80 NSSS. With this technique, just one test bank is inserted into the bottom of the core at maximum stepping rate and withdrawn immediately to the all rod-out position. Specially designed inverse point kinetics equations are used to determine the test bank worth from the measured ex-core detector signals, which are controlled by the neutron-to-response conversion factor and the dynamic-to-static conversion factor. These two parameters are predetermined by the three-dimensional neutron adjoint flux distribution for both the top and bottom ex-core detector and the three-dimensional steady and transient core power distribution for test bank movement. To eliminate the gamma-ray effect on ex-core detector signals, a simple method, using reactivity curve characteristics, was also developed. To verify the DCRM method, a total of 28 bank worths of six different PWRs was measured by the DCRM and compared with those of conventional method. Results show that the DCRM method has a similar accuracy as the conventional technique. However, with the DCRM method, it only takes ∼15 min per bank from the beginning of rod insertion to the determination of measured static worth. From its performance, one can conclude that the DCRM method is an effective replacement for the conventional rod worth measurement method

  9. New dynamic method to measure rod worths in zero power physics test at PWR startup

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E.K. [Korea Electric Power Research Institute, 103-16 Munji Yusung, Daejeon 305 380 (Korea, Republic of)]. E-mail: lek@kepri.re.kr; Shin, H.C. [Korea Electric Power Research Institute, 103-16 Munji Yusung, Daejeon 305 380 (Korea, Republic of); Bae, S.M. [Korea Electric Power Research Institute, 103-16 Munji Yusung, Daejeon 305 380 (Korea, Republic of); Lee, Y.K. [Korea Electric Power Research Institute, 103-16 Munji Yusung, Daejeon 305 380 (Korea, Republic of)

    2005-09-15

    To measure and validate the worth of control (or shutdown) bank in zero power physics test at PWRs, a dynamic control rod reactivity measurement (DCRM) technique has been developed and applied to six startups of Westinghouse plants as well as Korea Standard Nuclear power Plants based on the Combustion Engineering System 80 NSSS. With this technique, just one test bank is inserted into the bottom of the core at maximum stepping rate and withdrawn immediately to the all rod-out position. Specially designed inverse point kinetics equations are used to determine the test bank worth from the measured ex-core detector signals, which are controlled by the neutron-to-response conversion factor and the dynamic-to-static conversion factor. These two parameters are predetermined by the three-dimensional neutron adjoint flux distribution for both the top and bottom ex-core detector and the three-dimensional steady and transient core power distribution for test bank movement. To eliminate the gamma-ray effect on ex-core detector signals, a simple method, using reactivity curve characteristics, was also developed. To verify the DCRM method, a total of 28 bank worths of six different PWRs was measured by the DCRM and compared with those of conventional method. Results show that the DCRM method has a similar accuracy as the conventional technique. However, with the DCRM method, it only takes {approx}15 min per bank from the beginning of rod insertion to the determination of measured static worth. From its performance, one can conclude that the DCRM method is an effective replacement for the conventional rod worth measurement method.

  10. Estimation of ground reaction force and zero moment point on a powered ankle-foot prosthesis.

    Science.gov (United States)

    Martinez-Villalpando, Ernesto C; Herr, Hugh; Farrell, Matthew

    2007-01-01

    The ground reaction force (GRF) and the zero moment point (ZMP) are important parameters for the advancement of biomimetic control of robotic lower-limb prosthetic devices. In this document a method to estimate GRF and ZMP on a motorized ankle-foot prosthesis (MIT Powered Ankle-Foot Prosthesis) is presented. The method proposed is based on the analysis of data collected from a sensory system embedded in the prosthetic device using a custom designed wearable computing unit. In order to evaluate the performance of the estimation methods described, standing and walking clinical studies were conducted on a transtibial amputee. The results were statistically compared to standard analysis methodologies employed in a gait laboratory. The average RMS error and correlation factor were calculated for all experimental sessions. By using a static analysis procedure, the estimation of the vertical component of GRF had an averaged correlation coefficient higher than 0.94. The estimated ZMP location had a distance error of less than 1 cm, equal to 4% of the anterior-posterior foot length or 12% of the medio-lateral foot width. PMID:18003052

  11. Cell heterogeneity problems in the analysis of zero-power experiments

    International Nuclear Information System (INIS)

    Methods are described for treating plate and pin cell heterogeneity in the preparation of broad group cross-sections used in the analysis of zero-power fast reactor experiments. Methods used at Karlsruhe and Winfrith are summarized and compared, with particular reference to the treatment of resonance shielding, the calculation of broad group spatial fine structure, the treatment leakage and the calculation of anisotropic diffusion coefficients. The problems of cells near boundaries such as core-breeder interfaces and of singularities such as control rods are also considered briefly. Numerical studies carried out to investigate approximations in the methods are described. These include tests of the accuracy of one-dimensional cell-modelling techniques, and the validation by Monte Carlo of methods for treating streaming in the calculation of diffusion coefficients. Comparisons are shown between the heterogeneity effects calculated by the Karlsruhe and Winfrith methods for typical pin and plate cells used in the BIZET experimental programme, and their effect in a whole reactor calculation is indicated. Comparisons are given with measurements which provide tests of the heterogeneity calculations. These include reaction rate scans within pin and plate cells, and reaction rate measurements across sectors of pin and plate fuel, where the flux tilt is determined by the relative reactivity of the pin and plate cells. Finally, the heterogeneity problems arising in the interpretation of reaction rate measurements are discussed. (author)

  12. A zero power harmonic transponder sensor for ubiquitous wireless μL liquid-volume monitoring

    Science.gov (United States)

    Huang, Haiyu; Chen, Pai-Yen; Hung, Cheng-Hsien; Gharpurey, Ranjit; Akinwande, Deji

    2016-01-01

    Autonomous liquid-volume monitoring is crucial in ubiquitous healthcare. However, conventional approach is based on either human visual observation or expensive detectors, which are costly for future pervasive monitoring. Here we introduce a novel approach based on passive harmonic transponder antenna sensor and frequency hopping spread spectrum (FHSS) pattern analysis, to provide a very low cost wireless μL-resolution liquid-volume monitoring without battery or digital circuits. In our conceptual demonstration, the harmonic transponder comprises of a passive nonlinear frequency multiplier connected to a metamaterial-inspired 3-D antenna designed to be highly sensitive to the liquid-volume within a confined region. The transponder first receives some FHSS signal from an interrogator, then converts such signal to its harmonic band and re-radiates through the antenna sensor. The harmonic signal is picked up by a sniffer receiver and decoded through pattern analysis of the high dimensional FHSS signal strength data. A robust, zero power, absolute accuracy wireless liquid-volume monitoring is realized in the presence of strong direct coupling, background scatters, distance variance as well as near-field human-body interference. The concepts of passive harmonic transponder sensor, metamaterial-inspired antenna sensor, and FHSS pattern analysis based sensor decoding may help establishing cost-effective, energy-efficient and intelligent wireless pervasive healthcare monitoring platforms.

  13. RESEARCH ACTION: IMPLEMENTATION ZERO BASED BUDGET (ZBB IN THE PROVIDER SERVICE LEASING EQUIPAMENTS OF CARGO HANDLING.

    Directory of Open Access Journals (Sweden)

    Levi Gimenez

    2013-06-01

    Full Text Available This article aims to present the implementation of zero-based budgeting in a rental service provider of cargo handling equipment using the action research methodology. The goal was to examine the possibility of concomitant use of this instrument in service providers in need of accurate information that enables targeting at the best result in a setting avid for quick decisions and actions. Action research was used as research method. It was concluded that it is suitable for this branch, confirming its position as a useful model for restructuring and cutting costs, improving operational and financial results, and as a factor improving organizational environment (behavioral aspects, indirectly creating value to stakeholders.

  14. Zero power protection of generator%发电机零功率保护

    Institute of Scientific and Technical Information of China (English)

    乔永成; 寇海荣; 王云辉; 张道农

    2011-01-01

    大型汽轮发电机组突然甩负荷,会使汽轮机组超速、发电机变压器组过电压.利用发电机有功功率作为特征量,通过判断发电机机端有功功率值在极短时间内从一高值(PF>)降至一低值(PF),以机组快速减负荷(RB)工况有功功率的1/3为参考值;有功功率低值(PR<)以发电机组厂用电作为参考值,再加上发电机低电压与主汽门关闭闭锁判据,就能正确区分发电机组是否发生了甩负荷工况.由此判据构成的发电机零功率保护可在发电机组甩负荷初始时间内做出快速反应,能够在发电机突然甩负荷时关闭主汽门、灭磁,将机组转速、端电压升高幅度降至最低.结合某电厂在送出系统中断导致发电机功率不能送出,发电机零功率保护快速动作于全停来保障机组安全的实例,论证了发电机组装设零功率保护的必要性.%Sudden load rejection will lead to the overspeed of turbo-generator and the overvoltage of unit-generator. The sudden drop of generator output active power from PF> to PF< is taken as the criteria,together with the blocking condition of low voltage of generator or close of main steam valve,to detect the load rejection. The PF> is set as onethird of the active power of unit in RB operation and the PF< as the plant power consumption. According to it,the zero power protection can response at the very beginning of load rejection. It shuts down the main steam valve and deexcites the generator to limit the increase of generator rotating speed and terminal voltage. Site operation shows its necessity for the secure operation of unit.

  15. Power Relations: Their Embodiment in Research.

    Science.gov (United States)

    Florczak, Kristine L

    2016-07-01

    The purpose of this column is to consider the notion of power in research. To that end, the idea of power is considered from the perspective of philosophy and then linked to a nursing concept analysis that compares the differences between power over and power to. Then, the nature of power relations is compared and contrasted between quantitative and qualitative methodologies. PMID:27271128

  16. Research in power systems: power quality and electricity market

    OpenAIRE

    Amarís Duarte, Hortensia; Usaola, Julio

    2008-01-01

    The research group REDES from UC3M has experience on electricity market, grid integration of wind energy and power quality. The group may offer consulting activities with a high component of research. We are looking for the collaboration of companies devoted to the consulting related to electricity markets, the integration of wind power in the electricity network, and with power quality.

  17. Research Developments on Power System Integration of Wind Power

    DEFF Research Database (Denmark)

    Chen, Zhe; Hansen, Jens Carsten; Qiuwei, Wu; Hansen, Anca Daniela; Bak-Jensen, Birgitte

    2011-01-01

    This paper presents an overview on the recent research activities and tendencies regarding grid integration of wind power in Denmark and some related European activities, including power electronics for enhancing wind power controllability, wind turbines and wind farms modeling,wind power...

  18. ANL results for LMFR reactivity coefficients benchmark

    International Nuclear Information System (INIS)

    The fast reactor analysis methods developed at ANL were extensively tested in ZPR and ZPPR experiments, applied to EBR-2 and FFTF test reactors. The basic nuclear data library used was ENDF/B-V.2 with the ETOE-2 data processing code and the ENDF/B-VI. Multigroup constants were generated by Monte Carlo code MCNP2-2. Neutron flux calculation were done by DIF3D code applying neutron diffusion theory and finite difference method. The results obtained include basic parameters; fuel and structure regional Doppler coefficients; geometry expansion fuel coefficients; kinetics parameters. In general, agreement between phase 1 and 2 results were excellent

  19. A user's guide to the PLTEMP/ANL code.

    Energy Technology Data Exchange (ETDEWEB)

    Kalimullah, M. (Nuclear Engineering Division)

    2011-07-05

    PLTEMP/ANL V4.1 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of-Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

  20. A User's Guide to the PLTEMP/ANL Code

    Energy Technology Data Exchange (ETDEWEB)

    Olson, Arne P. [Argonne National Lab. (ANL), Argonne, IL (United States); Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-07-07

    PLTEMP/ANL V4.2 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of- Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst’s time.

  1. A User's Guide to the PLTEMP/ANL Code

    International Nuclear Information System (INIS)

    PLTEMP/ANL V4.2 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of- Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

  2. MEASUREMENT ERROR EFFECT ON THE POWER OF THE CONTROL CHART FOR ZERO-TRUNCATED BINOMIAL DISTRIBUTION UNDER STANDARDIZATION PROCEDURE

    Directory of Open Access Journals (Sweden)

    Anwer Khurshid

    2014-12-01

    Full Text Available Measurement error effect on the power of control charts for zero truncated Poisson distribution and ratio of two Poisson distributions are recently studied by Chakraborty and Khurshid (2013a and Chakraborty and Khurshid (2013b respectively. In this paper, in addition to the expression for the power of control chart for ZTBD based on standardized normal variate is obtained, numerical calculations are presented to see the effect of errors on the power curve. To study the sensitivity of the monitoring procedure, average run length (ARL is also considered.

  3. Recommended documentation for computer users at ANL

    Energy Technology Data Exchange (ETDEWEB)

    Heiberger, A.A.

    1992-04-01

    Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

  4. Studies into operating conditions of ground-fault zero-current protection in 6000 V mine power systems. [Poland

    Energy Technology Data Exchange (ETDEWEB)

    Lucyk, W.

    1984-01-01

    Ground-fault protection systems for 6000 V power systems in underground black coal mines are evaluated. Using the ZSG-6 and UZP-12 protection systems is associated with high cost due to the complicated design of electronic elements of the systems and use of filters for zero sequence voltage. Evaluations are aimed at determining whether the expensive conventional protection system could be replaced by less expensive ground-fault protection of zero sequence voltage type (the system measures zero sequence voltage). Conditions for use of ground-fault protection of zero sequence voltage type in underground mining are characterized: size of power systems, structure of the system, types of electrical equipment in the system. Effects of ground-fault protection on operation of equipment with electric motors are analyzed. Safety regulations which characterize requirements for ground-fault protection are discussed. Electrical equipment used in ground-fault protection systems developed in Poland (by ZWAR, EMAG and the Automation and Measurement Center of the Knurow mine) is characterized. Recommendations are made on use of ground-fault protection in underground coal mines. 4 references.

  5. Power Production with Zero Atmospheric Emissions for the 21st Century

    International Nuclear Information System (INIS)

    This paper describes a new concept for economically producing power without atmospheric emissions of regulated or greenhouse gases. A 5-MW to 10-MW experimental electric power generating plant is being designed for installation at the Lawrence Livermore National Laboratory to perform research to develop the new technology and to demonstrate its reliability. The research electric power generating plant will burn any gaseous fuel, including syngas derived from coal, with oxygen. Natural gas and oxygen will be used initially to produce a mixture of steam and carbon dioxide. The mixture will be delivered to three turbines in series to produce electricity. After leaving the low-pressure turbine, the gaseous mixture will be cooled in a condenser where the carbon dioxide separates from the steam. The carbon dioxide will be pumped into a local oil formation, which is located at a depth of 460 m below ground adjacent to the Laboratory. In the more general siting case, the carbon dioxide would be pumped into deep underground permeable strata. The natural gas will be combusted with oxygen in a gas generator to produce the turbine working fluid. Three turbines will drive an electric generator to generate electricity. In the first phase of the research, the plant will use three commercially available steam turbines that operate at a temperature of 566 C. In a second phase, the high- and low-pressure turbines will be replaced by turbines using uncooled blade technology developed by the US Department of Energy (DOE) to permit a turbine operation temperature of 816 C. The intermediate turbine will use actively cooled gas turbine technology and operate at a temperature of 1,425 C. This plant will have an efficiency of 50%. DOE has funded research to reduce the cost of oxygen generation using ceramic membranes. When this technology becomes available and when high-temperature steam turbines are developed, efficiencies of 60% are expected, including the energy cost of carbon dioxide

  6. Sliding mode controller for four leg shunt active power filter to eliminating zero sequence current, compensating harmonics and reactive power with fixed switching frequency

    Directory of Open Access Journals (Sweden)

    Chebabhi Ali

    2015-01-01

    Full Text Available In this paper, the four leg inverter controlled by the three dimensional space vector modulation (3D SVM is used as the shunt active power filter (SAPF for compensating the three phase four wire electrical network, by using the four leg inverter with 3D SVM advantages to eliminated zero sequence current, fixed switching frequency of inverter switches, and reduced switching losses. This four leg inverter is employed as shunt active power filter to minimizing harmonic currents, reducing magnitude of neutral wire current, eliminating zero sequence current caused by nonlinear single phase loads and compensating reactive power, and a nonlinear sliding mode control technique (SMC is proposed for harmonic currents and DC bus voltage control to improve the performances of the three phase four wire four leg shunt active power filter based on Synchronous Reference Frame (SRF theory in the dq0 axes, and to decoupling the four leg SAPF mathematical model.

  7. Renewal of safety circuitry on a zero-energy research reactor using microprocessor units

    International Nuclear Information System (INIS)

    The conventional hard-wired safety-circuitry of the zero-energy research reactor at the Central Electricity Generating Board's Berkeley Nuclear Laboratories is being replaced by microprocessor-based units. The Paper describes how levels of reliability that are necessary for safety circuitry have been achieved by the use of two entirely different guard line systems based on a Motorola 6800 microprocessor and an Intel 8085A microprocessor. The two systems operate in parallel and either will trip the reactor. Each has been programmed by a different programmer using different philosophies. The two units and the test programme involving over 106 simulated guard line trips are described. An overall reliability of better than 10-6 per annum is claimed. (author)

  8. Steady state thermal hydraulics analysis of GHARR-1 using the pl temp/anl v 4.0 code

    International Nuclear Information System (INIS)

    Thermal-hydraulics analysis of the Ghana Research Reactor-1 (GHARR-1) has been carried out. The reactor consists of an assembly of 344 HEU vertical fuel rods cooled by natural convection. The Steady State thermal-hydraulics Analysis of the axial temperature distributions of the fuel rods, cladding surface and coolant channels in a sub-cooled boiling regime using the PLTEMP/ANL v 4.0 code has been modeled. External coupling of the Monte Carlo N Particle version 5 (MCNP5) Code provided the axial power peaking factors that sufficed the entire modeling process. At a steady state inlet temperature of 30°Celsius and pressure of 0.1237 MPa, the peak fuel and clad surface temperatures were predicted to be 110.55°Celsius and 104.25°Celsius respectively which are all below the eutectic temperature of the U-Al alloy i.e. (640°Celsius). The maximum outlet coolant temperature was predicted to be 50°Celsius giving a coolant temperature rise of 20°Celsius. Standard correlations in the PLTEMP/ANL code was used to compute the various axial properties of the fuel rods such as: coolant flow rates, coolant velocity, density, pressure drop, heat fluxes, fractional powers per rod at the margins to Onset-of-Nucleate Boiling (ONB), Minimum Departure from Nucleate Boiling ratio (MDNBR) and the Minimum Flow instability Power ratio (FIR). Most of the model predictions in this study were consistent with experimental results in the Safety Analysis Report (SAR). Outcomes of the research certify that GHARR-1 can be operated at a steady state thermal power of 30kW without compromising on safety. (au)

  9. Pulsed Neutron Measurements on a Heavy Water Power Reactor (MZFR) at Zero Energy

    International Nuclear Information System (INIS)

    The pulsed neutron method was used for zero-power measurements in the core of a heavy water reactor. Various methods were used for the evaluation of the pulsed measurements. The so-called ''integral'' evaluation methods are based on theories published by Sjöstrand and Gozani; so far they have been applied mainly to light water reactors. These methods use not only the prompt neutron decay constant but also the information contained in the delayed neutron tails to determine the reactivity. For measurements on the heavy water reactor, however, the methods had to be modified so as to adequately take into account the time dependence of the delayed neutrons. The fraction of the delayed neutrons was calculated using a reasonable assumption for its time dependence. All the information needed could be obtained from the measurements. These methods are well suited for hand calculations to yield the reactivity with proper accuracy. An analytical procedure was applied to check the results of the integral methods. This essentially involves the exact calculation of the time dependence of the delayed neutron fraction by an iteration procedure. The results of the different evaluation methods mentioned above are compared by plotting them as functions of the D2O level and of the boron concentration. Due to the inclined control rods the flux distribution is distorted in a rather complicated manner when the rods are inserted. Therefore the time dependence of this distribution was measured for different positions of the pulsed neutron source. It was possible to find one position for which the influence of higher modes on the measurements of the shutdown reactivity was sufficiently small. Finally it is shown that the values of (δρ(H, ci)/δ(l/H2)) H = Hi and (δρ(Hi, c)/δc) c = ci (ρ reactivity, Hi critical D2O level for boron concentration c1) obtained by period measurements in the slightly supercritical state and pulsed measurements in the subcritical state are in excellent

  10. Concept and measures of radioactive liquid effluents 'near-zero release' in inland nuclear power plants

    International Nuclear Information System (INIS)

    The radioactive liquid effluents of inland NPPs are discharged into inland surface water. In order to better protect the public and environment, the Chinese national standards, GB 6249-2011 and GB 14587-2011, put forward more stringent requirements on release concentrations of inland NPPs than that of coastal NPPs. It means in fact a target of 'near-zero release' of radioactive liquid effluents for inland NPPs. This paper sets forth the concept of 'near-zero release' of radioactive liquid effluents for inland NPPs, and also describes measures that should be taken to achieve this target. (authors)

  11. Three-Phase High-Power and Zero-Current-Switching OBC for Plug-In Electric Vehicles

    OpenAIRE

    Cheng-Shan Wang; Wei Li; Zhun Meng; Yi-Feng Wang; Jie-Gui Zhou

    2015-01-01

    In this paper, an interleaved high-power zero-current-switching (ZCS) onboard charger (OBC) based on the three-phase single-switch buck rectifier is proposed for application to plug-in electric vehicles (EVs). The multi-resonant structure is used to achieve high efficiency and high power density, which are necessary to reduce the volume and weight of the OBC. This study focuses on the border conditions of ZCS converting with a battery load, which means the variation ranges of the output volta...

  12. Study of reactor parameters of on critical systems, Phase I: Safety report for RB zero power reactor

    International Nuclear Information System (INIS)

    In addition to the safety analysis for the zero power RB reactor, this report contains a general description of the reactor, reactor components, auxiliary equipment and the reactor building. Reactor Rb has been reconstructed during 1961-1962 and supplied with new safety-control system as well as with a complete dosimetry instrumentation. Since RB reactor was constructed without shielding special attention is devoted to safety and protection of the staff performing experiments. Due to changed circumstances in the Institute ( start-up of the RA 7 MW power reactor) the role of the RB reactor was redefined

  13. Advancing Concentrating Solar Power Research (Fact Sheet)

    Energy Technology Data Exchange (ETDEWEB)

    2014-02-01

    Researchers at the National Renewable Energy Laboratory (NREL) provide scientific, engineering, and analytical expertise to help advance innovation in concentrating solar power (CSP). This fact sheet summarizes how NREL is advancing CSP research.

  14. RESEARCH ON THE ZERO-CURRENT OPENING BASED ON THE WORKING PATTERN OF THE HIGH TEMPERATURE SUPERCONDUCTING HYBRID PULSE POWER TRANSFORMER%钙和铈二元掺杂对钇钡铜氧超导体性能的影响

    Institute of Scientific and Technical Information of China (English)

    吴锐; 程志; 桂志兴; 李海涛; 严仲明; 王豫

    2012-01-01

    超导储能脉冲功率系统中,关键的电路元件是断路开关,它的关断性能直接决定了输出脉冲的特性,传统的直接截流断路方法不仅会产生大电弧影响关断损耗,还会在断路瞬间产生高峰值的过电压脉冲.针对直接截流方法的缺点,本文提出了一种基于混合脉冲变压器(HPPT)工作模式的新型开关断路方法,该方法采用电流过零瞬时断路方式换流.经过理论分析和仿真,验证了该方法的正确性与可行性,对同类开关断路技术的研究提供了十分重要的参考依据.%In the superconducting magnet energy storage pulsed power system, the key component of circuit is the opening switch, its opening performance directly determines characteristics of the output pulse. The traditional method of direct interruption not only produces large arc, but also transiently produces the high peak of over-voltage pulse. Based on the shortcoming of direct interruption and the working pattern of the hybrid pulse power transform- er(HPPT), the paper puts forward a new opening method which uses the zero-current conversion. Through theoretical analysis and simulation, the correctness and feasibility have been verified and it provides some important references for the study on the congener switching opening technology.

  15. NUMERICAL ALGORITHMS AT NON-ZERO CHEMICAL POTENTIAL. PROCEEDINGS OF RIKEN BNL RESEARCH CENTER WORKSHOP, VOLUME 19

    Energy Technology Data Exchange (ETDEWEB)

    BLUM,T.

    1999-09-14

    The RIKEN BNL Research Center hosted its 19th workshop April 27th through May 1, 1999. The topic was Numerical Algorithms at Non-Zero Chemical Potential. QCD at a non-zero chemical potential (non-zero density) poses a long-standing unsolved challenge for lattice gauge theory. Indeed, it is the primary unresolved issue in the fundamental formulation of lattice gauge theory. The chemical potential renders conventional lattice actions complex, practically excluding the usual Monte Carlo techniques which rely on a positive definite measure for the partition function. This ''sign'' problem appears in a wide range of physical systems, ranging from strongly coupled electronic systems to QCD. The lack of a viable numerical technique at non-zero density is particularly acute since new exotic ''color superconducting'' phases of quark matter have recently been predicted in model calculations. A first principles confirmation of the phase diagram is desirable since experimental verification is not expected soon. At the workshop several proposals for new algorithms were made: cluster algorithms, direct simulation of Grassman variables, and a bosonization of the fermion determinant. All generated considerable discussion and seem worthy of continued investigation. Several interesting results using conventional algorithms were also presented: condensates in four fermion models, SU(2) gauge theory in fundamental and adjoint representations, and lessons learned from strong; coupling, non-zero temperature and heavy quarks applied to non-zero density simulations.

  16. Power Analysis Software for Educational Researchers

    Science.gov (United States)

    Peng, Chao-Ying Joanne; Long, Haiying; Abaci, Serdar

    2012-01-01

    Given the importance of statistical power analysis in quantitative research and the repeated emphasis on it by American Educational Research Association/American Psychological Association journals, the authors examined the reporting practice of power analysis by the quantitative studies published in 12 education/psychology journals between 2005…

  17. The Relationship between Teachers' and Principals' Decision-Making Power: Is It a Win-Win Situation or a Zero-Sum Game?

    Science.gov (United States)

    Shen, Jianping; Xia, Jiangang

    2012-01-01

    Is the power relationship between public school teachers and principals a win-win situation or a zero-sum game? By applying hierarchical linear modeling to the 1999-2000 nationally representative Schools and Staffing Survey data, we found that both the win-win and zero-sum-game theories had empirical evidence. The decision-making areas…

  18. Effective switching mode power supplies common mode noise cancellation technique with zero equipotential transformer models

    OpenAIRE

    Pong, MH; Chan, YP; Poon, NK; Liu, CP

    2010-01-01

    In this paper a transformer construction technique is proposed that effectively cut off the Common Mode (CM) noise voltage passing across the isolated primary and secondary windings. This technique employs the Zero Equipotential Line theory to construct an anti-phase winding. It effectively cuts down CM noise by eliminating the noise voltage across the isolated primary and secondary windings. The concept of maintaining an equipotential line along the bobbin and quiet node connections are just...

  19. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes

    International Nuclear Information System (INIS)

    Research highlights: → The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. → The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). → The most important conclusion is that all obtained values of DNBR, fuel center and surface temperature, cladding surface temperature and coolant temperature across the hottest channel are largely far to compromise safety of the reactor. - Abstract: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. In order to validate our PARET/ANL and COOLOD-N2 models, the fuel center temperature as function of core power was calculated and compared with the corresponding experimental values. The comparison indicates that the calculated values are in satisfactory agreement with the measurement. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). Therefore, we have calculated the departure from nucleate boiling ratio (DNBR), fuel center and surface temperature, cladding surface temperature and coolant temperature profiles across the hottest channel. The most important conclusion is that all obtained values are largely far to compromise safety of the reactor.

  20. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes

    Energy Technology Data Exchange (ETDEWEB)

    Boulaich, Y., E-mail: boulaich@cnesten.org.m [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Nacir, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); El Bardouni, T.; Zoubair, M. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); El Bakkari, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Merroun, O. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); El Younoussi, C. [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Htet, A. [CEN-Maamora, CNESTEN, Rabat (Morocco); Boukhal, H. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Chakir, E. [LRM/EPTN, Department of Physics, Faculty of Sciences, Kenitra (Morocco)

    2011-01-15

    Research highlights: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). The most important conclusion is that all obtained values of DNBR, fuel center and surface temperature, cladding surface temperature and coolant temperature across the hottest channel are largely far to compromise safety of the reactor. - Abstract: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. In order to validate our PARET/ANL and COOLOD-N2 models, the fuel center temperature as function of core power was calculated and compared with the corresponding experimental values. The comparison indicates that the calculated values are in satisfactory agreement with the measurement. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). Therefore, we have calculated the departure from nucleate boiling ratio (DNBR), fuel center and surface temperature, cladding surface temperature and coolant temperature profiles across the hottest channel. The most important conclusion is that all obtained values are largely far to compromise safety of the reactor.

  1. The role of nuclear power in the option zero emission technologies for fossil fuels

    International Nuclear Information System (INIS)

    The energy sector is one of the main sources of greenhouse gas (GHG) emissions particularly carbon dioxide (CO2) increasing concerns due to their potential risk to induce global warming and climate change. The Parties having signed the Kyoto Protocol in December 1997, committed to decrease their GHG emissions. The Protocol states that countries shall undertake promotion, research, development and increased use of new and renewable forms of energy, of carbon dioxide sequestration technologies and of advanced and innovative environmentally sound technologies. The one significant option that is not specifically mentioned is nuclear energy which is essentially carbon-free. There are a number of technical options that could help reducing, or at least slowing the increase of, GHG emissions from the energy sector. The list of options includes: improving the efficiency of energy conversion and end-use processes; shifting to less carbon intensive energy sources (e.g. shifting from coal to natural gas); developing carbon-free or low-carbon energy sources; and carbon sequestration (e.g. planting forests or capturing and storing carbon dioxide). It must be pointed out that nuclear power is one of the few options that are currently available on the market, competitive in a number of countries, especially if global costs to society of alternative options are considered; practically carbon-free; and sustainable at large-scale deployment. The nuclear power could play significant role in alleviating the risk of global climate change. The main objective of the article is to present sequestration options, their cost evaluation as well as comparation with alternative possibilities of nuclear energy production. (author)

  2. Researcher/Researched: Relations of Vulnerability/Relations of Power

    Science.gov (United States)

    Huckaby, M. Francyne

    2011-01-01

    Turning to reflexive journals and fieldnotes, the author reconsiders Foucault's "relations of power" through her experiences with five research participants, who are professors of education. The paper explores: (1) the translation of Foucault for an analysis of power; (2) the dynamics of researching up and analyzing from below; and (3) the…

  3. MIT research reactor. Power uprate and utilization

    International Nuclear Information System (INIS)

    The MIT Research Reactor (MITR) is a university research reactor located on MIT campus. and has a long history in supporting research and education. Recent accomplishments include a 20% power rate to 6 MW and expanding advanced materials fuel testing program. Another important ongoing initiative is the conversion to high density low enrichment uranium (LEU) monolithic U-Mo fuel, which will consist of a new fuel element design and power increase to 7 MW. (author)

  4. Wireless power transmission for biomedical implants: The role of near-zero threshold CMOS rectifiers.

    Science.gov (United States)

    Mohammadi, Ali; Redoute, Jean-Michel; Yuce, Mehmet R

    2015-01-01

    Biomedical implants require an electronic power conditioning circuitry to provide a stable electrical power supply. The efficiency of wireless power transmission is strongly dependent on the power conditioning circuitry specifically the rectifier. A cross-connected CMOS bridge rectifier is implemented to demonstrate the impact of thresholds of rectifiers on wireless power transfer. The performance of the proposed rectifier is experimentally compared with a conventional Schottky diode full wave rectifier over 9 cm distance of air and tissue medium between the transmitter and receiver. The output voltage generated by the CMOS rectifier across a 1 KΩ resistive load is around twice as much as the Schottky rectifier. PMID:26737525

  5. Preparation of mandatory documentation before the start up of the RA-0 'zero power' nuclear reactor at Cordoba National University

    International Nuclear Information System (INIS)

    Before the start up of the RA-0 'zero power' nuclear reactor installed at Cordoba National University, it was necessary to send to the Regulatory Authority the mandatory documentation which is required in the licensing process. With the previous papers existing for the operation in the first years of the '70, a work program for the future operational training personnel was elaborated. Based on the Authority's applicable rules and the recommendations and with particular criteria originated in the working university conditions, the SAFETY report of RA-0 nuclear reactor was prepared. This paper describes the principal contents, items and documents involved in the safety report. (Author)

  6. Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois

    Energy Technology Data Exchange (ETDEWEB)

    W. C. Adams

    2007-05-25

    Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory’s Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007).

  7. ANL experimental program for pulsed superconducting coils

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) had recognized the clear advantage of a superconducting ohmic-heating (OH) coil and started in aggressive development program in FY 1977. The main objectives for FY 1977 are to develop cryostable basic cable configurations with reasonably low ac losses, to develop 12 kA cryostable cable, using it to design and build a 1.5 MJ pulsed coil, and to develop a rather inexpensive large fiberglass reinforced helium cryostat for the 1.5 MJ pulsed coil. The principal objective in building the 1.5 MJ ac coil is to demonstrate ac cryostability of a large coil ranging from 2 T/s up to 12 T/s. Another objective in the pulsed coil program is to determine the feasibility of parallel coil operation in order to avoid excessive voltage and current requirements and to minimize the number of turns for the equilibrium field (EF) coils, should the EF coils be connected in parallel with the OH coils. A two-coil section model using the 11 kA cable will be built and tested

  8. Research Overview on Wireless Power Transmission Technology

    Directory of Open Access Journals (Sweden)

    Li Tao

    2015-01-01

    Full Text Available According to the latest researches, this paper outlines the development of wireless power transmission and introduces the latest applications of wireless power transmission in life. To describe the wireless power transmission technologies in detail, the paper presents the short-range, medium-range and remote wireless power transmission, respectively. In addition, the paper also depicts some unique properties of wireless power transmission system to make readers understand WPT system better. At last, the existing problems and developing trends are presented.

  9. Large capacity cnergy from Geo- Plutonic formation for power plants with zero CO2 emissions

    Directory of Open Access Journals (Sweden)

    R.H. Kozłowski

    2010-12-01

    Full Text Available Purpose: The publication presented is a realistic, one of the practicable idea for a substitute to system power plants, consisting in the construction of combined heat and power plants using renewable resources of geo-plutonic energy.Design/methodology/approach: There are various methods of obtaining geothermal energy and various uses for it. The proposed GEO-PLUTONIC ENERGY represents an endless, renewable source of energy coming from nuclear reaction in the Earth’s nucleus, where the temperature reaches 6,000 Centigrade. Mass production of electricity from the Earth’s heat, possible in Iceland due to the volcanic nature of these resources and the shallow depth at which they occur, was difficult in other countries due to the high cost of drilling to greater depths. This barrier has been overcome by us through using a special horizontal drilling technique.Findings: In order to extract and collect the accumulated energy from the area of a large thermal field, a modified shaft/drilling system (called a Super Daisy System equipped with a 3D grate of directional bore-holes called Jet-Stingers fitted with multi-functional heat exchangers is used. The emission-free concept of Geo-Plutonic Energy with the temperature of only over 250ºC, from which we can obtain about 30 MPa of pressure on the turbine. With increased the depth the temperature and heat transmissibility will be raised significantly, which can resulted the yield even to 7-10 MWe (of electricity from one deep heat exchanger.Research limitations/implications: From the rock mass we can collect renewable resources of ,,dry” ascending energy from the paleo heat flow coming from the great atomic furnace – the magma.Originality/value: We are experienced in using the appropriate hydro-thermodynamic theory and its applications which allows us to almost precisely forecast and control the quantity of heat not exceeding 20% of the 100% regeneration capability in the same time range.

  10. Analysis of Zero CO2 Emission SOFC Hybrid Power System%CO2零排放的SOFC复合动力系统分析

    Institute of Scientific and Technical Information of China (English)

    张潇元; 段立强

    2011-01-01

    Based on the Aspen-plus soft, SOFC stack model is established. The SOFC hybrid power system without CO2 capture is designed. Then, the zero CO2 emission SOFC hybrid power system is proposed. The performances of these two systems are compared and analyzed. With the mode of pure oxygen combustion, the outlet gas of zero CO2 emission SOFC hybrid power system is composed of only CO2 and steam, so it is easy to get CO2 with higher concentration by means of condensation. Compared with the conventional power system with CO2 capture, the energy consumption of CO2 capture in the new system decreases a lot. This paper also analyzes the effects of the main parameters on the performance of the hybrid power system. Above research achievements will provide the useful guide for further study on zero CO2 emission SOFC hybrid power system.%基于Aspen-Plus软件建立了SOFC电池堆的模型,设计了不回收CO2的SOFC复合动力系统,针对系统特点,提出了CO2零排放的SOFC复合动力系统,对这两种系统的性能进行了详细的比较和分析.CO2零排放系统利用纯氧燃烧方式得到的燃烧产物只有CO2和水蒸气,通过冷凝得到高浓度的CO2.与带CO2脱除的常规电厂相比,极大地降低了回收CO2的能耗.通过对主要参数(燃料利用率、蒸汽/碳比、运行压力等)进行优化,详细分析了各主要参数对系统性能的影响.本文研究成果将为进一步研究高效的CO2零排放SOFC复合动力系统提供有益的参考.

  11. Thermal noise informatics: totally secure communication via a wire, zero-power communication, and thermal noise driven computing

    Science.gov (United States)

    Kish, Laszlo B.; Mingesz, Robert; Gingl, Zoltan

    2007-06-01

    Very recently, it has been shown that Gaussian thermal noise and its artificial versions (Johnson-like noises) can be utilized as an information carrier with peculiar properties therefore it may be proper to call this topic Thermal Noise Informatics. Zero Power (Stealth) Communication, Thermal Noise Driven Computing, and Totally Secure Classical Communication are relevant examples. In this paper, while we will briefly describe the first and the second subjects, we shall focus on the third subject, the secure classical communication via wire. This way of secure telecommunication utilizes the properties of Johnson(-like) noise and those of a simple Kirchhoff's loop. The communicator is unconditionally secure at the conceptual (circuit theoretical) level and this property is (so far) unique in communication systems based on classical physics. The communicator is superior to quantum alternatives in all known aspects, except the need of using a wire. In the idealized system, the eavesdropper can extract zero bit of information without getting uncovered. The scheme is naturally protected against the man-in-the-middle attack. The communication can take place also via currently used power lines or phone (wire) lines and it is not only a point-to-point communication like quantum channels but network-ready. We report that a pair of Kirchhoff-Loop-Johnson(-like)-Noise communicators, which is able to work over variable ranges, was designed and built. Tests have been carried out on a model-line with ranges beyond the ranges of any known direct quantum communication channel and they indicate unrivalled signal fidelity and security performance. This simple device has single-wire secure key generation/sharing rates of 0.1, 1, 10, and 100 bit/second for copper wires with diameters/ranges of 21 mm / 2000 km, 7 mm / 200 km, 2.3 mm / 20 km, and 0.7 mm / 2 km, respectively and it performs with 0.02% raw-bit error rate (99.98 % fidelity). The raw-bit security of this practical system

  12. Minimal zero-sum sequence of length five over finite cyclic groups of prime power order

    OpenAIRE

    Xia, Li-meng; Li, Yuanlin; Peng, Jiangtao

    2014-01-01

    Let $G$ be a finite cyclic group. Every sequence $S$ of length $l$ over $G$ can be written in the form $S=(x_1g)\\cdot\\ldots\\cdot(x_lg)$ where $g\\in G$ and $x_1, \\ldots, x_l\\in[1, \\ord(g)]$, and the index $\\ind(S)$ of $S$ is defined to be the minimum of $(x_1+\\cdots+x_l)/\\ord(g)$ over all possible $g\\in G$ such that $\\langle g \\rangle =G$. Recently the second and the third authors determined the index of any minimal zero-sum sequence $S$ of length 5 over a cyclic group of a prime order where $...

  13. ANL progress in developing an LEU target and process for Mo-99 production: Cooperation with CNEA

    International Nuclear Information System (INIS)

    The primary mission of the Reduced Enrichment in Research and Test Reactors (RERTR) Program is to facilitate the conversion of research and test-reactor fuel and targets from high-enriched uranium (HEU) to low-enriched uranium (LEU). One of the current goals at Argonne National Laboratory (ANL) is to assist the Argentine Comision Nacional de Energia Atomica (CNEA) in developing an LEU foil target and a process for 99Mo production. Specifically addressed in this paper is ANL R and D related to this conversion: (1) designing a prototype production vessel for digesting irradiated LEU foils in alkaline solutions and (2) developing a new digestion method to address all issues related to HEU to LEU conversion. (author)

  14. Colloid-Associated Radionuclide Concentration Limits: ANL

    International Nuclear Information System (INIS)

    The purpose and scope of this report is to describe the analysis of available colloidal data from waste form corrosion tests at Argonne National Laboratory (ANL) to extract characteristics of these colloids that can be used in modeling their contribution to the source term for sparingly soluble radioelements (e.g., Pu). Specifically, the focus is on developing a useful description of the following waste form colloid characteristics: (1) composition, (2) size distribution, and (3) quantification of the rate of waste form colloid generation. The composition and size distribution information are intended to support analysis of the potential transport of the sparingly soluble radionuclides associated with the waste form colloids. The rate of colloid generation is intended to support analysis of the waste form colloid-associated radionuclide concentrations. In addressing the above characteristics, available data are interpreted to address mechanisms controlling colloid formation and stability. This report was developed in accordance with the ''Technical Work Plan for Waste Form Degradation Process Model Report for SR'' (CRWMS M and O 2000). Because the end objective is to support the source term modeling we have organized the conclusions into two categories: (1) data analysis conclusions and (2) recommendations for colloid source term modeling. The second category is included to facilitate use of the conclusions from the data analysis in the abstraction of a colloid source term model. The data analyses and conclusions that are presented in this report are based on small-scale laboratory tests conducted on a limited number of waste glass compositions and spent fuel types

  15. Three-Phase High-Power and Zero-Current-Switching OBC for Plug-In Electric Vehicles

    Directory of Open Access Journals (Sweden)

    Cheng-Shan Wang

    2015-06-01

    Full Text Available In this paper, an interleaved high-power zero-current-switching (ZCS onboard charger (OBC based on the three-phase single-switch buck rectifier is proposed for application to plug-in electric vehicles (EVs. The multi-resonant structure is used to achieve high efficiency and high power density, which are necessary to reduce the volume and weight of the OBC. This study focuses on the border conditions of ZCS converting with a battery load, which means the variation ranges of the output voltage and current are very large. Furthermore, a novel hybrid control method combining pulse frequency modulation (PFM and pulse width modulation (PWM together is presented to ensure a driving frequency higher than 10 kHz, and this will reduce the unexpected inner resonant power flow and decrease the total harmonic distortion (THD of the input current under a light load at the end of the charging process. Finally, a prototype is established, and experiments are carried out. According to the experimental results, the conversion efficiency is higher than 93.5%, the THD about 4.3% and power factor (PF 0.98 under the maximum power output condition. Besides, a three-stage charging process is also carried out the experimental platform.

  16. Technical Note: Zero Emissions Power Generation with CO2 Reduction by Fayalite

    OpenAIRE

    Akinfiev, Nikolay; McGovern, James; Yantovski, Evgeny

    2005-01-01

    In this paper a new ‘fuel’, fayalite Fe2SiO4, is proposed tentatively and a new concept involving the convergence of a power plant and its fuel source is described. The CO2 from the power plant would be injected underground where it would be reduced to methane. The methane would then serve as the ‘derived fuel’ of the power plant having been produced by the reaction of fayalite with the CO2. One of the possible chemical reactions of CO2 with rock is indicated, along wi...

  17. Electric Power Research in 1988 No. 5

    International Nuclear Information System (INIS)

    This book deals with eight fields of electric power, which are study on the high level of confidence of electronic control system with micro computers in a field of generator, study on the emergency scenarios of radiation in nuclear power plant in a field of nuclear energy, research for improvement of record and calculation of SCADA system in a field of supply of electric power, study on the utilization and survey of domestic Bio-mass in a field of energy, and study on the digital communications net for electric power in a field of communication.

  18. Power Control Method for Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Baang, Dane; Suh, Yongsuk; Park, Cheol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Considering safety-oriented design concept and other control environment, we developed a simple controller that provides limiting function of power change- rate as well as fine tracking performance. The design result has been well-proven via simulation and actual application to a TRIGA-II type research reactor. The proposed controller is designed to track the PDM(Power Demand) from operator input as long as maintaining the power change rate lower than a certain value for stable reactor operation. A power control method for a TRIGA-II type research reactor has been designed, simulated, and applied to actual reactor. The control performance during commissioning test shows that the proposed controller provides fine control performance for various changes in reference values (PDM), even though there is large measurement noise from neutron detectors. The overshoot at low power level is acceptable in a sense of reactor operation.

  19. Demonstration personnel and material tracking system at ANL-W

    International Nuclear Information System (INIS)

    A Personnel and Material Tracking System (PMTS) was demonstrated in the Fuel Manufacturing Facility (FMF) at Argonne National Laboratories-West (ANL-W) in July, 1987. The PMTS is intended to aid in the transfer of inventory materials from area to area within a facility such as FMF. It is also intended to assure that only those personnel who are authorized to do so may conduct these transfer operations. The PMTS Personnel Movement (PM) subsystem uses portals installed between areas to alert the system to the movement of personnel between areas. The portals are composed to two sensors, one on either side of a proximity badge reader, to detect the presence of personnel entering the portal area. However, a restricted area can be assigned to any badge holder which will cause the system to issue an alert if the badge holder passes into his/her restricted area. The PM subsystem is intended to be transparent when in use. The PMTS Inventory Material Access (IMA) subsystem provides two functions: material control and material access. The material control is provided by the Wireless Alarm Transmission of Container Handling (WATCH) system which is a sensor rf transmitter system that detects item movements. Material access is provided by the Mobile Accountability Verification Inventory Station (MAVIS) system which is a self-powered smart barcode reader

  20. Characterization of Zero-Bias Microwave Diode Power Detectors at Cryogenic Temperature

    CERN Document Server

    Giordano, Vincent; Dubois, Benoît; Rubiola, Enrico

    2016-01-01

    We present the characterization of commercial tunnel diode low-level microwave power detectors at room and cryogenic temperatures. The sensitivity as well as the output voltage noise of the tunnel diodes are measured as functions of the applied microwave power, the signal frequency being 10 GHz. We highlight strong variations of the diode characteristics when the applied microwave power is higher than few microwatt. For a diode operating at ${4}$ K, the differential gain increases from ${1,000}$ V/W to about ${4,500}$ V/W when the power passes from ${-30}$ dBm to ${-20}$ dBm. The diode present a white noise floor equivalent to a NEP of ${0.8}$ pW/ ${\\sqrt{\\mathrm{Hz}}}$ and ${8}$ pW/${ \\sqrt{\\mathrm{Hz}}}$ at 4 K and 300 K respectively. Its flicker noise is equivalent to a relative amplitude noise power spectral density ${S_{\\alpha}(1~\\mathrm{Hz})=-120}$~dB/Hz at ${4}$ K. Flicker noise is 10 dB higher at room temperature.

  1. Technical Note: Zero Emissions Power Generation with CO2 Reduction by Fayalite

    Directory of Open Access Journals (Sweden)

    Evgeny Yantovski

    2005-09-01

    Full Text Available In this paper a new ‘fuel’, fayalite Fe2SiO4, is proposed tentatively and a new concept involving the convergence of a power plant and its fuel source is described. The CO2 from the power plant would be injected underground where it would be reduced to methane. The methane would then serve as the ‘derived fuel’ of the power plant having been produced by the reaction of fayalite with the CO2. One of the possible chemical reactions of CO2 with rock is indicated, along with properties of the mineral fayalite. Calculations of the Gibbs free energy and enthalpy show that the reaction of carbon dioxide with fayalite is exothermic and might be self-sustaining.

  2. Solar energy conversion through seaweed photosynthesis with combustion in a zero-emission power plant

    OpenAIRE

    Yantovski, Evgeny; McGovern, Jim

    2006-01-01

    A proposed ‘closed cycle’ power plant scheme, referred to as SOFT (Solar Oxygen Fuel Turbine), is described. The scheme involves the cultivation of macroalgae in a pond, combustion of their organic matter in a fluidised bed boiler that generates steam for a Rankine cycle steam power plant and the return of the combustion products to the pond to feed the algae. Oxygen, equivalent to that used for combustion, is re-released to the atmosphere by photosynthesis, while the carbon dioxide that is p...

  3. Validation of finite element code DELFIN by means of the zero power experiences at the nuclear power plant of Atucha I

    International Nuclear Information System (INIS)

    Code DELFIN, developed in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and currents among elements and a more realistic representation of the hexagonal lattice of the reactor. It can be used for fuel management calculation, Xenon oscillation and spatial kinetics. Using the HUEMUL code for cell calculation (which uses a generalized two dimensional collision probability theory and has the WIMS library incorporated in a data base), the zero power experiences performed in 1974 were calculated. (author). 8 refs., 9 figs., 3 tabs

  4. The ANL electric vehicle battery R&D program for DOE-EHP

    Science.gov (United States)

    1993-06-01

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides technical and programmatic support to DOE's Electric and Hybrid Propulsion Division (DOE-EHP). The goal of DOE-EHP is to advance promising electric-vehicle (EV) propulsion technologies to levels where industry will continue their commercial development and thereby significantly reduce air pollution and petroleum consumption due to the transportation sector of the economy. In support of this goal, ANL provides research, development, testing/evaluation, post-test analysis, modeling, and project management on advanced battery technologies for DOE-EHP. The battery-related activities undertaken during the period of 1 Jan. 1993 through 31 Mar. 1993 are summarized. The objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: Project Management; Sodium/Metal Chloride R&D and Microreference Electrodes for Lithium/Polymer Batteries.

  5. Research Developments on Power System Integration of Wind Power

    DEFF Research Database (Denmark)

    Chen, Zhe; Hansen, Jens Carsten; Wu, Qiuwei;

    2011-01-01

    variability and prediction, wind power plant ancillary services, grid connection and operation, Smart grids and demand side management under market functionality. The topics of the first group of PhD program starting 2011 under the wind energy Sino-Danish Centre for Education & Research (SDC) are also...

  6. Performance assessment of KORAT-3D on the ANL IBM-SP computer

    International Nuclear Information System (INIS)

    The TENAR code is currently being developed at the Russian Federal Nuclear Center (VNIIEF) as a coupled dynamics code for the simulation of transients in VVER and RBMK systems and other nuclear systems. The neutronic module in this code system is KORAT-3D. This module is also one of the most computationally intensive components of the code system. A parallel version of KORAT-3D has been implemented to achieve the goal of obtaining transient solutions in reasonable computational time, particularly for RBMK calculations that involve the application of >100,000 nodes. An evaluation of the KORAT-3D code performance was recently undertaken on the Argonne National Laboratory (ANL) IBM ScalablePower (SP) parallel computer located in the Mathematics and Computer Science Division of ANL. At the time of the study, the ANL IBM-SP computer had 80 processors. This study was conducted under the auspices of a technical staff exchange program sponsored by the International Nuclear Safety Center (INSC)

  7. Effects of Zero Moment of Truth on Consumer Buying Decision: An Exploratory Research in Turkey

    OpenAIRE

    ERTEMEL, Adnan Veysel; BAŞÇI, Ahmet

    2015-01-01

    With the advent of Internet that enables always connected consumers and readily available rich information about all types of products, consumer’s purchase decision process has been radically altered that accompanies more information seeking activity prior to going to the store shelf. First moment of truth (FMoT) and Zero Moment of Truth (ZMoT) are the concepts coined by practitioners studying important moments in the consumer purchase decision process. First moment of truth emphasizes the cr...

  8. Analysis of Rod Removal Transient Experiments in VVER Reactors at Zero Power

    International Nuclear Information System (INIS)

    Within the context of the Fissile Materials Disposition Program of the U.S. Department of Energy we analyzed rod removal transient experiments performed at the Kurchatov Institute in a full-scale mockup of WWER reactors. The transients were started (via water inlet) in slightly (few cents) supercritical configurations with all the control rods withdrawn. After a few minutes, control rods banks or individual control rods were f and t inserted and later withdrawn (returning to the initial state). Available experimental data include the relative time profiles of nine incore and excore detectors. Because of the mild nature of the transients (very low power and no more than 2 $ reactivities) we decided to use a quasistatic approach. The time-dependent flux is factorized into two terms: a function of phase space, given by the solution of the static equation with parametric excitation; and a function of time, given by the solution of the point kinetic equations with time-dependent kinetics para meters. Due to the nature of the experiment, cold conditions, control rods withdrawn and critical state with water level, the power distributions, measured and calculated, are quite unusual, with the inner part of the core heavily shielded. Measured power levels at the center of the reactor are almost 20 times smaller than similar regions at the periphery. Transport and diffusion calculations of the power distributions are in reasonable agreement, so the division code BOLD-VENTURE was used to calculate the kinetics parameters and the relative changes of the detector field of view. The numerical integration of the time-dependent part of the solution was made with the LSODE package using ENDFIB-V and VI delayed neutron data. Very good results were obtained for the nine lime profiles

  9. The calculation of the YALINA BOOSTER zero power sub critical assembly driven by external neutron sources: Brazillian contribution

    Science.gov (United States)

    Carluccio, Thiago; Rossi, Pedro Carlos Russo; Maiorino, José Rubens

    2011-08-01

    The YALINA-Booster is an experimental zero power Accelerator Driven Reactor (ADS), which consists of a sub-critical assemby driven by external neutron sources. It has a fast spectrum booster zone in the center, surrounded by a thermal one. The sub-critical core is driven by external neutron sources. Several experiments have been proposed in the framework of IAEA Coordinated Reserch Project (CRP) on ADS. This work shows results obtained by IPEN modelling and simulating experiments proposed at CRP, using the MCNP code. The comparison among our results, the experimental one and the results obtained by other participants is being done by CRP coordinators. This coolaborative work has an important role in the qualification and improvement of calculational methodologies.

  10. Thermal noise informatics: Totally secure communication via a wire; Zero-power communication; and Thermal noise driven computing

    CERN Document Server

    Kish, Laszlo B; gingl, Zoltan

    2007-01-01

    Very recently, it has been shown that Gaussian thermal noise and its artificial versions (Johnson-like noises) can be utilized as an information carrier with peculiar properties therefore it may be proper to call this topic Thermal Noise Informatics. Zero Power (Stealth) Communication, Thermal Noise Driven Computing, and Totally Secure Classical Communication are relevant examples. In this paper, while we will briefly describe the first and the second subjects, we shall focus on the third subject, the secure classical communication via wire. This way of secure telecommunication utilizes the properties of Johnson(-like) noise and those of a simple Kirchhoff's loop. The communicator is unconditionally secure at the conceptual (circuit theoretical) level and this property is (so far) unique in communication systems based on classical physics. The communicator is superior to quantum alternatives in all known aspects, except the need of using a wire.

  11. RELAP5-3D calculation of steam outlet header rupture of WWER-1000 NPP at hot zero power

    International Nuclear Information System (INIS)

    This presentation is devoted to one of the transients from the spectrum of steam line ruptures, which are analyzed for safety report purposes in Czech Republic. It is focused on the SGI steam outlet header rupture of WWER-1000 at hot zero power conditions analysis with advanced thermal-hydraulic code RELAP5-3D. The attention is addressed a reactor vessel and reactor core nodalization. The steam line rupture followed by steam release results in a strong drain oaf energy from primary circuit, what presents significant decreasing of primary coolant temperature and pressure. Then the feedback reactivity coefficients in connection with reduction of coolant temperature on the reactor inlet would cause introduction of positive reactivity and they could result in reactor restart (after its shutdown). Such transients are characterised by an unsymmetrical cool down of reactor and a strongly non-uniform distribution of power increase in the core. Safety analyses of such transients, where substantial changes oaf power distribution could occur, need apply thermal-hydraulic computational programs containing a 3D neutronic and thermal-hydraulic model of the reactor. The used computer codes, initial conditions for thermal-hydraulic calculations and basic results are presented. The DNBR value was monitored from the point of view of fuel integrity (Authors)

  12. CO{sub 2} and H{sub 2}O diluted oxy-fuel combustion for zero-emission power

    Energy Technology Data Exchange (ETDEWEB)

    Richards, G.A.; Casleton, K.H.; Chorpening, B.T. [US DOE, Morgantown, WV (United States). National Energy Technology Lab.

    2005-03-01

    Concerns about climate change have encouraged significant interest in concepts for zero-emission power generation systems. These systems are intended to produce power without releasing CO{sub 2} into the atmosphere. One approach is to replace the nitrogen diluent that accompanies conventional combustion in air with either CO{sub 2} or H{sub 2}O. In this concept, CO{sub 2} or H{sub 2}O is added to oxygen to control combustion temperatures in oxygen-fuel reactions. In the absence of nitrogen, the primary combustion products for any hydrocarbon under lean conditions are then simply CO{sub 2} and H{sub 2}O. Thus, merely cooling the exhaust stream condenses the water and produces an exhaust of pure CO{sub 2}, ready for sequestration. The dilute oxy-fuel combustion strategy can be incorporated in power cycles that are similar to Brayton or Rankine configurations, using CO{sub 2} or H{sub 2}O as the primary diluent respectively. In this paper, the expected combustion performance of CO{sub 2} and H{sub 2}O diluted systems are compared. Experimental results from a high-pressure oxy-fuel combustor are also presented.

  13. Gaussian and non-Gaussian processes of zero power variation, and related stochastic calculus.

    OpenAIRE

    Russo, Francesco; Viens, Frederi

    2014-01-01

    We consider a class of stochastic processes $X$ defined by $X\\left( t\\right) =\\int_{0}^{T}G\\left( t,s\\right) dM\\left( s\\right) $ for $t\\in\\lbrack0,T]$, where $M$ is a square-integrable continuous martingale and $G$ is a deterministic kernel. Let $m$ be an odd integer. Under the assumption that the quadratic variation $\\left[ M\\right] $ of $M$ is differentiable with $\\mathbf{E}\\left[ \\left\\vert d\\left[ M\\right] (t)/dt\\right\\vert ^{m}\\right] $ finite, it is shown that the $m$th power variation ...

  14. THE SOLAR ENERGY CONVERSION THROUGH SEAWEED PHOTOSYNTHESIS AND ZERO EMISSIONS POWER GENERATION

    OpenAIRE

    E.I. Yantovski

    2008-01-01

    Present paper is aimed at describing a “closed cycle” power plant schematics(SOFT, Solar Oxygen Fuel Turbine) with macroalgae (seaweed) cultivation in a pond, combustion of its organic matter in a fluidized bed boiler of Rankine cycle and return the combustion products to the pond to feed algae. Used for combustion oxygen is released to atmosphere in photosynthesis. It is further elaboration of the paper in ECOS2005 in Trondheim. As a renewable fuel the seaweed Ulva lactuca is selected. Its g...

  15. Advanced exergoenvironmental analysis of a near-zero emission power plant with chemical looping combustion.

    Science.gov (United States)

    Petrakopoulou, Fontina; Tsatsaronis, George; Morosuk, Tatiana

    2012-03-01

    Carbon capture and storage (CCS) from power plants can be used to mitigate CO(2) emissions from the combustion of fossil fuels. However, CCS technologies are energy intensive, decreasing the operating efficiency of a plant and increasing its costs. Recently developed advanced exergy-based analyses can uncover the potential for improvement of complex energy conversion systems, as well as qualify and quantify plant component interactions. In this paper, an advanced exergoenvironmental analysis is used for the first time as means to evaluate an oxy-fuel power plant with CO(2) capture. The environmental impacts of each component are split into avoidable/unavoidable and endogenous/exogenous parts. In an effort to minimize the environmental impact of the plant operation, we focus on the avoidable part of the impact (which is also split into endogenous and exogenous parts) and we seek ways to decrease it. The results of the advanced exergoenvironmental analysis show that the majority of the environmental impact related to the exergy destruction of individual components is unavoidable and endogenous. Thus, the improvement potential is rather limited, and the interactions of the components are of lower importance. The environmental impact of construction of the components is found to be significantly lower than that associated with their operation; therefore, our suggestions for improvement focus on measures concerning the reduction of exergy destruction and pollutant formation. PMID:22239071

  16. Watts Bar Unit 1 cycle 1 zero power physics tests analysis with VERA-CS

    International Nuclear Information System (INIS)

    The Consortium for Advanced Simulation of Light Water Reactors (CASL) is developing a collection of methods and software products known as VERA, the Virtual Environment for Reactor Applications, including a core simulation capability called VERA-CS. A key milestone for this endeavor is to validate VERA against measurements from operating nuclear power reactors. The first step in validation against plant data is to determine the ability of VERA to accurately simulate the initial startup physics tests for Watts Bar Nuclear Power Station, Unit 1 (WBN1) cycle 1. VERA-CS calculations were performed with the Insilico code developed at Oak Ridge National Laboratory using cross section processing from the SCALE system and the transport capabilities within the Denovo transport code using the SPN method. The calculations were performed with ENDF/B-VII.0 cross sections in 252 groups (collapsed to 23 groups for the 3D transport solution). The key results of the comparison of calculations with measurements include initial criticality, control rod worth critical configurations, control rod worth, differential boron worth, and isothermal temperature reactivity coefficient (ITC). The VERA results for these parameters show good agreement with measurements, with the exception of the ITC, which requires additional investigation. Results are also compared to those obtained with Monte Carlo methods and a current industry core simulator. (author)

  17. Acidification: cost-benefit analysis zeros in on power producers, refiners

    International Nuclear Information System (INIS)

    Measures reducing sulphur dioxide emissions by Europe's power producers and oil refineries are viewed by the European Commission as among the most cost-effective in combating acidification. The main elements of the Commission's strategy include the establishment of national emission ceilings; EU ratification of the 1994 Sulphur Protocol to further reduce sulphur emissions under the UN ECE Convention on Long-Range Transboundary Air Pollution; a revision of directive 93/12/EEC limiting the sulphur content of certain liquid fuels, this time including heavy fuel oils; revision of the 1988 Large Combustion Plants directive; and the designation of the Baltic Sea and the North Sea as SO2 emission control areas. (UK)

  18. The Zero Emission Fossil Fuel Power Plant - from vision to reality.

    Energy Technology Data Exchange (ETDEWEB)

    Stroemberg, L.; Sauthoff, M.

    2007-07-01

    Sufficient supply of energy without fossil fuels is not possible the next fifty years. Thus, we must find a solution to use coal, without endangering the environment. Carbon Capture and Storage, CCS, might be the answer. At a cost of about 20 Euro/ton CO{sub 2}, there exist technologies, which can be ready for commercial application in 2020. After that, even more cost effective technologies will be developed. To reduce emissions by more than half until 2050, cannot be reached without CCS. However, CCS is very powerful, but not the only tool. All ways to reduce emissions, including renewables and nuclear must be used. To put emphasis behind the words, Vattenfall has started an R and D program to develop technology for CCS in a ten year program. As part of that, Vattenfall is building a Pilot Plant including all process steps from coal input to liquid CO{sub 2}. It will be ready in 2008. In parallel, preparations for a demonstration plant are ongoing. It will be a coal fired full size plant with storage on shore. That will be ready for operation in 2015. (auth)

  19. Experimental Setup for the Measurement of the Thermoelectric Power in Zero and Applied Magnetic Field

    CERN Document Server

    Mun, Eundeok; Torikachvili, Milton S; Canfield, Paul C

    2010-01-01

    An experimental setup was developed for the measurement of the thermoelectric power (TEP, Seebeck coefficient) in the temperature range from 2 to 350 K and magnetic fields up to 140 kOe. The system was built to fit in a commercial cryostat and is versatile, accurate and automated; using two heaters and two thermometers increases the accuracy of the TEP measurement. High density data of temperature sweeps from 2 to 350 K can be acquired in under 16 hours and high density data of isothermal field sweeps from 0 to 140 kOe can be obtained in under 2 hours. Calibrations for the system have been performed on a platinum wire and Bi$_{2}$Sr$_{2}$CaCu$_{2}$O$_{8+\\delta}$ high $T_{c}$ superconductors. The measured TEP of phosphor-bronze (voltage lead wire) turns to be very small, where the absolute TEP value of phosphor-bronze wire is much less than 0.5 $\\mu$V/K below 80 K. For copper and platinum wires measured against to the phosphor-bronze wire, the agreement between measured results and the literature data is good....

  20. Analysis and performance assessment of a multigenerational system powered by Organic Rankine Cycle for a net zero energy house

    International Nuclear Information System (INIS)

    This paper develops a new Organic Rankine Cycle (ORC) based multigenerational system to meet the demands of a net zero energy building and assesses such a system for an application to a net zero energy house in Lebanon. Solar energy is the prime source for the integrated system to achieve multigeneration to supply electricity, fresh and hot water, seasonal heating and cooling. The study starts by optimizing the power system with and without grid connection. Then, a comprehensive thermodynamic analysis through energy and exergy, and a parametric study to assess the sensitivity and improvements of the overall system are conducted. Furthermore, exergoeconomic analysis and a follow-up optimization study for optimizing the total system cost to the overall system efficiency using genetic algorithm to obtain the optimal design or a set of optimal designs (Pareto Front), are carried out. The present results show that the optimum solar energy system for a total connected load to the house of 90 kWh/day using a combination of ORC, batteries, convertor has a total net present cost of US $52,505.00 (based on the prices in 2013) with a renewable energy fraction of 1. Moreover, the optimization for the same connected load with ORC, batteries and converter configuration with grid connection results in a total net present cost of $50,868.00 (2013) with a renewable energy fraction of 0.992 with 169 kg/yr of CO2 emissions. In addition, exergoeconomic analysis of the overall system yields a cost of $117,700.00 (2013), and the multi-objective optimization provides the overall exergetic efficiency by 14% at a total system cost increase of $10,500.00 (2013). - Highlights: • To develop a new Organic Rankine Cycle (ORC) based multigenerational system to meet the demands of a net zero energy building. • To perform a comprehensive thermodynamic analysis through energy and exergy approaches. • To apply an exergoeconomic model for exergy-based cost accounting. • To undertake

  1. Development of Biomimetic Membranes for Near Zero PC Power Plant Emissions

    Energy Technology Data Exchange (ETDEWEB)

    Michael Trachtenberg; Robert Cowan; David Smith; Ira Sider

    2009-07-31

    The first objective of this project was to develop, evaluate and compare two different CO2 separation (capture) systems. The second was to carry the preferred solution to pre-pilot development and testing. To achieve these objectives we undertook several infrastructure enabling elements: (1) development of a preferred catalyst coupled with its immobilization onto a microporous polymer membrane, (2) design and development of a microporous membrane-based, contained liquid membrane permeator and a membrane-based absorber/desorber apparatus, (3) development of a resin-wafer electrodialytic absorber/desorber apparatus, (4) development and demonstration of a pre-treatment process to condition the feed gas stream, (5) and development of computer modeling of the components and of the integrated system. The first technology was an enzyme catalyzed, membrane supported, contained liquid membrane apparatus whose gas capture was pressure/vacuum and temperature driven. A first embodiment was as a permeator, i.e. a combined absorber/desorber in a single housing. The second embodiment was as discrete absorber and desorber units. The second technology was an enzyme catalyzed, ion exchange resin wafer electrodialytically-based separation. For each of these technologies the objective was to design, manufacture, test and demonstrate the apparatus, first in the laboratory and then at pre-pilot scale, and to run it for sufficient time at the pre-pilot scale to demonstrate stability even in the face of upset. Tests would include several ranks of coal, which had been appropriately pre-treated to remove NOx, SOx and particles, to a pre-determined acceptance level, as a basis for demonstrating efficient CO{sub 2} capture. The pre-pilot tests would be run at the Energy and Environmental Research Center (EERC) in North Dakota. A larger scale test (400m{sup 2} test unit) would later be run also at EERC. An economic goal was to compare the cost of CO{sub 2} capture by each of these methods with

  2. Zero effluent; Efluente zero

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Silvio Rogerio; Santos, Angelo Francisco dos [Liquigas Distribuidora S.A., Sao Paulo, SP (Brazil)

    2008-07-01

    A scenery of water shortage and the search for profitability improvement obligate the companies to exercise their creativity and to adopt alternative methods to the conventional ones to preserve the environmental resources. The 'Effluent Zero' project comes from a paradigms changing that the environmental preservation is a necessary cost. It brings a new analysis approach of this problem with the purpose to adapt the investments and operational costs with the effluents treatment to the demands of the productive processes. In Liquigas, the project brought significant results; made a potential reduction of nearly 90% in the investments of the effluents treatment systems. That means nearly 13% in reduction in the total investments in modernization and upgrade of the existents companies installations and of 1,6% in the total operational costs of the Company. Further more, it has contributed for a reduction of until 43% of the water consumption in the bottling process of the Liquefied Petroleum Gas (LPG). This way, the project resulted in effective actions of environmental protection with relevant economic benefits. (author)

  3. Status of ANL out-of-pile investigations of severe accident phenomena for liquid metal reactors

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, B.W.; Marchaterre, J.F.; Anderson, R.P.; Armstrong, D.R.; Baker, L.; Cho, D.H.; Gabor, J.D.; Pedersen, D.R.; Sienicki, J.J.; Stein, R.P.

    1986-01-01

    Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on quantifying reactivity feedbacks, and in particular enhancing negative feedback, so that advanced LMR designs will provide inherently safe operation. The status of recent HCDA-related laboratory research performed at ANL, up to the time that such activities were no longer needed to support CRBR licensing, is described. Included are descriptions of programs addressing sodium channel voiding, fuel sweepout, fuel dispersal and plugging, boiled-up pool, UO/sub 2//sodium FCI, and debris coolability. Descriptions of recent investigations involving the metal fuel/sodium system are also included.

  4. Status of ANL out-of-pile investigations of severe accident phenomena for liquid metal reactors

    International Nuclear Information System (INIS)

    Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on quantifying reactivity feedbacks, and in particular enhancing negative feedback, so that advanced LMR designs will provide inherently safe operation. The status of recent HCDA-related laboratory research performed at ANL, up to the time that such activities were no longer needed to support CRBR licensing, is described. Included are descriptions of programs addressing sodium channel voiding, fuel sweepout, fuel dispersal and plugging, boiled-up pool, UO2/sodium FCI, and debris coolability. Descriptions of recent investigations involving the metal fuel/sodium system are also included

  5. TRIGA research reactors with higher power density

    International Nuclear Information System (INIS)

    The recent trend in new or upgraded research reactors is to higher power densities (hence higher neutron flux levels) but not necessarily to higher power levels. The TRIGA LEU fuel with burnable poison is available in small diameter fuel rods capable of high power per rod (∼48 kW/rod) with acceptable peak fuel temperatures. The performance of a 10-MW research reactor with a compact core of hexagonal TRIGA fuel clusters has been calculated in detail. With its light water coolant, beryllium and D2O reflector regions, this reactor can provide in-core experiments with thermal fluxes in excess of 3 x 1014 n/cm2·s and fast fluxes (> 0.1 MeV) of 2 x 1014 n/cm2·s. The core centerline thermal neutron flux in the D2O reflector is about 2 x 1014 n/cm2·s and the average core power density is about 230 kW/liter. Using other TRIGA fuel developed for 25-MW test reactors but arranged in hexagonal arrays, power densities in excess of 300 kW/liter are readily available. A core with TRIGA fuel operating at 15-MW and generating such a power density is capable of producing thermal neutron fluxes in a D2O reflector of 3 x 1014 n/cm2·s. A beryllium-filled central region of the core can further enhance the core leakage and hence the neutron flux in the reflector. (author)

  6. Higher power density TRIGA research reactors

    International Nuclear Information System (INIS)

    The uranium zirconium hydride (U-ZrH) fuel is the fundamental feature of the TRIGA family of reactors that accounts for its widely recognized safety, good performance, economy of operation, and its acceptance worldwide. Of the 65 TRIGA reactors or TRIGA fueled reactors, several are located in hospitals or hospital complexes and in buildings that house university classrooms. These examples are a tribute to the high degree of safety of the operating TRIGA reactor. In the early days, the majority of the TRIGA reactors had power levels in the range from 10 to 250 kW, many with pulsing capability. An additional number had power levels up to 1 MW. By the late 1970's, seven TRIGA reactors with power levels up to 2 MW had been installed. A reduction in the rate of worldwide construction of new research reactors set in during the mid 1970's but construction of occasional research reactors has continued until the present. Performance of higher power TRIGA reactors are presented as well as the operation of higher power density reactor cores. The extremely safe TRIGA fuel, including the more recent TRIGA LEU fuel, offers a wide range of possible reactor configurations. A long core life is assured through the use of a burnable poison in the TRIGA LEU fuel. In those instances where large neutron fluxes are desired but relatively low power levels are also desired, the 19-rod hexagonal array of small diameter fuel rods offers exciting possibilities. The small diameter fuel rods have provided extremely long and trouble-free operation in the Romanian 14 MW TRIGA reactor

  7. Analysis of higher power research reactors' parameters

    International Nuclear Information System (INIS)

    The objective of this monograph was to analyze and compare parameters of different types of research reactors having higher power. This analysis could be used for decision making and choice of a reactor which could possibly replace the existing ageing RA reactor in Vinca. Present experimental and irradiation needs are taken into account together with the existing reactors operated in our country, RB and TRIGA reactor

  8. Reanalysis of the Gas-cooled fast reactor experiments at the zero power facility Proteus - Spectral indices

    Science.gov (United States)

    Perret, G.; Pattupara, R. M.; Girardin, G.; Chawla, R.

    2013-03-01

    PROTEUS is a zero power reactor at the Paul Scherrer Institute which has been employed during the 1970's to study experimentally the physics of the gas-cooled fast reactor. Reaction rate distributions, flux spectrum and reactivity effects have been measured in several configurations featuring PuO2/UO2 fuel, absorbers, large iron shields, and thorium oxide and thorium metal fuel either distributed quasihomogeneously in the reference PuO2/UO2 lattice or introduced in the form of radial and axial blanket zones. This papers focus on the spectral indices - including fission and capture in 232Th and 237Np - measured in the reference PuO2/UO2 lattices and their predictions with an MCNPX model specially developed for the PROTEUS-GCFR core. Predictions were obtained with JEFF-3.1 and -3.11, ENDF/B-VII.0 and VII.1, and JENDL-3.3 and -4.0. A general good agreement was demonstrated. The ratio of 232Th fission to 239Pu fission, however, was under-predicted by 8.7±2.1% and 6.5±2.1% using ENDF/B-VII.0 and VII.1, respectively. Finally, the capture rates in 237Np tended to be underpredicted by the JEFF and JENDL libraries, although the new cross section in JEFF-3.1.1 slightly improved the 237Np capture to 239Pu fission results (3.4±2.4%).

  9. Reanalysis of the gas-cooled fast reactor experiments at the zero power facility proteus - Spectral indices

    International Nuclear Information System (INIS)

    The gas-cooled fast reactor (GCFR) concept was investigated experimentally in the PROTEUS zero power facility at the Paul Scherrer Inst. during the 1970's. The experimental program was aimed at neutronics studies specific to the GCFR and at the validation of nuclear data in fast spectra. A significant part of the program used thorium oxide and thorium metal fuel either distributed quasi-homogeneously in the reference PuO2/UO2 lattice or introduced in the form of radial and axial blanket zones. Experimental results obtained at the time are still of high relevance in view of the current consideration of the Gas-cooled Fast Reactor (GFR) as a Generation-IV nuclear system, as also of the renewed interest in the thorium cycle. In this context, some of the experiments have been modeled with modern Monte Carlo codes to better account for the complex PROTEUS whole-reactor geometry and to allow validating recent continuous neutron cross-section libraries. As a first step, the MCNPX model was used to test the JEFF-3.1, JEFF-3.1.1, ENDF/B-VII.0 and JENDL-3.3 libraries against spectral indices, notably involving fission and capture of 232Th and 237Np, measured in GFR-like lattices. (authors)

  10. Benchmark Evaluation of Start-Up and Zero-Power Measurements at the High-Temperature Engineering Test Reactor

    International Nuclear Information System (INIS)

    Benchmark models were developed to evaluate six cold-critical and two warm-critical, zero-power measurements of the HTTR. Additional measurements of a fully-loaded subcritical configuration, core excess reactivity, shutdown margins, six isothermal temperature coefficients, and axial reaction-rate distributions were also evaluated as acceptable benchmark experiments. Insufficient information is publicly available to develop finely-detailed models of the HTTR as much of the design information is still proprietary. However, the uncertainties in the benchmark models are judged to be of sufficient magnitude to encompass any biases and bias uncertainties incurred through the simplification process used to develop the benchmark models. Dominant uncertainties in the experimental keff for all core configurations come from uncertainties in the impurity content of the various graphite blocks that comprise the HTTR. Monte Carlo calculations of keff are between approximately 0.9 % and 2.7 % greater than the benchmark values. Reevaluation of the HTTR models as additional information becomes available could improve the quality of this benchmark and possibly reduce the computational biases. High-quality characterization of graphite impurities would significantly improve the quality of the HTTR benchmark assessment. Simulation of the other reactor physics measurements are in good agreement with the benchmark experiment values. The complete benchmark evaluation details are available in the 2014 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments

  11. Large power supply facilities for fusion research

    International Nuclear Information System (INIS)

    The authors had opportunities to manufacture and to operate two power supply facilities, that is, 125MVA computer controlled AC generator with a fly wheel for JIPP-T-2 stellerator in Institute of Plasma Physics, Nagoya University and 3MW trial superconductive homopolar DC generator to the Japan Society for Promotion of Machine Industry. The 125MVA fly-wheel generator can feed both 60MW (6kV x 10kA) DC power for toroidal coils and 20MW (0.5kV x 40kA) DC power for helical coils. The characteristic features are possibility of Bung-Bung control based on Pontrjagin's maximum principle, constant current control or constant voltage control for load coils, and cpu control for routine operation. The 3MW (150V-20000A) homopolar generator is the largest in the world as superconductive one, however, this capacity is not enough for nuclear fusion research. The problems of power supply facilities for large Tokamak devices are discussed

  12. Reanalysis of the Gas-cooled fast reactor experiments at the zero power facility Proteus – Spectral indices

    Directory of Open Access Journals (Sweden)

    Girardin G.

    2013-03-01

    Full Text Available PROTEUS is a zero power reactor at the Paul Scherrer Institute which has been employed during the 1970’s to study experimentally the physics of the gas-cooled fast reactor. Reaction rate distributions, flux spectrum and reactivity effects have been measured in several configurations featuring PuO2/UO2 fuel, absorbers, large iron shields, and thorium oxide and thorium metal fuel either distributed quasihomogeneously in the reference PuO2/UO2 lattice or introduced in the form of radial and axial blanket zones. This papers focus on the spectral indices – including fission and capture in 232Th and 237Np - measured in the reference PuO2/UO2 lattices and their predictions with an MCNPX model specially developed for the PROTEUS-GCFR core. Predictions were obtained with JEFF-3.1 and -3.11, ENDF/B-VII.0 and VII.1, and JENDL-3.3 and -4.0. A general good agreement was demonstrated. The ratio of 232Th fission to 239Pu fission, however, was under-predicted by 8.7±2.1% and 6.5±2.1% using ENDF/B-VII.0 and VII.1, respectively. Finally, the capture rates in 237Np tended to be underpredicted by the JEFF and JENDL libraries, although the new cross section in JEFF-3.1.1 slightly improved the 237Np capture to 239Pu fission results (3.4±2.4%.

  13. Reanalysis of the gas-cooled fast reactor experiments at the zero power facility Proteus - Spectral indices

    International Nuclear Information System (INIS)

    PROTEUS is a zero power reactor at the Paul Scherrer Institute which has been employed during the 1970's to study experimentally the physics of the gas-cooled fast reactor. Reaction rate distributions, flux spectrum and reactivity effects have been measured in several configurations featuring PuO2/UO2 fuel, absorbers, large iron shields, and thorium oxide and thorium metal fuel either distributed quasi-homogeneously in the reference PuO2/UO2 lattice or introduced in the form of radial and axial blanket zones. This papers focuses on the spectral indices - including fission and capture in 232Th and 237Np - measured in the reference PuO2/UO2 lattices and their predictions with an MCNPX model specially developed for the PROTEUS-GCFR core. Predictions were obtained with JEFF-3.1 and -3.11, ENDF/B-VII.0 and VII.1, and JENDL-3.3 and -4.0. A general good agreement was demonstrated. The ratio of 232Th fission to 239Pu fission, however, was under-predicted by (8.7±2.1)% and (6.5±2.1)% using ENDF/B-VII.0 and VII.1, respectively. Finally, the capture rates in 237Np tended to be under-predicted by the JEFF and JENDL libraries, although the new cross section in JEFF-3.1.1 slightly improved the 237Np capture to 239Pu fission results (3.4±2.4)%. (authors)

  14. The Zero Program

    Science.gov (United States)

    Roland, Erling; Midthassel, Unni Vere

    2012-01-01

    Zero is a schoolwide antibullying program developed by the Centre for Behavioural Research at the University of Stavanger, Norway. It is based on three main principles: a zero vision of bullying, collective commitment among all employees at the school using the program, and continuing work. Based on these principles, the program aims to reduce…

  15. Degradation modeling of the ANL ceramic waste form

    International Nuclear Information System (INIS)

    A ceramic waste form composed of glass-bonded sodalite is being developed at Argonne National Laboratory (ANL) for immobilization and disposition of the molten salt waste stream from the electrometallurgical treatment process for metallic DOE spent nuclear fuel. As part of the spent fuel treatment program at ANL, a model is being developed to predict the long-term release of radionuclides under repository conditions. Dissolution tests using dilute, pH-buffered solutions have been conducted at 40, 70, and 90 C to determine the temperature and pH dependence of the dissolution rate. Parameter values measured in these tests have been incorporated into the model, and preliminary repository performance assessment modeling has been completed. Results indicate that the ceramic waste form should be acceptable in a repository environment

  16. Delayed neutron measurements of induced fission rates in burnt LWR fuel samples at the Proteus zero-power reactor facility - 125

    International Nuclear Information System (INIS)

    The LIFE'at'PROTEUS program at the Paul Scherrer Institut is being undertaken to characterize the interfaces between burnt and fresh fuel assemblies in modern LWRs. Techniques are being developed to measure fission rates in burnt fuel, following re-irradiation in the zero-power PROTEUS research reactor. In the presented approach, the fission rates are estimated by measuring delayed neutrons emitted by re-irradiated fuel. To demonstrate the feasibility of this technique, fresh and burnt fuel samples (with burnup varying from 36 to 64 GWd/MTU) were irradiated in the PROTEUS reactor, and their neutron outputs were recorded shortly after irradiation. Relative fission rates between different core lattice positions were derived for a fresh sample as well as for the three burnt samples. The measured fission rate ratios have 1-σ uncertainties between 2% and 3.5%, with the larger uncertainties corresponding to the more highly burnt fuel. Results obtained by Monte Carlo simulations agree with the experimentally determined values within these limits. With further development of the technique, the experimental uncertainties can be further reduced. Continuing effort is being directed towards accurate comparison of fission rates between fuel samples of different burn-up. (authors)

  17. Method of adiabatic modes in research of smoothly irregular integrated optical waveguides: zero approximation

    International Nuclear Information System (INIS)

    We consider the application of the method of adiabatic waveguide modes for calculating the propagation of electromagnetic radiation in three-dimensional (3D) irregular integrated optical waveguides. The method of adiabatic modes takes into account a three-dimensional distribution of quasi-waveguide modes and explicit ('inclined') tangential boundary conditions. The possibilities of the method are demonstrated on the example of numerical research of two major elements of integrated optics: a waveguide of 'horn' type and a thin-film generalised waveguide Luneburg lens by the methods of adiabatic modes and comparative waveguides. (integral optical waveguides)

  18. Ground Zero.

    Science.gov (United States)

    Lozada, Marlene

    1998-01-01

    Many public school districts have adopted a policy of zero tolerance toward drug use, weapon possession, and sexual harassment on school grounds. Although a study by the National Center for Education Statistics reported no evidence that zero tolerance policies have lowered school crime rates, prominent education groups favor them. (JOW)

  19. 78 FR 29159 - Electric Power Research Institute; Seismic Evaluation Guidance

    Science.gov (United States)

    2013-05-17

    ... COMMISSION Electric Power Research Institute; Seismic Evaluation Guidance AGENCY: Nuclear Regulatory... issuing an endorsement letter of Electric Power Research Institute (EPRI) Report, ``Seismic Evaluation... Committee (SSHAC) guidelines (these guidelines are discussed in NRC's NUREG 2117, ``Practical...

  20. Nuclear power plant Severe Accident Research Plan

    International Nuclear Information System (INIS)

    The Severe Accident Research Plan (SARP) will provide technical information necessary to support regulatory decisions in the severe accident area for existing or planned nuclear power plants, and covers research for the time period of January 1982 through January 1986. SARP will develop generic bases to determine how safe the plants are and where and how their level of safety ought to be improved. The analysis to address these issues will be performed using improved probabilistic risk assessment methodology, as benchmarked to more exact data and analysis. There are thirteen program elements in the plan and the work is phased in two parts, with the first phase being completed in early 1984, at which time an assessment will be made whether or not any major changes will be recommended to the Commission for operating plants to handle severe accidents. Additionally at this time, all of the thirteen program elements in Chapter 5 will be reviewed and assessed in terms of how much additional work is necessary and where major impacts in probabilistic risk assessment might be achieved. Confirmatory research will be carried out in phase II to provide additional assurance on the appropriateness of phase I decisions. Most of this work will be concluded by early 1986

  1. Low-frequency electromagnetic measurements as a zero-time discriminant of nuclear and chemical explosions - OSI research final report

    International Nuclear Information System (INIS)

    This is the final report on a series of investigations of low frequency (1-40 Hz) electromagnetic signals produced by above ground and underground chemical explosions and their use for confidence building under the Comprehensive Test-Ban Treaty. I conclude that low frequency electromagnetic measurements can be a very powerful tool for zero-time discrimination of chemical and nuclear explosions for yields of 1 Kt or greater, provided that sensors can be placed within 1-2 km of the suspected detonation point in a tamper-proof, low noise environment. The report includes descriptions and analyses of low frequency electromagnetic measurements associated with chemical explosions carried out in a variety of settings (shallow borehole, open pit mining, underground mining). I examine cavity pressure data from the Non-Proliferation Experiment (underground chemical explosion) and present the hypothesis that electromagnetic signals produced by underground chemical explosions could be produced during rock fracturing. I also review low frequency electromagnetic data from underground nuclear explosions acquired by Lawrence Livermore National Laboratory during the late 1980s. (author)

  2. The ANL electric vehicle battery R/D program for DOE-EHP

    Science.gov (United States)

    1993-03-01

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides technical and programmatic support to DOE's Electric and Hybrid PropuLsion Division (DOE-EHP). The goal of DOE-EHP is to advance promising electric-vehicle (EV) propulsion technologies to levels where industry will continue their commercial development and thereby significantly reduce air pollution and petroleum consumption. In support of this goal, ANL provides research, development, testing/evaluation, post-test analysis, modeling, and technical management of industrial R&D contracts on advanced battery technologies for DOE-EHP. This report summarizes the battery-related activities undertaken during the period of 1 Oct. 1992 - 31 Dec. 1992. In this report, the objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: 1.0 Project Management and Coordination; 2.0 Sodium/Metal Chloride R&D 3.0 Microreference Electrodes for Lithium/Polymer Batteries; and 4.0 USABC Support. The Project Management and Coordination Task Area encompasses planning, organization, coordination, integration, and overall management of battery R&D projects for DOE-EHP, as well as work performed in behalf of DOE-directed inter-laboratory tasks. Section 3 of this report recounts the work performed during this reporting period on each task within these task areas.

  3. The ANL Electrochemical Program for DOE on electric vehicle R/D

    Science.gov (United States)

    1992-11-01

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides technical and programmatic support to DOE's Electric and Hybrid Propulsion Division (DOE-EHP). The goal of DOE-EHP is to advance promising electric-vehicle (EV) propulsion technologies to levels where industry will continue their commercial development and thereby significantly reduce petroleum consumption in the transportation sector of the economy. In support of this goal, ANL provides research, development, testing/evaluation, post-test analysis, modeling, database management, and technical management of industrial R&D contracts on advanced battery technologies for DOE-EHP. This report summarizes the battery-related activities undertaken during the period of July 1, 1992 through September 30, 1992. In this report, the objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: Project Management and Coordination; Lithium/Sulfide Batteries; Advanced Sodium/Beta Batteries; Advanced Ambient-Temperature Batteries; and EV Battery Performance and Life Evaluation.

  4. The research of period measuring instruments on zero power assembly based on DSP

    International Nuclear Information System (INIS)

    In order to improving measure precision and anti-interference capacity, and respond to the digital trend, a new technique to measure reactor period is promoted, which is based on the DSP technique, calculate period with least-squares-fitting method. The systematic design is promoted, in which TMS320F2812 chip is chosen as the Central Processing/Controlling unit and software design is based on DSP/BIOS embedded operating system. Testing of both a simulation of the lab environment and an experiment shows that, as expected, the new TMS320F2812 based reactor period inspection equipment has excellent anti-interference capacity, high precision and fast response time, all of which prove that it has good prospective. (authors)

  5. Research on Low Power Marine Current Power Generation System

    Directory of Open Access Journals (Sweden)

    Dongkai Peng

    2013-09-01

    Full Text Available This study proposes a simple topological structure and power control method for a small scale stand alone marine current system, in which a diode rectifier, DC/DC boost converter for the maximum power control, battery as a storage element and a single phase inverter to link with load. The study establishes the steady-state mathematical model of marine current power generation system and derives the formula between the maximum power point and dc battery voltage. Then use the measurements of DC voltage and DC current to obtain Maximum Power Point Tracking (MPPT by controlling the duty cycle of the boost converter switch in order to simplify the system structure and the control strategies. In this case, the hill climbing searching algorithm is employed to get maximum power point and the double closed loops control strategy is used to improve the dynamic and static performance of single phase inverter. The simulation model is developed in MATLAB/Simulink. And the control method is executed in dSPACE1104 real-time platform. The simulation and experimental results demonstrate the feasibility and validity of the proposed control strategies.

  6. Større anlæg til overfladenedsivning af separat regnvand

    DEFF Research Database (Denmark)

    Vollertsen, Jes; Hvitved-Jacobsen, Thorkild; Nielsen, Asbjørn Haaning

    2012-01-01

    Nedsivning af regnvand kan foregå i underjordiske anlæg eller i anlæg til overfladenedsivning. Sidstnævnte kan være udformet decentralt med nedsivning på fx græsplæner, i grøfter, vejtrug, eller i beplantede bede. Alternativt kan overfladenedsivning ske i centrale anlæg, der modtager vand fra et ...

  7. Experimental Research on Microscopic Indicators of Temperature's Returning-to-Zero in Deformation of Calcite and Discussions of Correlation Problem

    Institute of Scientific and Technical Information of China (English)

    Yao Daquan; Zhai Hongtao

    2005-01-01

    In order to determine the degree of returning-to-zero of temperatures of deformed calcite, a series of rock-breaking experiments were designed to test calcite-rich limestone samples under fixed confining pressures and different temperatures. The consolidated deformed samples in their initial state were observed under a microscope and the microscopic indicators in different zero-returning states were put forward, thus providing a microscopic foundation for evaluation of reliability of dating values of deformation in calcite. At last, the correction of dating values of deformation for samples whose temperature has not yet returned to zero is discussed.

  8. Practical Uses of Statistical Power in Business Research Studies.

    Science.gov (United States)

    Markowski, Edward P.; Markowski, Carol A.

    1999-01-01

    Proposes the use of statistical power subsequent to the results of hypothesis testing in business research. Describes how posttest use of power might be integrated into business statistics courses. (SK)

  9. Recommended documentation for computer users at ANL. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Heiberger, A.A.

    1992-04-01

    Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

  10. Effect of age on inter and intra-subject variability in acceptable noise level (ANL in listeners with normal hearing

    Directory of Open Access Journals (Sweden)

    Bankole K. Fasanya

    2013-02-01

    Full Text Available Several industrial engineering and psychological studies have shown that noise affects the important aspects of communication for both adults and children. For speech understanding by hearing aids users and language development in children, an accurate hearing is very important. A metric has been developed for measuring an individual's acceptance of noise while listening to speech in quiet. This metric is known as Acceptable Noise Levels (ANLs. Studies have shown large inter-subject variability in acceptance of background noise. An argument has been made that an acceptance of background noise is a “means” that will help to solve the puzzle and monumental problem of hearing aid rejection. Meanwhile, within subject age dependency has not been investigated. This study is conducted to determine if ANL inter and intra-subject variability under music signal depends on age. Twenty subjects participated in the study (average age = 29; SD = 3.7; range 23-35 years. All participants had hearing level not worse than 25dB HL at octave frequencies from 250Hz to 4000Hz. Listeners’ task was to adjust the level of music played in quiet to their most comfortable listening level and then to adjust the level of background noise to the maximum level that they still consider acceptable while listening to music. Further, music is not a speech signal that many researchers have used to determine the significance of age on ANL inter-subject variability. Results of this study supported the findings of others on age dependency, which shows that ANL inter and intra-subject variability is independent of age.

  11. The Real-Time Research of Optimal Power Flow Calculation in Reduce Active Power Loss Aspects of Power Grid

    OpenAIRE

    Yuting Pan; Yuchen Chen; Zhiqiang Yuan; Bo Liu

    2015-01-01

    In order to research how to availably reduce the active power loss value in power grid system when the power system is operating, it offers a quantitative research in theory through conceiving the unbalanced losses of power grid system under the overloading bus as the investigative object, and establishing an active power loss mathematical model. It carries out online real-time optimal flow calculation within the condition that meets the control variables and state variables of the equality a...

  12. Safety evaluation report related to the renewal of the operating license for the Zero-Power Reactor at Cornell University, Docket No. 50-97

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by Cornell University (CU) for a renewal of Operating License R-80 to continue to operate a zero-power reactor (ZPR) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Cornell University and is located on the Cornell campus in Ithaca, New York. The staff concludes that the ZPR facility can continue to be operated by CU without endangering the health and safety of the public

  13. Sexuality degree zero: pleasure and power in the novels of John Rechy, Arturo Islas, and Michael Nava.

    Science.gov (United States)

    Ortiz, R L

    1993-01-01

    "Sexuality Degree Zero" explores common themes and formal strategies in the fiction of three prominent gay Chicano writers: John Rechy, Arturo Islas, and Michael Nava. Employing the concept of a politicized textual "pleasure" as theorized by French critic Roland Barthes, the study argues for the political efficacy of aesthetic choices characteristic to the three authors. Analyses of Rechy's use of pornography, of Islas' transgressive use of cultural iconography, and of Nava's use of sexual "perversions" in the context of classic crime fiction, all go to demonstrate the various uses of pleasure in the construction of a doubly marginalized but defiant self and voice in fiction by gay Chicano men. PMID:8113611

  14. Fixing the 'zero state' at the main equipment of the primary coolant circuit at the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    To determine the reference, so-called 'zero' state of the main reactor components and to prepare the original fault-map, a four-fold inspection system was applied to the primary circuit equipment of the Paks NPP based on the inspection of the reactor components and weldings before and after assembly works and after cold and hot washings. Investigations are carried out either manually or using special manipulators able to inspect the welded joints, and the structural materials of the reactor vessels by means of ultrasonic measurements and to monitor visually the vessel mantles by means of TV cameras. (V.N.)

  15. Pengurangan Arus Harmonisa Urutan Nol Dengan Zero Sequence Blocking Transformer Dan Transformator Zig-Zag Yang Menggunakan Tiga Buah Transformator Satu Fasa

    OpenAIRE

    Pane, Zulkarnaen

    2014-01-01

    The zero-sequence harmonics current or the third sequence of harmonic current generated by non-linear loads potentially cause power quality problems on 4-wires 3-phase distributed systems. This research exposes an harmonic current suppression method by utilizing a zero sequence blocking transformer and a zig-zag transformer which employ three single-phase transformers. The zero sequence blocking transformer is connected serially to the power source to generate a high zero sequence impedance, ...

  16. Determination of the decay constants and relative abundances of delayed neutrons by noise analysis in zero-power reactors

    International Nuclear Information System (INIS)

    A reactor noise approach has been employed at the IPEN/MB-01 research reactor facility in order to determine experimentally the effective delayed neutron parameters βi and λi in a six group model and assuming the point reactor. The method can be considered a novice one because exploits the very low frequency domain of the spectral densities. The proposed method has some advantages to other in-pile methods since it does not disturb the reactor system and consequently does not 'excite' any sort of harmonic modes. As a byproduct and a consistency check, the βeff parameter was obtained without the need of the Diven factor and the power normalization and it is in excellent agreement with independent measurements. The theory/experiment comparison shows that for the abundances the JENDL 3.3 presents the best performance while for the decay constants the revised version of ENDF/B-VI.8 shows the best agreement. The best performance for the βeff determination is obtained with JENDL3.3. In contrast, ENDF/B-VI.8 and its revised version performed at LANL overestimate βeff by as much as 4%. The βeff results of this work support totally the proposal of reducing the thermal delayed neutron number for 235U fission as made by Sakurai and Okajima. A new observed effect related to the correlation between the fluctuations of both measurement channels is also presented and discussed. This effect can be considered as an indirect evidence for the use of the point reactor model in this work as well as a possible useful tool in the understanding of reactor dynamics. (author)

  17. Analysis of the KUCA MEU experiments using the ANL code system

    Energy Technology Data Exchange (ETDEWEB)

    Shiroya, S.; Hayashi, M.; Kanda, K.; Shibata, T.; Woodruff, W.L.; Matos, J.E.

    1982-01-01

    This paper provides some preliminary results on the analysis of the KUCA critical experiments using the ANL code system. Since this system was employed in the earlier neutronics calculations for the KUHFR, it is important to assess its capabilities for the KUHFR. The KUHFR has a unique core configuration which is difficult to model precisely with current diffusion theory codes. This paper also provides some results from a finite-element diffusion code (2D-FEM-KUR), which was developed in a cooperative research program between KURRI and JAERI. This code provides the capability for mockup of a complex core configuration as the KUHFR. Using the same group constants generated by the EPRI-CELL code, the results of the 2D-FEM-KUR code are compared with the finite difference diffusion code (DIF3D(2D) which is mainly employed in this analysis.

  18. Future Directions in Community Power Research: A Colloquium.

    Science.gov (United States)

    Wirt, Frederick M., Ed.

    This compilation of symposium papers on community power structure research focuses on the theme that community power structure research must shift away from case study methods and move toward aggregate data analysis. Advocating comparative analysis, seven authors present their views under the following topics: (1) Charles R. Adrian, "Several Loose…

  19. Design and research of CSR dipole pulsed thyristor power supply

    International Nuclear Information System (INIS)

    The pulsed power supply is very important for HIRFL-CSR power supply system. All power supplies in CSRm and CSRe need pulsed operation mode. These power supplies must have high current stability, low current ripple and good dynamic characteristic. A small-scale thyristor rectifier prototype has been researched and designed to find and solve all technique problems of pulsed power supply. The parameters of prototype are the same or higher than dipole power supplies in CSRm and CSRe. The tested results are satisfied

  20. Research for nuclear power. A Swiss perspective

    International Nuclear Information System (INIS)

    Nuclear energy research in Switzerland is concentrated in the Department for Nuclear Energy and Safety Research of the Paul Scherrer Institute (PSI). Nuclear research at PSI is structured around three main poles: safety and related operational issues for existing NPPs, nuclear waste management, and safety characteristics of future reactor concepts. Further, global aspects of energy systems are examined with regard to safety, economics and environmental impact. Presently, a total effort of about 200 py/a is invested in the nuclear research. Government funding of nuclear research was relatively stable during recent years, reaching about 35 MCHF/a. External funding of about 15 MCHF/a is expected to remain stable. (R.P.)

  1. Research and development for Canadian nuclear power

    International Nuclear Information System (INIS)

    Rapid expansion of the successful CANDU reactor system offers immediate substitution for scarce oil and gas, combined with long-term security of energy supplies. A continuing large and vigorous R and D program on nuclear power is essential to achieve these objectives. The program, described here, consists of tactical R and D in support of the current CANDU reactor system, strategic R and D to develop and demonstrate advanced CANDU systems, and exploratory R and D to put Canada in a position to exploit any fusion opportunities. Two support activities, management of radioactive wastes and techniques to safeguard nuclear materials against diversion, although integral components of the nuclear power programs, are identified separately because they are currently of special public interest. (author)

  2. Research on the Wind Power Penetration Limit in Power System

    Directory of Open Access Journals (Sweden)

    Yang Zhang

    2013-08-01

    Full Text Available An approach to calculate the wind farm penetration capacity based on chance constrained programming combining with transient check was presented. A novel model for programming penetration of wind farm under indeterminacy operating mode was presented. Constraint condition consisted of conventional generator output limits, system spinning reserve, transmission lines capability, nodal voltage, system frequency etc, and genetic algorithm based on Monte Carlo simulating was used to solve the problem, and the actual sample system verified the feasibility of the model and method. Results for the application of this approach revealed the influencing factors of penetration of wind farm consisted of the parallel node voltage, the output variation range of wind generating set and mean wind speed etc. The research results have important practical significance, which can guide the actual wind farms in the planning and operation analysis of reality wind farm.  

  3. Chamber dynamic research with pulsed power

    Energy Technology Data Exchange (ETDEWEB)

    PETERSON,ROBERT R.; OLSON,CRAIG L.; RENK,TIMOTHY J.; ROCHAU,GARY E.; SWEENEY,MARY ANN

    2000-05-15

    In Inertial Fusion Energy (IFE), Target Chamber Dynamics (TCD) is an integral part of the target chamber design and performance. TCD includes target output deposition of target x-rays, ions and neutrons in target chamber gases and structures, vaporization and melting of target chamber materials, radiation-hydrodynamics in target chamber vapors and gases, and chamber conditions at the time of target and beam injections. Pulsed power provides a unique environment for IFE-TCD validation experiments in two important ways: they do not require the very clean conditions which lasers need and they currently provide large x-ray and ion energies.

  4. Meson facility. Powerful new research tool

    International Nuclear Information System (INIS)

    A meson facility is being built at the Institute of Nuclear Research, USSR Academy of Sciences, in Troitsk, where the Scientific Center, USSR Academy of Sciences is located. The facility will include a linear accelerator for protons and negative hydrogen ions with 600 MeV energy and 0.5-1 mA beam current. Some fundamental studies that can be studied at a meson facility are described in the areas of elementary particles, neutron physics, solid state physics, and applied research. The characteristics of the linear accelerator are given and the meson facility's experimental complex is described

  5. Acceptable noise level (ANL) with Danish and non-semantic speech materials in adult hearing-aid users

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Lantz, Johannes; Nielsen, Lars Holme;

    2012-01-01

    The acceptable noise level (ANL) test is used for quantification of the amount of background noise subjects accept when listening to speech. This study investigates Danish hearing-aid users' ANL performance using Danish and non-semantic speech signals, the repeatability of ANL, and the associatio...

  6. Acceptable noise level (ANL) with Danish and non-semantic speech materials in adult hearing-aid users

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Lantz, Johannes; Nielsen, Lars Holme;

    2012-01-01

    The acceptable noise level (ANL) test is used for quantification of the amount of background noise subjects accept when listening to speech. This study investigates Danish hearing-aid users' ANL performance using Danish and non-semantic speech signals, the repeatability of ANL, and the association...

  7. Ultralight Solar Powered Hybrid Research Drone

    CERN Document Server

    Singer, Csaba

    2013-01-01

    A planetary research drone is proposed, which is capable for vertical takeoff and landing. A hybrid flight concept utilizing static lift enables the exploration over ground. The static lift is achieved with a lighter than CO2 gas like air, He or H2.

  8. Exergy Analysis of Zero CO2 Emission SOFC Hybrid Power System%基于炯分析的CO2零排放SOFC 复合动力系统研究

    Institute of Scientific and Technical Information of China (English)

    段立强; 张潇元; 杨勇平; 徐钢

    2011-01-01

    Based on a traditional SOFC (Solid Oxide Fuel Cell) hybrid power system, zero CO2emission SOFC hybrid power systems are proposed in this paper, and the comparison results of theall systems are revealed in detail. Compared with the conventional power plants with CO2 capture,the new systems greatly reduce the energy consumption for CO2 capture. Based on exergy analysismethod, the exergy loss distribution for every unit of system is revealed and compared. The largestexergy destruction part is pointed out and some feasible ways to further lowering the exergy loss areprovided. In addition, some key operation parameters are optimized. The research achievements from this paper will provide the valuable reference for further study on of zero CO2 emissions SOFC hybridpower systems with higher efficiency.%本文建立了SOFC复合动力系统模型,提出了两种CO2零排放的SOFC复合动力系统,并对这两种系统的性能进行了详细的比较和分析.与常规的进行脱除CO2电厂相比,极大地降低了回收CO2的能耗.基于(火用)分析理论,详细比较了系统各单元(火用)损系数,找出(火用)损的最大部位并提出解决措施.通过优化分析,得到运行参数的最佳值.本文研究成果将为进一步研究高效的CO2零排放SOFC复合动力系统提供有益的参考.

  9. The cost of integration of zero emission power plants-A case study for the island of Cyprus

    International Nuclear Information System (INIS)

    In this work, a technical, economic and environmental analysis is carried out for the estimation of the optimal option scenario for the Cyprus's future power generation system. A range of power generation technologies integrated with carbon capture and storage (CCS) were examined as candidate options and compared with the business as usual scenario. Based on the input data and the assumptions made, the simulations indicated that the integrated gasification combined cycle (IGCC) technology with pre-combustion CCS integration is the least cost option for the future expansion of the power generation system. In particular, the results showed that for a natural gas price of 7.9US$/GJ the IGCC technology with pre-combustion CCS integration is the most economical choice, closely followed by the pulverized coal technology with post-combustion CCS integration. The combined cycle technology can, also, be considered as alternative competitive technology. The combined cycle technologies with pre- or post-combustion CCS integration yield more expensive electricity unit cost. In addition, a sensitivity analysis has been also carried out in order to examine the effect of the natural gas price on the optimum planning. For natural gas prices greater than 6.4US$/GJ the least cost option is the use of IGCC technology with CCS integration. It can be concluded that the Cyprus's power generation system can be shifted slowly towards the utilization of CCS technologies in favor of the existing steam power plants in order not only to lower the environmental emissions and fulfilling the recent European Union Energy Package requirements but also to reduce the associated electricity unit cost

  10. Technology at Ground Zero.

    Science.gov (United States)

    Techniques: Connecting Education and Careers, 2002

    2002-01-01

    Describes the robots used to aid in rescue and recovery at Ground Zero after the September 11, 2001 attack on the World Trade Center. The robots were developed as a result of national Science Foundation Quick Response Research Awards. Describes several awards that were made following the attack. (JOW)

  11. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.; Rockwell, V.S.

    1992-08-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization plans for Word Processors, Personal Computers, Workstations, and Associated Software (ANL/TM, Revision 4) to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference document that (1) documents the plans of each organization for office automation, (2) identifies appropriate planners and other contact people in those organizations and (3) encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations (ANL/TM 458) and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan (ANL/TM 466).

  12. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.; Rockwell, V.S.

    1992-08-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization plans for Word Processors, Personal Computers, Workstations, and Associated Software (ANL/TM, Revision 4) to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference document that (1) documents the plans of each organization for office automation, (2) identifies appropriate planners and other contact people in those organizations and (3) encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations (ANL/TM 458) and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan (ANL/TM 466).

  13. Nuclear Power Plant Containment Pressure Boundary Research

    International Nuclear Information System (INIS)

    Research to address aging of the containment pressure boundary in light-water reactor plants is summarized. This research is aimed at understanding the significant factors relating occurrence of corrosion, efficacy of inspection, and structural capacity reduction of steel containment and liners of concrete containment. This understanding will lead to improvements in risk-informed regulatory decision making. Containment pressure boundary components are described and potential aging factors identified. Quantitative tools for condition assessments of aging structures to maintain an acceptable level of reliability over the service life of the plant are discussed. Finally, the impact of aging (i.e., loss of shell thickness due to corrosion) on steel containment fragility for a pressurized water reactor ice-condenser plant is presented

  14. Solar Power as a Source of Noise-free Power for Research

    OpenAIRE

    Dutta, Akshita; Chorescu, Irinel

    2011-01-01

    There has been increasing interest in solar convertors, mostly for energy. A further and in some cases primary advantage for many applications is the immunity to noise and interference. Many research disciplines that are dependent on sensitive research instrumentation can benefit from it, since solar power precludes the 60Hz (and multiples) noise of grid power. In this paper, we present a study that implements solar direct current (D.C.) power to eliminate such background disturbances. We mea...

  15. Carrier escape from ground state and non-zero resonance frequency at low bias powers for semiconductor quantum-dot lasers

    Science.gov (United States)

    Wang, C.; Grillot, F.; Even, J.

    2012-06-01

    The three-dimensional confinement of electrons and holes in the semiconductor quantum dot (QD) structure profoundly changes its density of states compared to the bulk semiconductor or the thin-film quantum well (QW) structure. The aim of this paper is to theoretically investigate the microwave properties of InAs/InP(311B) QD lasers. A new expression of the modulation transfer function is derived for the analysis of QD laser modulation properties based on a set of four rate equations. Analytical calculations point out that carrier escape from ground state (GS) to excited state (ES) induces a non-zero resonance frequency at low bias powers. Calculations also show that the carrier escape leads to a larger damping factor offset as compared to conventional QW lasers. These results are of prime importance for a better understanding of the carrier dynamics in QD lasers as well as for further optimization of low cost sources for optical telecommunications.

  16. Status report about the works for the start up of the RA-0 'zero power' nuclear reactor at the Cordoba National University

    International Nuclear Information System (INIS)

    After two years of works at the Cordoba National University for the new start-up of the RA-0 'zero power' nuclear reactor, the results obtained are herein presented. Starting with practically null infrastructure at the beginning, specially in human resources and instrumentation of the reactor, the objectives can be considered satisfactory. The training in work of the future operational staff, the design and the construction of the instrumentation and the fitting of the installations are the principal items described in this paper. An special attention is devoted to the insertion of this type of installation in the university organization, usually not prepared for the quality and control activities, which is necessarily considered in these type of works. (Author)

  17. Does the acceptable noise level (ANL) predict hearing-aid use?

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Brännström, K Jonas

    2014-01-01

    OBJECTIVE: It has been suggested that individuals have an inherent acceptance of noise in the presence of speech, and that different acceptance of noise results in different hearing-aid (HA) use. The acceptable noise level (ANL) has been proposed for measurement of this property. It has been...... reviewed journals as well as a number of papers from trade journals, posters and oral presentations from audiologyconventions. CONCLUSIONS: An inherent acceptance of noise in the presence of speech may exist, but no method for precise measurement of ANL is available. The ANL model for prediction of HA use...

  18. Research on hydraulic-powered roof supports test problems

    Institute of Scientific and Technical Information of China (English)

    SUN Hong-bo; JIANG Jin-qiu; MA Qiang

    2011-01-01

    The load-bearing characters of hydraulic-powered roof support with dual telescopic legs were analyzed. With a specific type hydraulic-powered roof support with dual telescopic legs for research object, the inside load test problems in factories was analyzed, and the correct test methods were given, which can enhance the test efficiency and make the factories away from the error design of hydraulic-powered roof supports and legs.

  19. Nuclear Power Plant Fire Protection Research Program

    International Nuclear Information System (INIS)

    The goal is to develop test data and analytical capabilities to support the evaluation of: (1) the contribution of fires to the risk from nuclear power plants; (2) the effects of fires on control room equipment and operations; and (3) the effects of actuation of fire suppression systems on safety equipment. A range of fire sources will be characterized with respect to their energy and mass evolution, including smoke, corrosion products, and electrically conductive products of combustion. An analytical method for determining the environment resulting from fire will be developed. This method will account for the source characteristics, the suppression action following detection of the fire, and certain parameters specific to the plant enclosure in which the fire originates, such as the geometry of the enclosure and the ventilation rate. The developing local environment in the vicinity of safety-related equipment will be expressed in terms of temperatures, temperature rise rates, heat fluxes, and moisture and certain species content. The response of certain safe shutdown equipment and components to the environmental conditions will be studied. The objective will be to determine the limits of environmental conditions that a component may be exposed to without impairment of its ability to function

  20. Research on psychological evaluation method for nuclear power plant operators

    International Nuclear Information System (INIS)

    The qualitative and quantitative psychology evaluation methods to the nuclear power plant operators were analyzed and discussed in the paper. The comparison analysis to the scope and result of application was carried out between method of outline figure fitted and method of fuzzy synthetic evaluation. The research results can be referenced to the evaluation of nuclear power plant operators. (authors)

  1. ANL statement of site strategy for computing workstations

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R. (ed.); Boxberger, L.M.; Amiot, L.W.; Bretscher, M.E.; Engert, D.E.; Moszur, F.M.; Mueller, C.J.; O' Brien, D.E.; Schlesselman, C.G.; Troyer, L.J.

    1991-11-01

    This Statement of Site Strategy describes the procedure at Argonne National Laboratory for defining, acquiring, using, and evaluating scientific and office workstations and related equipment and software in accord with DOE Order 1360.1A (5-30-85), and Laboratory policy. It is Laboratory policy to promote the installation and use of computing workstations to improve productivity and communications for both programmatic and support personnel, to ensure that computing workstations acquisitions meet the expressed need in a cost-effective manner, and to ensure that acquisitions of computing workstations are in accord with Laboratory and DOE policies. The overall computing site strategy at ANL is to develop a hierarchy of integrated computing system resources to address the current and future computing needs of the laboratory. The major system components of this hierarchical strategy are: Supercomputers, Parallel computers, Centralized general purpose computers, Distributed multipurpose minicomputers, and Computing workstations and office automation support systems. Computing workstations include personal computers, scientific and engineering workstations, computer terminals, microcomputers, word processing and office automation electronic workstations, and associated software and peripheral devices costing less than $25,000 per item.

  2. Zero emission power plants - a compatibility of the postcombustion technologies for the reduction of the Carbon emissions from thermal power plants with Directive 1996/61/EC

    International Nuclear Information System (INIS)

    An assessment of postcombustion- technologies for the reduction of the carbon emissions from thermal power plants with the Directive 1996/61/EC is done. It cannot be done quantitatively as in Bulgarian thermal power plants the carbon capture installations are not built. (authors)

  3. Zero-point energy

    International Nuclear Information System (INIS)

    Recently, investigations of novel non-conventional sources of energy and propulsion technologies have led to the belief that vacuum fluctuations or zero-point energy (ZPE) can be tapped as an additional prime mover alongside fusion, fission, hydrocarbons, hydropower, geothermal and solar-based technologies. Only a handful of researchers have seriously investigated the possible use of vacuum fluctuation energy for power production and gravitational interaction and suggested methods of experimentation, among them, Vallee, Puthoff, Tchernetsky, and Alzofon. In theories ranging from advanced semi-classical treatments to quantum electrodynamics (QED) and dynamic nuclear orientation, they suggest several more or less practical approaches to interacting with vacuum fluctuation energy which may be undertaken with today's technology. Notwithstanding the paucity of consistent, repeatable results directly attributable to vacuum interactions, it is possible to outline the engineering tools and techniques required to begin to investigate ZPE. Extremely high frequency oscillations at high field strengths (Vallee), highly non-linear plasmas or arcs (Tchernetsky), super-high charge concentrations or field gradients (Puthoff), and dynamic magnetic resonance cooling of nuclei (Alzofon) are prime candidates for investigation at present. The paper attempts to draw together the most practical aspects of this, which is currently at a sufficiently advance stage to allow initial experiments to be designed. Only the essentials of the theories propounded will be presented, chiefly those aspects from which real-world physical apparatus and order-of-magnitude measurements can be deduced. The work of other researchers which may have a bearing on the subject will also be briefly touched upon

  4. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.

    1991-11-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization Plans for Word Processors, Personal Computers, Workstations, and Associated Software to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference that documents the plans of each organization for office automation, identifies appropriate planners and other contact people in those organizations, and encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan.

  5. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.

    1991-11-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization Plans for Word Processors, Personal Computers, Workstations, and Associated Software to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference that documents the plans of each organization for office automation, identifies appropriate planners and other contact people in those organizations, and encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan.

  6. ENFICA-FC: Design of transport aircraft powered by fuel cell & flight test of zero emission 2-seater aircraft powered by fuel cells fueled by hydrogen

    OpenAIRE

    Cestino, Enrico; Borello, Fabio; Romeo, Giulio

    2013-01-01

    Fuel cells could become the main power source for small general aviation aircraft or could replace APU and internal sub-systems on larger aircraft, to obtain all-electric or more-electric air vehicles. There are several potential advantages of using such a power source, that range from environmental and economic issues to performance and operability aspects. A preliminary design is reported. Also, the paper contains a description of testing activities related to experimental flights of an all...

  7. Coupled 3-D kinetics thermal-hydraulic analysis of Hot Zero Power main steam line breaks using RETRAN and STAR codes

    International Nuclear Information System (INIS)

    The Main Steam Line Break (MSLB) at End of Life (EOL), Hot Zero Power (HZP) conditions accident was analyzed using a fully time-dependent coupled thermal-hydraulic (T/H) and neutronics method, and compared against conservative Final Safety Analysis Report (FSAR) results, which predict a return-to-power. The development and improvement of coupled neutronics/T/H analysis techniques provide many advantages including the capability to evaluate the impact of modeling assumptions made in previous reactor kinetics and T/H calculations. The coupled STAR kinetics and RETRAN T/H techniques developed here provides a means to evaluate the quasi-static, point kinetics approximation against a fully time-dependent, three-dimensional approach. Using the state-of-the-art 3-D STAR reactor kinetics code with the RETRAN reactor coolant system (RCS) T/H code in a best-estimate approach, it is now possible to evaluate the impact on safety margins imposed by conservative FSAR MSLB assumptions. The method presented shows how the time-dependent 3-D STAR nodal code model was used directly with core inlet conditions determined by RETRAN for a Westinghouse PWR. The STAR/RETRAN results clearly demonstrate that a return-to-power is NOT predicted when a 3-D thermal-hydraulically coupled time-dependent kinetics approach is used. This study shows that: (a) quasi-static and point kinetics methods are not able to describe severe PWR asymmetric transient phenomena adequately; and (b) fully coupled, 3-D time-dependent analysis methods should be used for PWR reactor transients instead. By coupling the RCS response in terms of updated core inlet conditions with 3-D time-dependent core kinetics response, in a tandem manner, the core power and T/H RCS conditions are forced to be self-consistent during the entire event, when non-equilibrium conditions exist. (orig.)

  8. Current Status of Research on Hybrid Power Generation Systems

    Directory of Open Access Journals (Sweden)

    Madan A. Sendhil

    2014-10-01

    Full Text Available The main aim of this paper is a detailed study of recent developments in hybrid power generation systems. Renewable energy sources nowadays play a vital role in efficient and pollution free electric power generation systems as a recent trend. Solar energy and wind energy are the most popular sources of power generation in many developing countries. This study presents a detailed analysis of recent research works that are made in the field of renewable power generation systems and a study of various hybridization methodologies of electric power generation schemes and electrical energy utilization from solar, wind, diesel, biomass and thermal power generating systems. In this study various IEEE journals, magazines and conference proceedings has been analyzed and are concluded.

  9. Experimental results from the Lysekil Wave Power Research Site

    OpenAIRE

    Svensson, Olle

    2012-01-01

    This thesis presents how experimental results, from wave power research performed offshore at the Lysekil research site, were obtained. The data were used to verify theoretical models as well as evaluate the feasibility of wave power as a future sustainable energy source. The first experiments carried out at the research site was the measurement of the force in a line where one end was connected to a buoy with a diameter of 3 m and the other end to a set of springs with limited stroke length....

  10. DANBIO-powerful research database and electronic patient record

    DEFF Research Database (Denmark)

    Hetland, Merete Lund

    2011-01-01

    an overview of the research outcome and presents the cohorts of RA patients. The registry, which is approved as a national quality registry, includes patients with RA, PsA and AS, who are followed longitudinally. Data are captured electronically from the source (patients and health personnel). The IT...... an electronic patient 'chronicle' in routine care, and at the same time provides a powerful research database.......The nationwide DANBIO registry has been designed to capture operational clinical data as part of routine clinical care. At the same time, it provides a powerful research database. This article reviews the DANBIO registry with focus on problems and solutions of design, funding and linkage, provides...

  11. Nuclear Power Plant Operator Reliability Research Based on Fuzzy Math

    International Nuclear Information System (INIS)

    This paper makes use of the concept and theory of fuzzy number in fuzzy mathematics, to research for the response time of operator in accident of Chinese nuclear power plant. Through the quantitative analysis for the performance shape factors (PSFs) which influence the response time of operators, the formula of the operator response time is obtained based on the possibilistic fuzzy linear regression model which is used for the first time in this kind of research. The research result shows that the correct research method can be achieved through the analysis of the information from a small sample. This method breaks through the traditional research method and can be used not only for the reference to the safe operation of nuclear power plant, but also in other areas.

  12. Design study of a fast spectrum zero-power reactor dedicated to source driven sub-critical experiments

    Energy Technology Data Exchange (ETDEWEB)

    Mercatali, L.; Serikov, A. [Forschungszentrum Karlsruhe, Institute for Neutron Physics and Reactor Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Baeten, P.; Uyttenhove, W. [SCK-CEN, Boeretang 200, B-2400 Mol (Belgium); Lafuente, A. [Univerisdad Politecnica de Madrid, 28006 Madrid (Spain); Teles, P. [Instituto Tecnologico e Nuclear, EN 10, 2680-953 Sacavem (Portugal)

    2010-09-15

    In the framework of the European P and T program (IFP6-EUROTRANS), the Generation of Uninterrupted Intense NEutrons pulses at the lead VEnus REactor (GUINEVERE) project consists of an Accelerator Driven System (ADS) that is composed by a fast lead simulated-cooled reactor operated in sub-critical conditions, coupled with an updated version of the GENEPI neutron generator previously used for the MUSE experiments. The GUINEVERE facility aims at developing and improving different techniques for the reactivity monitoring of sub-critical ADS's. As such, the GUINEVERE project will comprise a series of major experiments that will be performed in the near future. The GUINEVERE facility will be located at the VENUS light water moderated research reactor at the SCK-CEN site of Mol (Belgium), which needs to be modified in order to accommodate a completely different and new type of core. A series of constraints were taken into account in the technical design of the GUINEVERE core, in order to properly conjugate the technical feasibility of this facility and the necessity to comply with the envisioned experimental program and its associated scientific outcome. The complete design study of the GUINEVERE core is the subject of this paper. The final design of the fuel assemblies, safety and control rods is provided. Also, the critical core configuration, to be used as reference for absolute reactivity measurements, is presented along with its associated reactor physics parameters, calculated by means of Monte Carlo methodologies. Finally, for licensing purposes, the GUINEVERE facility must satisfy the required nuclear safety criteria of the Belgian safety authorities, and in this paper, an overview of the safety analysis that has been performed with regard to the core physics, thermal assessment and shielding issues is also provided. (author)

  13. Research on export system of marine nuclear power device

    International Nuclear Information System (INIS)

    A marine nuclear power plant simulation system is founded, and a management expert system, which can administer and diagnose the typical faults, is constituted by the intelligent expert theory. This real-time expert system can analyze the reason of the typical fault caused by the nuclear power plant practically running and give the best solvent by the expert knowledge reasoning in the repository; a neural network fault inspection and diagnosis expert system which can inspect every equipment continually and give the faults diagnosis result based on the inspective dates is established. Based on the three hierarchical architecture, the operation performance is improved very much by using of the neural network fault inspection and diagnosis expert system to inspect and diagnose the nuclear power plant faults and the management expert system to supervise the nuclear power plant running. The expert system research can give guidance for the marine nuclear power plant safety operation

  14. Syrinx - a research program for the pulsed power radiation facility

    International Nuclear Information System (INIS)

    Syrinx is a targeted research program with the objective to study, through practical examples, the fundamentals necessary to define the details of all parts which will be required for a new powerful plasma radiation source. The current level of activities of Syrinx is in the design and construction of a multi-megajoule class IES based pulsed power driver which will use long conduction Plasma Opening Switch technology. The present paper reviews mainly the basic experimental research of the POS a nd Z-pinch accomplished in the framework of Syrinx project. This work has a unique international level of participation, from conceptual designs to particular investigations. (author). 9 figs., 17 refs

  15. Technology and use of low power research reactors

    International Nuclear Information System (INIS)

    The report contains a summary of discussions and 10 papers presented at the Consultants' Meeting on the Technology and Use of Low Power Research Reactors organized by the IAEA and held in Beijing (China) during 30 April - 3 May 1985. The following topics have been covered: reactor utilization in medicine and biology, in universities, for training, as a neutron source for radiography and some remarks on the safety of low power research reactors. A separate abstract was prepared for each paper presented at the meeting

  16. WIMS-ANL 4.0, Deterministic Code System for Lattice Calculation

    International Nuclear Information System (INIS)

    1 - Description of program or function: The WIMS-ANL code is an extension of the Winfrith WIMS-D4 code for lattice cell computations. This code has been tailored to address some of the problem areas encountered in dealing with research reactor fuels, experiment, reflector and control regions. The SUPERCELL option eliminates some of the limitations of the traditional SPECTROX solution and supports the solution of more complex geometries with a more detailed spatial mesh and multiple resonance materials. The code generates both macroscopic and microscopic cross sections in the ISOTXS format with any selected number of energy groups. The user can specify which fission product isotopes are to be explicitly included in the microscopic burnup dependent ISOTXS library. Fission product library data can be generated for use with the MCNP code and burnup dependent applications. The cross section library data provided are based on ENDF/B version VI (69 group) and V (69 and 172 group) data. A revised 172 group library based on ENDF/B-VI is being generated with newer data and additional isotopes. This library will be made available at a later time. The code is variably dimensioned so that other group structures could be used. The source code and output format have been completely revised to reflect current coding practices and to permit display of the results on typical desk top monitors. The content of the output displayed is completely under the user's control. 2 - Methods:The methods of solution in WIMS-ANL remain unchanged from those used in the original WIMS-D4 code with the same resonance treatment and a choice of collision probability and DSN solutions for the simple lattice cell. The SUPERCELL option provides for the selection of supporting auxiliary cells that might represent the various different elements and varying spectra of the final SUPERCELL model. The resonance treatments where applicable are carried out in the auxiliary cells. These data are combined in the

  17. ZERO WASTE

    OpenAIRE

    Upadhyaya, Luv

    2013-01-01

    The aim of the thesis was to develop a clear vision on better waste management system. The thesis introduced the sustainable waste management along with innovation. The aim of the research was to find out the types of waste being introduced to environment, their consequence on human beings and surroundings, best policies, principles and practices to minimize the effect of the waste to lowest. The study was based on literature. The thesis includes the introduction of types of waste, clarifi...

  18. Development of nuclear power plant safety research in the USSR

    International Nuclear Information System (INIS)

    The progress in the development of any industry including nuclear power depends substantially on its safety for men and their environment. The most serious potential danger of nuclear power development is the radioactive contamination of biosphere. The safety of nuclear power in the USSR means the quality of nuclear power plants as the results of inherent design features, special engineering means and organizational and technical measures. To solve the problem of the safety, it is generally necessary to establish the goal and the corresponding criteria of safety, to develop the engineering safety means for ensuring the implementation of the adopted safety criteria, and to develop the administrative and organizational requirements and measures. To develop the measures for controlling the safety, it is necessary to create effective accident prevention means. On the basis of these principles, the hydrodynamic and heat exchange studies on reactor facilities in accidents, the research on the behavior of fuel elements and assemblies in accidents, the research on the release of fission products during serious accidents, the study on the presence of hydrogen in nuclear power plants, and the reliability analysis of the systems and components in nuclear power plants, the probabilistic safety analysis and risk assessment have been carried out. (Kako, I.)

  19. Mighty Morphin Power Ranger Play: Research and Reality.

    Science.gov (United States)

    Crosser, Sandra

    1995-01-01

    Explores the question of whether or not Mighty Morphin Power Rangers-type aggressive play is developmentally appropriate for the early childhood classroom. Compares results from research in child development to the reality of television programming, highlighting the relationship between television violence and children's aggressive behavior. (AA)

  20. Basic research on human reliability in nuclear power plants

    International Nuclear Information System (INIS)

    Human reliability in nuclear power plants is one of key factors in nuclear safety and economic operation. According to cognitive science, behaviour theory and ergonomic and on the bases of human cognitive behaviour characteristics, performance shaping factors, human error mechanisms and organization management, the project systematically studied the human reliability in nuclear power plant systems, established the basic theory and methods for analyzing human factor accidents and suggested feasible approaches and countermeasures for precaution against human factor accidents and improving human reliability. The achievement has been applied in operation departments, management departments and scientific research institutions of nuclear power, and has produced guiding significance and practical value to design, operation and management in nuclear power plants. (11 refs.)

  1. Research Reactor Power Control System Design by MATLAB/SIMULINK

    Energy Technology Data Exchange (ETDEWEB)

    Baang, Dane; Suh, Yong Suk; Kim, Young Ki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Im, Ki Hong [Samsung Electronics, Suwon (Korea, Republic of)

    2013-07-01

    In this study it is presented that MATLAB/SIMULINK can be efficiently used for modeling and power control system design for research reactors. The presented power control system deals with various functions including reactivity control, signals processing, reactivity calculation, alarm request generation, etc., thus it is required to test all the software logic using proper model for reactor, control rods, and field instruments. In MATLAB/SIMULINK tool, point kinetics, thermal model, control absorber rod model, and other instrument models were developed based on reactor parameters and known properties of each component or system. The software for power control system was invented and linked to the model to test each function. From the simulation result it is shown that the power control performance and other functions of the system can be easily tested and analyzed in the proposed simulation structure.

  2. Research Reactor Power Control System Design by MATLAB/SIMULINK

    International Nuclear Information System (INIS)

    In this study it is presented that MATLAB/SIMULINK can be efficiently used for modeling and power control system design for research reactors. The presented power control system deals with various functions including reactivity control, signals processing, reactivity calculation, alarm request generation, etc., thus it is required to test all the software logic using proper model for reactor, control rods, and field instruments. In MATLAB/SIMULINK tool, point kinetics, thermal model, control absorber rod model, and other instrument models were developed based on reactor parameters and known properties of each component or system. The software for power control system was invented and linked to the model to test each function. From the simulation result it is shown that the power control performance and other functions of the system can be easily tested and analyzed in the proposed simulation structure

  3. Uncertainty Evaluation for Core Thermal Power in a Research Reactor

    International Nuclear Information System (INIS)

    The Jordan Research and Training Reactor (JRTR) also has three separated and independent channels of the neutron detectors to measure the core power. To calibrate these detectors, the thermal power of Primary Cooling System (PCS) which cools down the heat generated in reactor core is used as calibration reference. The core thermal power can be estimated by the measured values of the mass flow rate, core inlet temperature, and core outlet temperature of coolant in the PCS. In general, the uncertainty of the core thermal power is required to be controlled below a certain value. To meet this requirement, the uncertainty of core thermal power should be evaluated based on the uncertainty of the measured parameters. In this paper, the uncertain evaluation is conducted with variation of the uncertainty of the measured parameters such as mass flow rate, core inlet temperature, core outlet temperature. In addition, the numbers of inlet and outlet temperature are considered to get a higher allowable uncertainty of temperature sensors. The core thermal power uncertainty has been valuated according to measuring parameters such as mass flow rate, temperatures, and number of RTDs. In this parametric study, allowable uncertainties for measuring devices have been obtained to guarantee 5% of the core thermal power uncertainty

  4. Uncertainty Evaluation for Core Thermal Power in a Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sunil; Seo, Kyoung-Woo; Kim, Seong-Hoon; Chi, Dae-Young; Park, Cheol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The Jordan Research and Training Reactor (JRTR) also has three separated and independent channels of the neutron detectors to measure the core power. To calibrate these detectors, the thermal power of Primary Cooling System (PCS) which cools down the heat generated in reactor core is used as calibration reference. The core thermal power can be estimated by the measured values of the mass flow rate, core inlet temperature, and core outlet temperature of coolant in the PCS. In general, the uncertainty of the core thermal power is required to be controlled below a certain value. To meet this requirement, the uncertainty of core thermal power should be evaluated based on the uncertainty of the measured parameters. In this paper, the uncertain evaluation is conducted with variation of the uncertainty of the measured parameters such as mass flow rate, core inlet temperature, core outlet temperature. In addition, the numbers of inlet and outlet temperature are considered to get a higher allowable uncertainty of temperature sensors. The core thermal power uncertainty has been valuated according to measuring parameters such as mass flow rate, temperatures, and number of RTDs. In this parametric study, allowable uncertainties for measuring devices have been obtained to guarantee 5% of the core thermal power uncertainty.

  5. Development of 3D full-core ERANOS-2.2/MCNPX-2.7.0 models and neutronic analysis of the BFS-2 zero-power facility

    International Nuclear Information System (INIS)

    The present paper is addressing the development and validation against experimental data of 3D full-core models of the BFS-2 zero-power fast-reactor using both the deterministic system code ERANOS-2.2 and the stochastic code MCNPX-2.7.0. The model configuration of BFS considered for analysis is the BFS-62-3A benchmark. To extend the - deterministic/stochastic - code-to-code comparison, neutronic parameters, i.e. reactivity, neutron spectrum and reaction rates, were also simulated at the cell level with the Monte Carlo code SERPENT-1.1.7 with two modern data libraries, ENDF-B/VII and JEFF-3.1.1. The BFS-2 critical zero-power facility at the Inst. of Physics and Power Engineering (IPPE) was designed for simulations of the core and shielding of sodium-cooled, fast reactors, for neutron data validation and comparison with experimental results. At the BFS-2 facility, the BFS-62-3A critical benchmark experiment was set-up as a mock-up of the BN-600 reactor, with hybrid MOX fuel and stainless steel reflectors. A UO2 blanket and a large non-homogeneous stainless-steel reflector surround the core. The lattice is hexagonal of pitch 5.1 cm and metallic dowels are used to keep in central position cylindrical rods made of different types of material (fissile, fertile, blanket, plenum, shielding and absorber). A typical subassembly is formed in piling up various pellets of about 1 cm in height and 4.6 cm in diameter, conferring large heterogeneity in the axial direction. The full-core model development was a complex task due to the large number of subassemblies and the axial subassembly heterogeneity. In ERANOS-2.2, it was necessary to homogenize axially per region the pellets used to form the subassembly. The self-shielded macroscopic cross-sections were calculated using the cell code ECCO in association with JEFF-3.1 and ENDF/B-VI.8 data libraries. The core calculations were performed with broad cross-sections data in 33 neutron energy groups with the solver AVNM in the

  6. Development of 3D full-core ERANOS-2.2/MCNPX-2.7.0 models and neutronic analysis of the BFS-2 zero-power facility

    Energy Technology Data Exchange (ETDEWEB)

    Girardin, G.; Alonso, M. [Ecole Polytechnique Federale de Lausanne EPFL, CH-1015 Lausanne (Switzerland); Mikityuk, K. [Paul Scherrer Institut PSI, CH-5232 Villigen-PSI (Switzerland)

    2012-07-01

    The present paper is addressing the development and validation against experimental data of 3D full-core models of the BFS-2 zero-power fast-reactor using both the deterministic system code ERANOS-2.2 and the stochastic code MCNPX-2.7.0. The model configuration of BFS considered for analysis is the BFS-62-3A benchmark. To extend the - deterministic/stochastic - code-to-code comparison, neutronic parameters, i.e. reactivity, neutron spectrum and reaction rates, were also simulated at the cell level with the Monte Carlo code SERPENT-1.1.7 with two modern data libraries, ENDF-B/VII and JEFF-3.1.1. The BFS-2 critical zero-power facility at the Inst. of Physics and Power Engineering (IPPE) was designed for simulations of the core and shielding of sodium-cooled, fast reactors, for neutron data validation and comparison with experimental results. At the BFS-2 facility, the BFS-62-3A critical benchmark experiment was set-up as a mock-up of the BN-600 reactor, with hybrid MOX fuel and stainless steel reflectors. A UO{sub 2} blanket and a large non-homogeneous stainless-steel reflector surround the core. The lattice is hexagonal of pitch 5.1 cm and metallic dowels are used to keep in central position cylindrical rods made of different types of material (fissile, fertile, blanket, plenum, shielding and absorber). A typical subassembly is formed in piling up various pellets of about 1 cm in height and 4.6 cm in diameter, conferring large heterogeneity in the axial direction. The full-core model development was a complex task due to the large number of subassemblies and the axial subassembly heterogeneity. In ERANOS-2.2, it was necessary to homogenize axially per region the pellets used to form the subassembly. The self-shielded macroscopic cross-sections were calculated using the cell code ECCO in association with JEFF-3.1 and ENDF/B-VI.8 data libraries. The core calculations were performed with broad cross-sections data in 33 neutron energy groups with the solver AVNM in the

  7. Effect size, confidence intervals and statistical power in psychological research.

    Directory of Open Access Journals (Sweden)

    Téllez A.

    2015-07-01

    Full Text Available Quantitative psychological research is focused on detecting the occurrence of certain population phenomena by analyzing data from a sample, and statistics is a particularly helpful mathematical tool that is used by researchers to evaluate hypotheses and make decisions to accept or reject such hypotheses. In this paper, the various statistical tools in psychological research are reviewed. The limitations of null hypothesis significance testing (NHST and the advantages of using effect size and its respective confidence intervals are explained, as the latter two measurements can provide important information about the results of a study. These measurements also can facilitate data interpretation and easily detect trivial effects, enabling researchers to make decisions in a more clinically relevant fashion. Moreover, it is recommended to establish an appropriate sample size by calculating the optimum statistical power at the moment that the research is designed. Psychological journal editors are encouraged to follow APA recommendations strictly and ask authors of original research studies to report the effect size, its confidence intervals, statistical power and, when required, any measure of clinical significance. Additionally, we must account for the teaching of statistics at the graduate level. At that level, students do not receive sufficient information concerning the importance of using different types of effect sizes and their confidence intervals according to the different types of research designs; instead, most of the information is focused on the various tools of NHST.

  8. Research and development toward realization of nuclear fusion power

    International Nuclear Information System (INIS)

    At National Institute for Fusion Science (NIFS), a part of National Institutes of Natural Sciences (NINS), conducts fundamental research of nuclear fusion power, which can generate energy from seawater. The research is centered on three main projects: (1) Large Helical Device (LHD) experiments, (2) computational simulations for experimental reactors, and (3) nuclear fusion engineering. This article introduces the basic principle of nuclear fusion power and the technologies that have been developed up to now, and then discusses future prospects. At first, in order to explain why human beings needs nuclear fusion power, the advantages of nuclear fusion power are described in comparison with other energy sources in terms of energy demand, available resources, carbon dioxide emission, and so on. Then, the current technological status of Helical method, which is being developed at our institute, and Tokamak method and other methods, which are being developed worldwide, as well as the reaction conditions for nuclear fusion are introduced. Furthermore, the future possibilities of nuclear fusion power mainly with Helical method but also with Tokamak method, as well as the outlook for the establishment of prototype reactor are discussed. (S.K.)

  9. RATU - Nuclear power plant structural safety research programme

    International Nuclear Information System (INIS)

    Studies on the structural materials in nuclear power plants create the experimental data and background information necessary for the structural integrity assessments of mechanical components. The research is carried out by developing experimental fracture mechanics methods including statistical analysis methods of materials property data, and by studying material ageing and, in particular, mechanisms of material deterioration due to neutron irradiation, corrosion and water chemistry. Besides material studies, new testing methods and sensors for measurement of loading and water chemistry parameters have been developed. The monitoring data obtained in real power plants has been used to simulate more precisely the real environment during laboratory tests. The research on structural analysis has focused on extending and verifying the analysis capabilities for structural assessments of nuclear power plants. A widely applicable system including various computational fracture assessment methods has been created with which different structural problems can be solved reliably and effectively. Research on reliability assessment of maintenance in nuclear power plants is directed to practical case studies on components and structures of safety importance, and to the development of models for maintenance related decision support. A systematic analysis of motor-operated valve has been performed

  10. Spin zero

    CERN Multimedia

    James Gillies

    2011-01-01

    This week saw the increasingly familiar sight of hordes of journalists descending on CERN to hear the latest news from the LHC. There were 66 of them to be precise, many of whom announced to us they planned to come for the seminar long before they were invited. It’s a sign of the times that science that used to be conducted in private is now carried out in the public domain. That has the potential to be very good news for science, and for society as a whole, particularly when CERN’s scientists do such a great job of conveying the passion and excitement of their research.   A typical Higgs candidate event in the CMS detector. We live in a science-dominated age, where everyone has to make science-based decisions on a daily basis. Yet at the same time, apathy towards science has been growing while pseudo-science gains ground. For that reason, it’s incumbent upon scientists to push science further up the popular agenda. The fact that the LHC has got the ‘...

  11. Marginalization and Power in Living with and Researching HIV

    DEFF Research Database (Denmark)

    Pedersen, Bodil Maria

    2005-01-01

    This article takes its point of departure in a research project studying the psychosocial problems of living with HIV. The project was intended to participate in changing practices dealing with these problems. It became a project including many differently situated and intersecting personal and...... generalized perspectives. The article researches the development of the HIV project as a contribution to discussions related to Participatory Action Research and Practice Research. In mainstream approaches methodological indications are often presented as rules to follow in order to ensure the quality of the...... obtained knowledge. But situated historical and societal processes are involved in the effectuation of the HIV project, like they are in any other project. Researching the project heightens the awareness of the necessity of reflecting on situated and historical issues of power and marginalization and on...

  12. Genes involved in the astrocyte-neuron lactate shuttle (ANLS) are specifcally regulated in cortical astrocytes following sleep deprivation in mice

    KAUST Repository

    Petit, Jean Marie

    2013-10-01

    Study Objectives: There is growing evidence indicating that in order to meet the neuronal energy demands, astrocytes provide lactate as an energy substrate for neurons through a mechanism called "astrocyte-neuron lactate shuttle" (ANLS). Since neuronal activity changes dramatically during vigilance states, we hypothesized that the ANLS may be regulated during the sleep-wake cycle. To test this hypothesis we investigated the expression of genes associated with the ANLS specifcally in astrocytes following sleep deprivation. Astrocytes were purifed by fuorescence-activated cell sorting from transgenic mice expressing the green fuorescent protein (GFP) under the control of the human astrocytic GFAP-promoter. Design: 6-hour instrumental sleep deprivation (TSD). Setting: Animal sleep research laboratory. Participants: Young (P23-P27) FVB/N-Tg (GFAP-GFP) 14Mes/J (Tg) mice of both sexes and 7-8 week male Tg and FVB/Nj mice. Interventions: Basal sleep recordings and sleep deprivation achieved using a modifed cage where animals were gently forced to move. Measurements and Results: Since Tg and FVB/Nj mice displayed a similar sleep-wake pattern, we performed a TSD in young Tg mice. Total RNA was extracted from the GFP-positive and GFP-negative cells sorted from cerebral cortex. Quantitative RT-PCR analysis showed that levels of Glut1, a-2-Na/K pump, Glt1, and Ldha mRNAs were signifcantly increased following TSD in GFP-positive cells. In GFP-negative cells, a tendency to increase, although not signifcant, was observed for Ldha, Mct2, and α-3-Na/K pump mRNAs. Conclusions: This study shows that TSD induces the expression of genes associated with ANLS specifcally in astrocytes, underlying the important role of astrocytes in the maintenance of the neuro-metabolic coupling across the sleep-wake cycle.

  13. A Theoretical and Experimental Research on Terahertz Electro-Optic Sampling at Near-Zero Optical Transmission Point

    Institute of Scientific and Technical Information of China (English)

    XU Shi-Xiang; CAI Hua

    2008-01-01

    We report an improved theoretical model to characterize terahertz electro-optic(EO)sampling detection operating at near crossed-polarizer design by considering the nonzero minimal transmission of polarizers and the polarization purlty of laser beam.The proof-of-concept experiments show that the model can give quiet reasonable explanations on many experimental phenomena in THz EO detection,e.g.the modulation depth vs the different optical biases,the noise level from the balance detector vs the input probe beam power,the main origin of the background light and the incomplete cancellation of noise from the laser intensity fluctuation in balanced detection.The terahertz signals and the noises are also measured based on two different EO sampling schemes for comparison.The measured results support our model very well.

  14. Large turbogenerators as high power supply for plasma physics research

    International Nuclear Information System (INIS)

    Many countries nowadays design and build research equipments for investigations on the field of plasma physics, requiring very high pulsed power supplies. Such supplies with DC-current output have not only to be powerful, but also quickly regulable. Peak capacities over 500 MW and energy amounts of some Gigajoule for a pulse duration of a few seconds cannot be delivered by a high voltage utility network, wihout untolerable voltage drops or marked current and voltage harmonics occuring. These negative influences can be greatly eliminated by using an intermediate energy storage. In this idea the utilization of a large turbogenerator - with or without suppplementary flywheel - represents an advantageous solution. In this paper the simulation of such power supplies is presented. On the base of three actual examples, the behaviour and the stresses of the generator, as well as its influence on the transient phenomena in the whole system are analyzed and explained. (orig.)

  15. DANBIO-powerful research database and electronic patient record

    DEFF Research Database (Denmark)

    Hetland, Merete Lund

    2011-01-01

    The nationwide DANBIO registry has been designed to capture operational clinical data as part of routine clinical care. At the same time, it provides a powerful research database. This article reviews the DANBIO registry with focus on problems and solutions of design, funding and linkage, provides...... an overview of the research outcome and presents the cohorts of RA patients. The registry, which is approved as a national quality registry, includes patients with RA, PsA and AS, who are followed longitudinally. Data are captured electronically from the source (patients and health personnel). The IT...... platform is based on open-source software. Via a unique personal identification code, linkage with various national registers is possible for research purposes. Since the year 2000, more than 10,000 patients have been included. The main focus of research has been on treatment efficacy and drug survival...

  16. Reflexively exploring knowledge and power in collaborative research

    DEFF Research Database (Denmark)

    Nordentoft, Helle Merete; Phillips, Louise Jane; Pedersen, Christina Hee;

    collaborative research stem from the methodological, epistemological and ethical problems and dilemmas that are inherent in collaborative knowledge production and communication and which relate to the inexorable workings of knowledge/power. The problems and dilemmas arise in the meeting between participants......The proposed workshop will take its starting point in the challenges which collaborative research practices share. The aim of the workshop is to work with, and further develop, a range of critical, reflexive strategies for understanding, analysing and dealing with those challenges. The workshop...... will be designed in order to stimulate dialogue across different analytical perspectives and empirical research. The analytical perspectives on which facilitation will be based are rooted in social constructionist approaches to dialogic communication theory and action research. The challenges of...

  17. Materials research in support of nuclear power generation

    International Nuclear Information System (INIS)

    This presentation outlines the activities of CANMET-MTL in materials research in support of nuclear power generation. CANMET-MTL is a Government of Canada research laboratory specializing in materials (metals and metal-based materials). Its mandate is to improve the competitive, social and environmental performance of Canadian industries in the area of metals. These include the economic benefits from value-added processing and manufacturing, materials for clean energy production and improved energy efficiency in processing and product end-use.

  18. University's role in research on superconducting power transmission

    International Nuclear Information System (INIS)

    Power transmission by superconducting cables appears to have enormous potential for the utility industry. It has still to be demonstrated that it will become a viable and economically competitive technology, however, development aimed at this goal by major research establishments has already exposed numerous research problems suitable for investigation by well qualified university departments without requiring large expenditures for equipment. What is missing in an organizational structure to relate work to the primary goals, monitor progress and influence the funding decisions of the major agencies. This does not seem difficult to set up, but continued success will require a long-term commitment from the participants

  19. How EPRI [Electric Power Research Institute] helps utilities save money

    International Nuclear Information System (INIS)

    A number of case studies are presented which illustrate how the work of the Electric Power Research Institute in the USA has enabled nuclear utilities to save money. The areas covered by the examples are: steam generator tube repair; streamlining of reliability centred maintenance; cost effective instrumentation and control maintenance; reducing the frequency of instrument calibration; optimising the engineering change process; detecting and reducing fuel failure; extending the qualified life of equipment. (U.K.)

  20. The power station society's new research and development initiative

    International Nuclear Information System (INIS)

    The society of power stations in Sweden has taken an initiative to promote research and development by its members which consist of privately owned generating stations. The areas of work are to be: technology, organisation, economy and finance, environment and relationship to society and man. The article deals with the economics, resources, aims and basis for cooperation and general administrative aspects. (J.H.H.)

  1. Human factors in nuclear power plants - object of ergonomics research

    International Nuclear Information System (INIS)

    In any high-automated plants a great number of disturbances can be attributed to human factor incidents. The higher the level of automation, the more important is human reliability to ensure reliability of the total system. This paper shows some possibilities for research in this field and their problems, especially in terms of nuclear power plant operation. The role of man-machine interface systems and human factors is mentioned and preventive measures to limit human factor incidents are proposed. (author)

  2. ZeroWaste

    DEFF Research Database (Denmark)

    Goltermann, Per; Ottosen, Lisbeth M.; Jensen, Pernille Erland;

    2014-01-01

    The ZeroWaste research group at the Department of Civil Engineering at the Technical University of Denmark (DTU Byg) was established two years ago and covers the broad range of expertise, required for turning waste materials into attractive, new materials. Members of the group have, prior to that......, developed methods for removal of heavy metals and phosphorous from waste incineration, sewage sludge and other bio ashes, providing the basis of to make these ash types an attractive, new material for the building sector. Initial results for upgrading and using different types of ashes are presented in the...

  3. Finnish research programmes on nuclear power plant safety

    International Nuclear Information System (INIS)

    The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

  4. Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Olson, Arne P. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. E. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanan, N. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-04-07

    The document compiles in a single volume several verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. Some works that are available in the open literature are simply referenced at the outset, and are not included in the document. PLTEMP has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a more validated code like the RELAP5 code.

  5. Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors

    International Nuclear Information System (INIS)

    The document compiles in a single volume several verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. Some works that are available in the open literature are simply referenced at the outset, and are not included in the document. PLTEMP has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a more validated code like the RELAP5 code.

  6. Improved Zero-Crossing Detector

    Science.gov (United States)

    Dick, G. John; Kuhnle, Paul F.

    1992-01-01

    Improved zero-crossing-detector circuit designed for precisely measuring difference between frequencies of two frequency-standard signal sources. Contains low-bandwidth first-stage amplifier and three limiting amplifiers, each "squares" signal bit more. Crosstalk eliminated and jitter reduced to about 10 to the negative 7th power microseconds.

  7. The effect of repeated measurements and working memory on the most comfortable level in the ANL test

    DEFF Research Database (Denmark)

    Brännström, K Jonas; Olsen, Steen Østergaard; Holm, Lucas;

    2014-01-01

    OBJECTIVE: To study the effect of a large number of repetitions on the most comfortable level (MCL) when doing the acceptable noise level (ANL) test, and explore if MCL variability is related to central cognitive processes. DESIGN: Twelve MCL repetitions were measured within the ANL test using in...

  8. ANL four-meter calorimeter design and operation manual

    International Nuclear Information System (INIS)

    The four-meter fuel rod calorimetric system measures the thermal power produced by radioactive decay of fuel rods containing Pu. The Pu mass is related to the measured power through the weighted average of the product of the isotopic decay energies and the decay constants of the Pu isotopes present. U content has no effect since the thermal power produced by the U nuclides is insignificant when compared to Pu. Radiations from Pu are alpha particles and low-energy photons. This calorimeter will measure samples producing power up to 1.5 watts at a rate of one sample every 120 min. The instrument consists of a data-acquisition module made up of a microprocessor, with an 8K-byte nonvolatile memory, a control cabinet and the calorimeter chamber

  9. ANL four-meter calorimeter design and operation manual

    Energy Technology Data Exchange (ETDEWEB)

    Perry, R.B.; Lewis, R.N.; Youngdahl, G.A.; Jung, E.A.; Roche, C.T.

    1980-02-01

    The four-meter fuel rod calorimetric system measures the thermal power produced by radioactive decay of fuel rods containing Pu. The Pu mass is related to the measured power through the weighted average of the product of the isotopic decay energies and the decay constants of the Pu isotopes present. U content has no effect since the thermal power produced by the U nuclides is insignificant when compared to Pu. Radiations from Pu are alpha particles and low-energy photons. This calorimeter will measure samples producing power up to 1.5 watts at a rate of one sample every 120 min. The instrument consists of a data-acquisition module made up of a microprocessor, with an 8K-byte nonvolatile memory, a control cabinet and the calorimeter chamber. (FS)

  10. Simulation research and optimal design for digital power regulating system of China advanced research reactor

    International Nuclear Information System (INIS)

    Based on SimPort simulation platform of nuclear power plant, a simulation model for Digital Power Regulating System (DPRS) of China Advanced Research Reactor (CARR) was established. By simulating the transient state of DPRS using this model, the adjusting parameters for the digital PID controller were determined. According to the features of the driving mechanism, the effects of the driving accuracy of the control rod and the displacement delay between electromagnetic coil and armature upon system stability and the regulating performance were analyzed, furthermore, their stability limit values were obtained respectively. The research results of this paper have some engineering practical value. (authors)

  11. Research and development into power reactor fuel performance

    International Nuclear Information System (INIS)

    The nuclear fuel in a power reactor must perform reliably during normal operation, and the consequences of abnormal events must be researched and assessed. The present highly reliable operation of the natural UO2 in the CANDU power reactors has reduced the need for further work in this area; however a core of expertise must be retained for purposes such as training of new staff, retaining the capability of reacting to unforeseen circumstances, and participating in the commercial development of new ideas. The assessment of fuel performance during accidents requires research into many aspects of materials, fuel and fission product behaviour, and the consolidation of that knowledge into computer codes used to evaluate the consequences of any particular accident. This work is growing in scope, much is known from out-reactor work at temperatures up to about 1500 degreesC, but the need for in-reactor verification and investigation of higher-temperature accidents has necessitated the construction of a major new in-reactor test loop and the initiation of the associated out-reactor support programs. Since many of the programs on normal and accident-related performance are generic in nature, they will be applicable to advanced fuel cycles. Work will therefore be gradually transferred from the present, committed power reactor system to support the next generation of thorium-based reactor cycles

  12. Research on reliability management systems for Nuclear Power Plant

    International Nuclear Information System (INIS)

    Investigation on a reliability management system for Nuclear Power Plants (NPPs) has been performed on national and international archived documents as well as on current status of studies at Idaho National Engineering and Environmental Laboratory (INEEL), US NPPs (McGuire, Seabrook), a French NPP (St. Laurent-des-Eaux), Japan Atomic Energy Research Institute (JAERI), Central Research Institute of Electric Power Industries (CRIEPI), and power plant manufacturers in Japan. As a result of the investigation, the following points were identified: (i) A reliability management system is composed of a maintenance management system to inclusively manage maintenance data, and an anomalies information and reliability data management system to extract data from maintenance results stored in the maintenance management system and construct a reliability database. (ii) The maintenance management system, which is widely-used among NPPs in the US and Europe, is an indispensable system for the increase of maintenance reliability. (iii) Maintenance management methods utilizing reliability data like Reliability Centered Maintenance are applied for NPP maintenance in the US and Europe, and contributing to cost saving. Maintenance templates are effective in the application process. In addition, the following points were proposed on the design of the system: (i) A detailed database on specifications of facilities and components is necessary for the effective use of the system. (ii) A demand database is indispensable for the application of the methods. (iii) Full-time database managers are important to maintain the quality of the reliability data. (author)

  13. Reduction zero-knowledge

    Institute of Scientific and Technical Information of China (English)

    ZHAO Yunlei; DENG Xiaotie; LEE C. H.; ZHU Hong

    2004-01-01

    The nature of zero-knowledge is re-examined and the evidence for the following belief is shown:the classic simulation based definitions of zero-knowledge(simulation zero-knowledge)may be somewhat too strong to include some "nice" protocols in which the malicious verifier seems to learn nothing but we do not know how to construct a zero-knowledge simulator for it.To overcome this problem a new relaxation of zero-knowledge,reduction zero-knowledge,is introduced.It is shown that reduction zero-knowledge just lies between simulation zero-knowledge and witness indistinguishability.Under the assumption of existence of one-way permutations a 4-round public-coin reduction zero-knowledge proof system for NP is presented and in practice this protocol works in 3 rounds since the first verifier's message can be fixed once and for all.

  14. Power plants 2020+. Power plant options for the future and the related demand for research

    International Nuclear Information System (INIS)

    This short overview already demonstrates that in the foreseeable future all generation options - nuclear power, fossil-fired power plants and renewable sources of energy - will continue to be applied. If, however, due to climate protection targets, energy conversion processes are to be to switched to CO2-free or -low carbon energy sources, comprehensive research endeavours will be required in order to advance existing technology options and to adjust them to changing conditions. This paper is bound to recommend individual fields of research from the viewpoint of the VGB Scientific Advisory Board for the period 2020 and beyond. Firstly, the generation structure in the European high-voltage grid and its development until 2020 will be considered, then the research demand for - Hard coal- and lignite-fired power plants, - Renewables-based electricity generation (wind, solar energy) and - Nuclear-based electricity generation will be outlined briefly, listing the main technology issues to be answered by researchers in order to increase efficiency and to settle any ''loose ends''. Apart from generation technologies, the options for storing electrical energy will also be dealt with. These options can contribute to make the feed-in of renewables-based electricity more permanent and sustainable. (orig.)

  15. Zero Energry Travel

    CERN Document Server

    Ahmad, Othman; Chekima, Ali

    2011-01-01

    It is fundamentally possible to travel with zero energy based on Newton Laws of Motion. According to the first law of motion, a body will continue to travel for infinite distance unless it is acted upon by another force. For a body in motion, the force which stops perpetual motion is friction. However, there are many circumstances that friction is zero, for example in space, where there is vacuum. On earth, gravity makes objects to be in constant contact with each other generating friction but technology exists to separate them in the air using powerful magnetic forces. At low speeds, the friction caused by air is minimal but we can create vacuum even on land for high speed travel. Another condition for travelling is for it to stop at its destination. On land, we can recover the kinetic energy back into electrical energy using brushless permanent magnet generators. These generators can also convert electric energy into kinetic energy in order to provide motion. This article reviews technologies that will allo...

  16. Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code

    Energy Technology Data Exchange (ETDEWEB)

    Boulaich, Y., E-mail: boulaich@cnesten.org.ma [CEN-Maamora, CNESTEN, Rabat (Morocco); Nacir, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); El Bardouni, T. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan (Morocco); CEN-Maamora, CNESTEN, Rabat (Morocco); Boukhal, H. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan (Morocco); Chakir, E. [LHESIR, Department of Physics, Faculty of Sciences, Kénitra (Morocco); El Bakkari, B.; El Younoussi, C. [CEN-Maamora, CNESTEN, Rabat (Morocco)

    2015-04-01

    Highlights: • PARET model for the Moroccan TRIGA MARK II reactor has been developed. • Transient behavior under reactivity insertion has been studied based on PARET code. • Power factors required by PARET code have been calculated by using MCNP5 code. • The dependence on time of the main thermal-hydraulic parameters was calculated. • Results are largely far to compromise the thermal design limits. - Abstract: A three dimensional model for the Moroccan 2 MW TRIGA MARK II reactor has been developed for thermal-hydraulic and safety analysis by using the PARET/ANL and MCNP5 codes. This reactor is located at the nuclear studies center of Mâamora (CENM), Morocco. The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM). The axial distributions of power factors required by the PARET code have been calculated in each fuel element rod by using MCNP5 code. Based on this thermal-hydraulic model, a safety analysis under the reactivity insertion phenomenon has been carried out and the dependence on time of the main thermal-hydraulic parameters was calculated. Results were compared to the thermal design limits imposed to maintain the integrity of the clad.

  17. Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code

    International Nuclear Information System (INIS)

    Highlights: • PARET model for the Moroccan TRIGA MARK II reactor has been developed. • Transient behavior under reactivity insertion has been studied based on PARET code. • Power factors required by PARET code have been calculated by using MCNP5 code. • The dependence on time of the main thermal-hydraulic parameters was calculated. • Results are largely far to compromise the thermal design limits. - Abstract: A three dimensional model for the Moroccan 2 MW TRIGA MARK II reactor has been developed for thermal-hydraulic and safety analysis by using the PARET/ANL and MCNP5 codes. This reactor is located at the nuclear studies center of Mâamora (CENM), Morocco. The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM). The axial distributions of power factors required by the PARET code have been calculated in each fuel element rod by using MCNP5 code. Based on this thermal-hydraulic model, a safety analysis under the reactivity insertion phenomenon has been carried out and the dependence on time of the main thermal-hydraulic parameters was calculated. Results were compared to the thermal design limits imposed to maintain the integrity of the clad

  18. A plan for administrative computing at ANL FY1991 through FY1993

    Energy Technology Data Exchange (ETDEWEB)

    Caruthers, L.E. (ed.); O' Brien, D.E.; Bretscher, M.E.; Hischier, R.C.; Moore, N.J.; Slade, R.G.

    1990-10-01

    In July of 1988, Argonne National Laboratory management approved the restructuring of Computing Services into the Computing and Telecommunications Division, part of the Physical Research area of the Laboratory. One major area of the Computing and Telecommunications Division is Management Information Systems (MIS). A significant aspect of Management Information Systems' work is the development of proposals for new and enhanced administrative computing systems based on an analysis of informational needs. This document represent the outcome of the planning process for FY1991 through FY1993. The introduction of the FY1991 through FY1993 Long-Range Plan assesses the state of administrative computing at ANL and the implications of FY1991 funding recommendations. It includes a history of MIS planning for administrative data processing. This document discusses the strategy and goals which are an important part of administrative data processing plans for the Laboratory. It also describes the management guidelines established by the Administrative Data Processing Oversight Committee for the proposal and implementation of administrative computing systems. Summaries of the proposals for new or enhanced administrative computing systems presented by individual divisions or departments with assistance of Management Information Systems, to the Administrative Data Processing Oversight Committee are given. The detailed tables in this paper give information on how much the resources to develop and implement a given systems will cost its users. The tables include development costs, computing/operations costs, software and hardware costs, and efforts costs. They include both systems funded by Laboratory General Expense and systems funded by the users themselves.

  19. Patient-powered research networks aim to improve patient care and health research.

    Science.gov (United States)

    Fleurence, Rachael L; Beal, Anne C; Sheridan, Susan E; Johnson, Lorraine B; Selby, Joe V

    2014-07-01

    The era of big data, loosely defined as the development and analysis of large or complex data sets, brings new opportunities to empower patients and their families to generate, collect, and use their health information for both clinical and research purposes. In 2013 the Patient-Centered Outcomes Research Institute launched a large national research network, PCORnet, that includes both clinical and patient-powered research networks. This article describes these networks, their potential uses, and the challenges they face. The networks are engaging patients, family members, and caregivers in four key ways: contributing data securely, with privacy protected; including diverse and representative groups of patients in research; prioritizing research questions, participating in research, and disseminating results; and participating in the leadership and governance of patient-powered research networks. If technical, regulatory, and organizational challenges can be overcome, PCORnet will allow research to be conducted more efficiently and cost-effectively and results to be disseminated quickly back to patients, clinicians, and delivery systems to improve patient health. PMID:25006148

  20. ANL small-sample calorimeter system design and operation

    Energy Technology Data Exchange (ETDEWEB)

    Roche, C.T.; Perry, R.B.; Lewis, R.N.; Jung, E.A.; Haumann, J.R.

    1978-07-01

    The Small-Sample Calorimetric System is a portable instrument designed to measure the thermal power produced by radioactive decay of plutonium-containing fuels. The small-sample calorimeter is capable of measuring samples producing power up to 32 milliwatts at a rate of one sample every 20 min. The instrument is contained in two packages: a data-acquisition module consisting of a microprocessor with an 8K-byte nonvolatile memory, and a measurement module consisting of the calorimeter and a sample preheater. The total weight of the system is 18 kg.

  1. SIRIUS 2: A versatile medium power research reactor

    International Nuclear Information System (INIS)

    Most of the Research Reactors in the world have been critical in the Sixties and operated for twenty to thirty years. Some of them have been completely shut down, modified, or simply refurbished; the total number of RR in operation has decreased but there is still an important need for medium power research reactors in order: - to sustain a power program with fuel and material testing for NPP or fusion reactors; - to produce radioisotopes for industrial or medical purposes, doped silicon, NAA or neutron radiography; - to investigate further the condensed matter, with cold neutrons routed through neutron guides to improved equipment; - to develop new technologies and applications such as medical alphatherapy. Hence, taking advantage of nearly hundred reactor x years operation and backed up by the CEA experience, TECHNICATOME assisted by FRAMATOME has designed a new versatile multipurpose Research Reactor (20-30 Mw) SIRIUS 2 taking into account: - more stringent safety rules; - the lifetime; - the flexibility enabling a wide range of experiments and, - the future dismantling of the facility according to the ALARA criteria

  2. Sample size and power analysis in medical research

    Directory of Open Access Journals (Sweden)

    Zodpey Sanjay

    2004-03-01

    Full Text Available Among the questions that a researcher should ask when planning a study is "How large a sample do I need?" If the sample size is too small, even a well conducted study may fail to answer its research question, may fail to detect important effects or associations, or may estimate those effects or associations too imprecisely. Similarly, if the sample size is too large, the study will be more difficult and costly, and may even lead to a loss in accuracy. Hence, optimum sample size is an essential component of any research. When the estimated sample size can not be included in a study, post-hoc power analysis should be carried out. Approaches for estimating sample size and performing power analysis depend primarily on the study design and the main outcome measure of the study. There are distinct approaches for calculating sample size for different study designs and different outcome measures. Additionally, there are also different procedures for calculating sample size for two approaches of drawing statistical inference from the study results, i.e. confidence interval approach and test of significance approach. This article describes some commonly used terms, which need to be specified for a formal sample size calculation. Examples for four procedures (use of formulae, readymade tables, nomograms, and computer software, which are conventionally used for calculating sample size, are also given

  3. Nuclear power and the public: an update of collected survey research on nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Rankin, W.L.; Melber, B.D.; Overcast, T.D.; Nealey, S.M.

    1981-12-01

    The purpose of this research was to collect, analyze, and summarize all of the nuclear power-related surveys conducted in the United States through June 1981, that we could obtain. The surveys collected were national, statewide, and areawide in scope. Slightly over 100 surveys were collected for an earlier, similar effort carried out in 1977. About 130 new surveys were added to the earlier survey data. Thus, about 230 surveys were screened for inclusion in this report. Because of space limitations, national surveys were used most frequently in this report, followed distantly by state surveys. In drawing our conclusions about public beliefs and attitudes toward nuclear power, we placed most of our confidence in survey questions that were used by national polling firms at several points in time. A summary of the research findings is presented, beginning with general attitudes toward nuclear power, followed by a summary of beliefs and attitudes about nuclear power issues, and ended by a summary of beliefs and attitudes regarding more general energy issues.

  4. Nuclear power and the public: an update of collected survey research on nuclear power

    International Nuclear Information System (INIS)

    The purpose of this research was to collect, analyze, and summarize all of the nuclear power-related surveys conducted in the United States through June 1981, that we could obtain. The surveys collected were national, statewide, and areawide in scope. Slightly over 100 surveys were collected for an earlier, similar effort carried out in 1977. About 130 new surveys were added to the earlier survey data. Thus, about 230 surveys were screened for inclusion in this report. Because of space limitations, national surveys were used most frequently in this report, followed distantly by state surveys. In drawing our conclusions about public beliefs and attitudes toward nuclear power, we placed most of our confidence in survey questions that were used by national polling firms at several points in time. A summary of the research findings is presented, beginning with general attitudes toward nuclear power, followed by a summary of beliefs and attitudes about nuclear power issues, and ended by a summary of beliefs and attitudes regarding more general energy issues

  5. Nuclear power plant control room operators' performance research

    International Nuclear Information System (INIS)

    A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator capabilities, of procedures and data for specifying and verifying simulator performance, and of methods and applications of task analysis

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. Background Radiation Measurements at High Power Research Reactors

    CERN Document Server

    Ashenfelter, J; Baldenegro, C X; Band, H R; Barclay, G; Bass, C D; Berish, D; Bowden, N S; Bryan, C D; Cherwinka, J J; Chu, R; Classen, T; Davee, D; Dean, D; Deichert, G; Dolinski, M J; Dolph, J; Dwyer, D A; Fan, S; Gaison, J K; Galindo-Uribarri, A; Gilje, K; Glenn, A; Green, M; Han, K; Hans, S; Heeger, K M; Heffron, B; Jaffe, D E; Kettell, S; Langford, T J; Littlejohn, B R; Martinez, D; McKeown, R D; Morrell, S; Mueller, P E; Mumm, H P; Napolitano, J; Norcini, D; Pushin, D; Romero, E; Rosero, R; Saldana, L; Seilhan, B S; Sharma, R; Stemen, N T; Surukuchi, P T; Thompson, S J; Varner, R L; Wang, W; Watson, S M; White, B; White, C; Wilhelmi, J; Williams, C; Wise, T; Yao, H; Yeh, M; Yen, Y -R; Zhang, C; Zhang, X

    2016-01-01

    Research reactors host a wide range of activities that make use of the intense neutron fluxes generated at these facilities. Recent interest in performing measurements with relatively low event rates, e.g. reactor antineutrino detection, at these facilities necessitates a detailed understanding of background radiation fields. Both reactor-correlated and naturally occurring background sources are potentially important, even at levels well below those of importance for typical activities. Here we describe a comprehensive series of background assessments at three high-power research reactors, including $\\gamma$-ray, neutron, and muon measurements. For each facility we describe the characteristics and identify the sources of the background fields encountered. The general understanding gained of background production mechanisms and their relationship to facility features will prove valuable for the planning of any sensitive measurement conducted therein.

  8. Background radiation measurements at high power research reactors

    Science.gov (United States)

    Ashenfelter, J.; Balantekin, B.; Baldenegro, C. X.; Band, H. R.; Barclay, G.; Bass, C. D.; Berish, D.; Bowden, N. S.; Bryan, C. D.; Cherwinka, J. J.; Chu, R.; Classen, T.; Davee, D.; Dean, D.; Deichert, G.; Dolinski, M. J.; Dolph, J.; Dwyer, D. A.; Fan, S.; Gaison, J. K.; Galindo-Uribarri, A.; Gilje, K.; Glenn, A.; Green, M.; Han, K.; Hans, S.; Heeger, K. M.; Heffron, B.; Jaffe, D. E.; Kettell, S.; Langford, T. J.; Littlejohn, B. R.; Martinez, D.; McKeown, R. D.; Morrell, S.; Mueller, P. E.; Mumm, H. P.; Napolitano, J.; Norcini, D.; Pushin, D.; Romero, E.; Rosero, R.; Saldana, L.; Seilhan, B. S.; Sharma, R.; Stemen, N. T.; Surukuchi, P. T.; Thompson, S. J.; Varner, R. L.; Wang, W.; Watson, S. M.; White, B.; White, C.; Wilhelmi, J.; Williams, C.; Wise, T.; Yao, H.; Yeh, M.; Yen, Y.-R.; Zhang, C.; Zhang, X.

    2016-01-01

    Research reactors host a wide range of activities that make use of the intense neutron fluxes generated at these facilities. Recent interest in performing measurements with relatively low event rates, e.g. reactor antineutrino detection, at these facilities necessitates a detailed understanding of background radiation fields. Both reactor-correlated and naturally occurring background sources are potentially important, even at levels well below those of importance for typical activities. Here we describe a comprehensive series of background assessments at three high-power research reactors, including γ-ray, neutron, and muon measurements. For each facility we describe the characteristics and identify the sources of the background fields encountered. The general understanding gained of background production mechanisms and their relationship to facility features will prove valuable for the planning of any sensitive measurement conducted therein.

  9. Overview of Multi-Kilowatt Free-Piston Stirling Power Conversion Research at Glenn Research Center

    Science.gov (United States)

    Geng, Steven M.; Mason, Lee S.; Dyson, Rodger W.; Penswick, L. Barry

    2008-01-01

    As a step towards development of Stirling power conversion for potential use in Fission Surface Power (FSP) systems, a pair of commercially available 1 kW class free-piston Stirling convertors and a pair of commercially available pressure wave generators (which will be plumbed together to create a high power Stirling linear alternator test rig) have been procured for in-house testing at Glenn Research Center (GRC). Delivery of both the Stirling convertors and the linear alternator test rig is expected by October 2007. The 1 kW class free-piston Stirling convertors will be tested at GRC to map and verify performance. The convertors will later be modified to operate with a NaK liquid metal pumped loop for thermal energy input. The high power linear alternator test rig will be used to map and verify high power Stirling linear alternator performance and to develop power management and distribution (PMAD) methods and techniques. This paper provides an overview of the multi-kilowatt free-piston Stirling power conversion work being performed at GRC.

  10. Beyond Zero Based Budgeting.

    Science.gov (United States)

    Ogden, Daniel M., Jr.

    1978-01-01

    Suggests that the most practical budgeting system for most managers is a formalized combination of incremental and zero-based analysis because little can be learned about most programs from an annual zero-based budget. (Author/IRT)

  11. An intrinsically safe facility for forefront research and training on nuclear technologies — A zero-power experiment

    Science.gov (United States)

    Alloni, D.; Borio di Tigliole, A.; Cagnazzo, M.; Magrotti, G.; Manera, S.; Panza, F.; Prata, M.; Salvini, A.; Cammi, A.; Chiesa, D.; Clemenza, M.; Previtali, E.; Sisti, M.

    2014-04-01

    The study of subcritical reactors needs some test to correctly evaluate many parameters that must be introduced in a reactor model. The Sub-critical Multiplication installation at the University of Pavia was used to measure neutron fluxes and multiplication factors that will be modelled with a MCNP Monte Carlo numerical simulation. The comparison between the measurements and the simulations were very promising demonstrating that also in a sub-critical system the Monte Carlo model could be very helpful in describing the reactor characteristics. Using all the collected data from measurements and simulations, it was possible to determine the k eff of the reactor plant with a reasonable accuracy. The ratio between the fast and the thermal component of the neutron fluxes was also determined.

  12. A Goal of Zero

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    As the picture of HIV/AIDS in China becomes more complex, more efforts are needed The theme of World AIDS Day this year is "Getting to Zero," which means zero new HIV infections, zero discrimination and zero AIDS-related deaths.Realizing these goals, however, is an extremely difficult challenge. Three decades after the first case of HIV was reported in the world in 1981, poor awareness and inadequate medical responses have allowed the virus to continue to spread worldwide.

  13. Utilization experience with research reactors of various power levels

    International Nuclear Information System (INIS)

    Utilization of research reactor, PARR-1 at the power level of 5 MW, and then at 9 MW, after the up gradation and conversion from highly enriched uranium (HEU) to low enriched uranium (LEU), has been described. In addition, the type of work carried out around a smaller facility, PARR-2, with power rating of 27kW has also been discussed. Utilization of PARR-1 in the area of neutron diffraction, neutron capture studies, radioisotope production, neutron activation analysis, reactor physics, and in reactor controls etc has been illustrated. The benefits derived from the up gradation of the power for neutron diffraction studies, radioisotope production and neutron radiography have been discussed. The problem, which can be handed successfully on PARR-2, include neutron activation analysis, production of short-lived radioisotopes, and experimentation in reactor engineering and physics for training purposes. Suitable methodologies have been developed for the analysis of samples of varied nature using neutron activation technique, and the experience gained has been applied to the analysis of geological, environmental and biological samples and high purity materials. (author)

  14. Radio-Tracking Studies of Adult Chinook Salmon and Steelhead to Determine the Effect of ''Zero'' River Flow During Water Storage at Little Goose Dam on the Lower Snake River, Final Report of Research.

    Energy Technology Data Exchange (ETDEWEB)

    Liscom, Kenneth

    1985-09-01

    Allowable instantaneous minimum river flows are established in the Columbia and Snake Rivers to ensure safe passage of anadromous fish during their migration to the spawning grounds. However, water storage during periods of low power demands (at night and on weekends) would be beneficial to the power producers. This storage procedure is called ''zero'' river flow and is now permitted on a limited basis when there are few if any actively migrating anadromous fish present in the river system. Requests were made to extend ''zero'' river flow into periods when anadromous fish were actively migrating and a study was initiated. Radio-tracking studies were conducted on the Snake River between Lower Monumental and Little Goose Dams to determine the effect of ''zero'' river flow on the migration of adult chinook salmon, Oncorhynchus tshawytscha, and steelhead, Salmo gairdneri. From July through September, 1981, a total of 258 steelhead and 32 chinook salmon were radio-tagged. The rate of migration was used to determine differences between test and control fish and a gamma distribution model was used to describe the migration rate for radio-tagged fish. Estimates of the parameters of the model were used to statistically compare ''zero'' flow and normal river flow conditions for the radio-tagged fish. The results show that the ''zero'' flow condition delays the migration of adult chinook salmon and steelhead; therefore, extended periods of ''zero'' flow to store water are not recommended when fish are actively migrating in the river system. 16 refs., 5 figs., 9 tabs.

  15. Helium research in support of superconducting power transmission

    Energy Technology Data Exchange (ETDEWEB)

    Jones, M. C. [ed.

    1979-04-01

    During FY 77, research for Superconducting Power Transmission Line (SPTL) development included the following four research tasks: preparation of computer codes for the computation of cooldown by either single stream or counterstream methods; experimental verification of cooldown computations with emphasis on counterstream cooling; thermal cycling of a length of lead-sheathed model cable destined for testing in the BNL 5th Avenue facility; and evaluation of heat flow sensors as a means of non-intrusive vacuum indication for power transmission line vacuum envelopes. A series of progress reports on these four tasks are presented, with 6 appendicies on: experimental observations of flow oscillations in a high aspect ratio heated tube with supercritical helium as coolant; the results of a study of friction factors measured in the same apparatus as was used in Appendix 1; results of a numerical study of the response of SPTL current leads to overload currents; the microwave cavity pressure transducer developed at NBS for SPTL application; a correlation of heat transfer data to supercritical helium in forced convection; and a pressure regulator designed and used in controlling the pressure of cryogenic helium at supercritical pressures.

  16. Electric Power Research Institute: Environmental Control Technology Center

    International Nuclear Information System (INIS)

    Operations and maintenance continued this month at the Electric Power Research Institute's (EPRI's) Environmental Control Technology Center (ECTC). Testing for the month involved the Dry Sorbent Injection (DST) test block with the Carbon Injection System. The 1.0 MW Cold-Side Selective Catalytic Reduction (SCR) unit, the 0.4 MW Mini-Pilot Wet Scrubber, and the 4.0 MW Pilot Wet Scrubber remained idle this month in a cold-standby mode and were inspected regularly. These units remain available for testing as future project work is identified. The 1990 Clean Air Act Amendments have required that the Environmental Protection Agency (EPA) assess the health risks and environmental effects associated with air toxic emissions (primarily mercury) from fossil-fuel fired utility boilers. EPRI has sponsored research on environmental mercury since 1983 to determine the factors that may influence human health, and to determine the role of electric power generating stations in contributing to those factors. Over the last four years, EPRI's Environmental Control Technology Center (ECTC) has conducted EPRI and DOE sponsored testing to develop and demonstrate appropriate measurement methods and control technologies for power plant atmospheric mercury emissions. Building upon the experience and expertise of the EPRI ECTC, a test program was initiated at the Center in July to further evaluate dry sorbent-based injection technologies upstream of a cold-side ESP for mercury control, and to determine the effects of such sorbents on ESP performance. The results from this program will be compared to the results from previous DOE/EPRI demonstrations, and to other ongoing programs. The primary objectives of this test program are to: (1) Determine the levels of mercury removal achievable by dry sorbent injection upstream of an electrostatic precipitator (ESP). The process parameters to be investigated include sorbent residence time, sorbent type, sorbent size, sorbent loading, and flue gas

  17. Nuclear power plant thermal-hydraulic performance research program plan

    International Nuclear Information System (INIS)

    The purpose of this program plan is to present a more detailed description of the thermal-hydraulic research program than that provided in the NRC Five-Year Plan so that the research plan and objectives can be better understood and evaluated by the offices concerned. The plan is prepared by the Office of Nuclear Regulatory Research (RES) with input from the Office of Nuclear Reactor Regulation (NRR) and updated periodically. The plan covers the research sponsored by the Reactor and Plant Systems Branch and defines the major issues (related to thermal-hydraulic behavior in nuclear power plants) the NRC is seeking to resolve and provides plans for their resolution; relates the proposed research to these issues; defines the products needed to resolve these issues; provides a context that shows both the historical perspective and the relationship of individual projects to the overall objectives; and defines major interfaces with other disciplines (e.g., structural, risk, human factors, accident management, severe accident) needed for total resolution of some issues. This plan addresses the types of thermal-hydraulic transients that are normally considered in the regulatory process of licensing the current generation of light water reactors. This process is influenced by the regulatory requirements imposed by NRC and the consequent need for technical information that is supplied by RES through its contractors. Thus, most contractor programmatic work is administered by RES. Regulatory requirements involve the normal review of industry analyses of design basis accidents, as well as the understanding of abnormal occurrences in operating reactors. Since such transients often involve complex thermal-hydraulic interactions, a well-planned thermal-hydraulic research plan is needed

  18. International power supply policy and the globalisation of research: the example of fusion research

    International Nuclear Information System (INIS)

    At the present state of our information, we can affirm that fusion research, as far as the necessary financial expenditures and their political justification are concerned, is a matter of politically controversial debate. In the political arenas, projects like controlled nuclear fusion are discussed primarily with regard to the controllability of complex technical systems and the sustainability of our future supply of electric power. The attempt to discuss this problem will have to consider: (i) on the one hand, already established concepts of sustainability; (ii) and on the other, the - according to the present state of our knowledge - foreseeable characteristics of a system of power generation and supply based on fusion reactors. Not only do the goals of global technology projects have to be embedded in patterns of universally accepted legitimisation (sustainability), but the organisation of research and development is also changing into networks acting globally. In this sense, globalisation means not only the worldwide linking of financial markets and the permanent availability of information and communication networks, but above all the creation of global organisations of research and innovation processes. The globalisation of research and development of technology has several dimensions: (i) the recognition and treatment of global problems; (ii) the transformation and evolution of new forms of organisation and cooperation in a global community of researchers; (iii) the constitution of Global Change Research. Fusion is playing a 'pathfinder role' for these processes and is at the same time itself an expression of the globalisation of the production of technology

  19. Graphs and Zero-Divisors

    Science.gov (United States)

    Axtell, M.; Stickles, J.

    2010-01-01

    The last ten years have seen an explosion of research in the zero-divisor graphs of commutative rings--by professional mathematicians "and" undergraduates. The objective is to find algebraic information within the geometry of these graphs. This topic is approachable by anyone with one or two semesters of abstract algebra. This article gives the…

  20. The research strategy of the Swedish Nuclear Power Inspectorate

    International Nuclear Information System (INIS)

    In its directive to the Swedish Nuclear Power Inspectorate for 2001 and 2002, the Government asked for a report on SKI's future research strategy. This report is meant to describe future needs for SKI's regulatory and supervisory work, the need for expertise in Sweden and the possibility of international co-operation. SKI's research currently focuses on a number of strategically important areas such as reactor technology, materials and fuel issues, human factors, nuclear waste and nuclear safeguards. Over the past decade, the nuclear infrastructure has changed considerably. The nuclear power companies' previous organisations with specialist expertise and resources have been successively closed down or converted into consulting companies. Furthermore, education and research in the nuclear area at universities have been considerably reduced and expertise, resources and interest in the area have thereby decreased. A review of the availability of expertise in Sweden shows that, in many areas, resources are adequate, but that SKI, in certain cases, needs to provide focused support in order to maintain the expertise that SKI needs for its regulatory and supervisory activities. The analysis highlights two areas without any real education and research: 'Materials testing and control' and 'Management, control and organisation'. Education and research in the latter area lacks a safety perspective. SKI intends to take the initiative to conduct work within both of these areas. Since national research resources are limited, SKI has, for a long time, actively participated in international research. SKI is prioritising co-operation on research conducted in the OECD/NEA and is participating in a large number of projects organised within this framework. Since Sweden joined the EU, the importance of joint European work has increased. SKI is itself also actively participating and supporting Swedish organisations participating in European Commission projects and intends to support

  1. Theoretical Research of Coal Gasification Products Burning in Boilers at Tomsk Thermal Power Plant-3

    Directory of Open Access Journals (Sweden)

    Somov A.A.

    2015-01-01

    Full Text Available Mathematical modeling of primary fuel change into power gas in power generating boiler with productivity of steam 160 t\\h was done. Research of aggregate work on some power modes was completed. Characteristic curves of efficiency coefficient at different loads and ratio on power and natural gases burning were made. Practicability of power gas use as fuel was proved.

  2. Theoretical Research of Coal Gasification Products Burning in Boilers at Tomsk Thermal Power Plant-3

    OpenAIRE

    Somov A.A.; Mel'nikov D.A.; Gvozdjakov D.V.; Gubin V.E.; Borovikov Yu.S.; Matveev A.S.

    2015-01-01

    Mathematical modeling of primary fuel change into power gas in power generating boiler with productivity of steam 160 t\\h was done. Research of aggregate work on some power modes was completed. Characteristic curves of efficiency coefficient at different loads and ratio on power and natural gases burning were made. Practicability of power gas use as fuel was proved.

  3. Research and application of pulsed-power technology

    International Nuclear Information System (INIS)

    Pulsed-power technology relating to that branch which was stimulated by military applications in the 1960's is addressed. A history of the development and characteristics of some devices producing intense electron and ion beams which resulted in Sandia's particle beam fusion program is presented. These include Hermes II, Aurora, Hydra, and Proto II. Research on inertial confinement fusion ignition is described, and the most critical issue in ICF today still is the demonstration of ignition and efficient burnup of a small amount of thermonuclear fuel. Progress on the Sandia particle beam fusion accelerator (PBFA I and II) is reported, but already plans are underway to further upgrade the device and if these modifications are carried out in 1983, fusion ignition concepts may be tested by 1985. Fusion could possibly provide an inexhaustible supply of energy in the next century

  4. Proceedings of the first energy research power supercomputer users symposium

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    The Energy Research Power Supercomputer Users Symposium was arranged to showcase the richness of science that has been pursued and accomplished in this program through the use of supercomputers and now high performance parallel computers over the last year: this report is the collection of the presentations given at the Symposium. Power users'' were invited by the ER Supercomputer Access Committee to show that the use of these computational tools and the associated data communications network, ESNet, go beyond merely speeding up computations. Today the work often directly contributes to the advancement of the conceptual developments in their fields and the computational and network resources form the very infrastructure of today's science. The Symposium also provided an opportunity, which is rare in this day of network access to computing resources, for the invited users to compare and discuss their techniques and approaches with those used in other ER disciplines. The significance of new parallel architectures was highlighted by the interesting evening talk given by Dr. Stephen Orszag of Princeton University.

  5. Pyrolysis of MSW: the current ANL/DOE program

    Energy Technology Data Exchange (ETDEWEB)

    Helt, J.E.; Henry, R.F.; Young, J.E.

    1984-01-01

    Pyrolysis of MSW is a promising method of producing useful fuels. However, several large-scale pyrolysis plants have not performed as expected, producing low yields of inferior products. Reasons for these shortcomings include a lack of understanding of the fundamental mechanisms and kinetics. Current DOE-sponsored research is directed at improved understanding of the basic thermokinetic mechanisms associated with pyrolytic converison of MSW. This work is directed not only at conventional pyrolysis, but also at the potential for product upgrading and advanced liquefaction concepts.

  6. Status of human factors research programs in Central Research Institute of Electric Power Industry, (2)

    International Nuclear Information System (INIS)

    In July, 1987, the Central Research Institute of Electric Power Industry founded the Human Factor Research Center, and it has promoted the research placing emphasis on practical use. In this report, among these subjects, J-HPES which has been developed since 1986 is described. The Japanese version of human performance enhancement system (J-HPES) is the Japanese version of HPES that the Institute of Nuclear Power Operations in USA has developed. It is a series of systems which, on the trouble occurred as human deed took part or became the origin, which are related to the operation and maintenance of nuclear power stations, analyzes and evaluates exactly the whole facts and the cause of the occurrence of such deed, and proposes the effective and concrete countermeasures for preventing troubles. It is shown in the easily usable form of procedure. The basic policy and the targets of the time of developing the Japanese version are shown. The course of development, the whole constitution and the features, and the contents of J-HPES are described. (K.I.)

  7. The ANL X6B beamline at NSLS: A versatile facility

    International Nuclear Information System (INIS)

    We have described the x-ray optics and beamline performance of the ANL X6B beam line at the NSLS. Considerable flexibility has been built into the beam line to accommodate a wide range of x-ray diffraction, scattering, and spectroscopy experiments with various requirements. We presented selected examples of experimental results and showed that with the high intensity, high energy resolution, high-q resolution, and energy tunability, the X6B beam line has become a versatile facility

  8. Light-quark baryon spectroscopy within ANL-Osaka dynamical coupled-channels approach

    CERN Document Server

    Kamano, Hiroyuki

    2016-01-01

    Recent results on the study of light-quark baryons with the ANL-Osaka dynamical coupled-channels (DCC) approach are presented, which contain the N* and Delta* spectroscopy via the analysis of pi N and gamma N reactions and the Lambda* and Sigma* spectroscopy via the analysis of K- p reactions. A recent application of our DCC approach to neutrino-nucleon reactions in the resonance region is also presented.

  9. Superconducting magnet systems for the ANL EPR design

    International Nuclear Information System (INIS)

    The magnet systems for the current Argonne experimental power reactor (EPR) design build on the earlier designs but incorporate a number of improvements. The toroidal field (TF) coil system consists of 16 coils of the constant tension shape, with NbTi, copper, and stainless steel as superconductor, stabilizer, and support material respectively. They are designed for 10 T operation at 3.7 K or 9 T operation at 4.2 K. Two changes from earlier designs permit a saving in material requirements. The coils are wound with the conductor in precompression and the support material in pretension so that when the coils are energized, the stainless steel experiences a stress of 60,000 psi while the copper stress does not exceed 15,000 psi. Both the copper and NbTi are graded, with higher current densities where magnetic and radiation effects are smaller. The ohmic heating (OH) coil system consists of a central solenoid plus ten other coils, all located outside the TF coils for ease of maintenance. The NbTi-copper coils are cryostable and operate at 4.2 K. The solenoid is segmented, with rings of insulation between segments to transfer the centering force from the TF coils to an insulating cylinder inside the OH solenoid. Locating the OH solenoid inside the support cylinder plus raising the central field to 8 T, enables the OH system to develop more volt-seconds than the earlier designs, even though the plasma major radius is smaller. The superconducting equilibrium field coils, also outside the TF coils, provide the field pattern required for a D-shaped plasma

  10. ANL site response for the DOE FY1994 information resources management long-range plan

    Energy Technology Data Exchange (ETDEWEB)

    Boxberger, L.M.

    1992-03-01

    Argonne National Laboratory's ANL Site Response for the DOE FY1994 Information Resources Management (IRM) Long-Range Plan (ANL/TM 500) is one of many contributions to the DOE information resources management long-range planning process and, as such, is an integral part of the DOE policy and program planning system. The Laboratory has constructed this response according to instructions in a Call issued in September 1991 by the DOE Office of IRM Policy, Plans and Oversight. As one of a continuing series, this Site Response is an update and extension of the Laboratory's previous submissions. The response contains both narrative and tabular material. It covers an eight-year period consisting of the base year (FY1991), the current year (FY1992), the budget year (FY1993), the plan year (FY1994), and the out years (FY1995-FY1998). This Site Response was compiled by Argonne National Laboratory's Computing and Telecommunications Division (CTD), which has the responsibility to provide leadership in optimizing computing and information services and disseminating computer-related technologies throughout the Laboratory. The Site Response consists of 5 parts: (1) a site overview, describes the ANL mission, overall organization structure, the strategic approach to meet information resource needs, the planning process, major issues and points of contact. (2) a software plan for DOE contractors, Part 2B, Software Plan FMS plan for DOE organizations, (3) computing resources telecommunications, (4) telecommunications, (5) printing and publishing.

  11. ANL site response for the DOE FY1994 information resources management long-range plan

    Energy Technology Data Exchange (ETDEWEB)

    Boxberger, L.M.

    1992-03-01

    Argonne National Laboratory`s ANL Site Response for the DOE FY1994 Information Resources Management (IRM) Long-Range Plan (ANL/TM 500) is one of many contributions to the DOE information resources management long-range planning process and, as such, is an integral part of the DOE policy and program planning system. The Laboratory has constructed this response according to instructions in a Call issued in September 1991 by the DOE Office of IRM Policy, Plans and Oversight. As one of a continuing series, this Site Response is an update and extension of the Laboratory`s previous submissions. The response contains both narrative and tabular material. It covers an eight-year period consisting of the base year (FY1991), the current year (FY1992), the budget year (FY1993), the plan year (FY1994), and the out years (FY1995-FY1998). This Site Response was compiled by Argonne National Laboratory`s Computing and Telecommunications Division (CTD), which has the responsibility to provide leadership in optimizing computing and information services and disseminating computer-related technologies throughout the Laboratory. The Site Response consists of 5 parts: (1) a site overview, describes the ANL mission, overall organization structure, the strategic approach to meet information resource needs, the planning process, major issues and points of contact. (2) a software plan for DOE contractors, Part 2B, ``Software Plan FMS plan for DOE organizations, (3) computing resources telecommunications, (4) telecommunications, (5) printing and publishing.

  12. Evaluating and Reporting Statistical Power in Counseling Research

    Science.gov (United States)

    Balkin, Richard S.; Sheperis, Carl J.

    2011-01-01

    Despite recommendations from the "Publication Manual of the American Psychological Association" (6th ed.) to include information on statistical power when publishing quantitative results, authors seldom include analysis or discussion of statistical power. The rationale for discussing statistical power is addressed, approaches to using "G*Power" to…

  13. Electric Power Research Institute turbine disk inspection program

    International Nuclear Information System (INIS)

    Beginning with the recognition that domestically manufactured low-pressure nuclear turbine disks could experience the same type of stress corrosion cracking that had precipitated the Hinkley Point turbine disk burst in 1969, the Electric Power Research Institute (EPRI) has funded a vast amount of related research. These projects have involved a full range of pertinent topics, including material characterization, crack mechanisms, design considerations, contributing steam conditions and chemistry, steam monitoring, potential consequences, and nondestructive evaluation (NDE). Most recently, EPRI has initiated a project to develop a state-of-the-art ultrasonic scan manipulator. This device will not only provide enhanced manipulation capabilities to support current ultrasonic examination techniques, but it will also support current ultrasonic examination techniques, but it will also support advanced detection and sizing techniques such as time-of-flight-diffraction and focused immersion testing. The system, which is now in its final design stages, will undergo extensive testing at the EPRI NDE Center when it is completed. In addition, the scanner will be married to available ultrasonic data acquisition systems to evaluate advanced ultrasonic detection and sizing techniques. The scanner and related future activities are described

  14. The Application of Paret/ANL Code for Accident Analysis on Inadvertent Control Rod Withdrawal for RSG GAS Reactor

    International Nuclear Information System (INIS)

    The analysis is intended to take a look the condition of safety parameters such as fuel and clad temperature, and minimum safety margin against flow instability (S) in the occurrence of inadvertent control rod withdrawal at nominal power, which is performed by PARET/ANL Code. The accident is initiated when all control rods are simultaneously withdrawn with maximum speed of 0.0564 cm/s which consequently gives maximum reactivity insertion rate σρ/σt = 2.82 x 10-4/s, resulting in the Reactor Protection System (RPS) respond to scram the reactor by dropping the control rods into the core. The primary cooling system is assumed to be in normal operation. It is postulated that the first trip signal from over power is not effective to scram the reactor, but only the second signal from Floating Limit Value eventually causes a scram with 0.5 s delays. During the occurrence of inadvertent control rods withdrawal at 30 MW of initial power, the maximum fuel and clad temperature reach 181.29oC and 137.62oC, respectively and the peak power of 37.11 MW. Meanwhile the minimum value of S reaches 2.62. Therefore, during the occurrence of control rods withdrawal at initial power of 30 MW, the integrity of fuel and clad can be maintained secure since they do not exceed the maximum limit of fuel and clad temperature of 207oC and 145oC, respectively and the minimum value of S is still higher than the design limit of 1.48 for anticipated transient

  15. High Performance Zero-Bleed CLSM/Grout Mixes for High-Level Waste Tank Closures Strategic Research and Development - FY99 Report

    International Nuclear Information System (INIS)

    The overall objective of this program, SRD-99-08, was to design and test suitable materials, which can be used to close high-level waste tanks at SRS. Fill materials can be designed to perform several functions including chemical stabilization and/or physical encapsulation of incidental waste so that the potential for transport of contaminants into the environment is reduced. Also they are needed to physically stabilize the void volume in the tanks to prevent/minimize future subsidence and inadvertent intrusion. The intent of this work was to develop a zero-bleed soil CLSM (ZBS-CLSM) and a zero-bleed concrete mix (ZBC) which meet the unique placement and stabilization/encapsulation requirements for high-level waste tank closures. These mixes in addition to the zero-bleed CLSM mixes formulated for closure of Tanks 17-F and 20-F provide design engineers with a suite of options for specifying materials for future tank closures

  16. High Performance Zero-Bleed CLSM/Grout Mixes for High-Level Waste Tank Closures Strategic Research and Development - FY99 Report

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.A.

    2000-08-11

    The overall objective of this program, SRD-99-08, was to design and test suitable materials, which can be used to close high-level waste tanks at SRS. Fill materials can be designed to perform several functions including chemical stabilization and/or physical encapsulation of incidental waste so that the potential for transport of contaminants into the environment is reduced. Also they are needed to physically stabilize the void volume in the tanks to prevent/minimize future subsidence and inadvertent intrusion. The intent of this work was to develop a zero-bleed soil CLSM (ZBS-CLSM) and a zero-bleed concrete mix (ZBC) which meet the unique placement and stabilization/encapsulation requirements for high-level waste tank closures. These mixes in addition to the zero-bleed CLSM mixes formulated for closure of Tanks 17-F and 20-F provide design engineers with a suite of options for specifying materials for future tank closures.

  17. Research on Comparisons of New Clean Power Generation Technologies

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    On the basis of introducing clean power generation technologies, the author calculated and analyzed the investment, economy and environmental protection of these technologies, posed his views of giving the priorities to the development of supercritical and ultra-supercritical pressure coal-fired power generation technologies and taking vigorous action to nuclear power generation technology within the following 5-10 years, exploiting wind power within the following 10-15 years, and suggested that the installed capacity of nuclear power reach 80-100 GW and that of wind power reach 50-80 GW by 2020.

  18. Simulation research and optimal design for digital power regulating system of China advanced research reactor

    International Nuclear Information System (INIS)

    Based on SimPort simulation platform of nuclear power plant, a simulation model for Digital Power Regulating System (DPRS) of China Advanced Research Reactor (CARR) was established. The transient state of DPRS was simulation studied using this model. According to the characteristics of the driving mechanism of the control rods, the effects of the driving precision of the control rod and its displacement delay upon the system stability were analyzed. Considering the process requirements of CARR and the function characteristic of DRPS, the adjusting parameters for the digital PID controller and the stability limits of the driving mechanism of the control rods were obtained. The sampling period of the digital PID controller is 100 ms and its proportion gain is 300. The stability limit of the driving precision of the control rod is 0.4 mm. The stability limit of displacement delay between electromagnetic coil and armature is 6.0 mm. (authors)

  19. Research on the security of nuclear power equipment

    International Nuclear Information System (INIS)

    Recently, the rapidly growing economy in conflict with the lack of power in the whole country become more and more seriously in our country. In other hand, there is also various kind of problems such as greenhouse effect and the oil price rising conditions. It greatly promote our country's development of Nuclear power project. As forecast, the number of Nuclear Power Plant will increase greatly in the future. However, the security of the Nuclear Power Plant is one of the topics that people always pay more attention to. Combining with the practice experience of Nuclear Power Plant in Japanese, the security of Nuclear Power Plant in multi-angles is discussed. It is pointed that the risk assesment and management system of nuclear power plant are effective measure for security of the development of nuclear power. (authors)

  20. Feasibility Research of Nuclear-power System for Car

    Institute of Scientific and Technical Information of China (English)

    WU; Xiao-chun; SUN; Zheng; LIU; Xin-ming; LI; Long; XU; Zhi-long; SHAO; Jing

    2013-01-01

    The idea of making nuclear-powered car can dated back to 1950s,and Ford company developed the first nuclear-powered car Nucleon which theoretically based on uranium-235 fission powered engine.Recently,General Motors released its Cadillac"World Thorium Fuel Concept"car at 2009 Chicago Auto Show,which didn’t include a working thorium-powered engine.But it’s claimed that the thorium laser

  1. Power Excursion Accident Analysis of Research Water Reactor

    International Nuclear Information System (INIS)

    A three-dimensional neutronic code POWEX-K has been developed, and it has been coupled with the sub-channel thermal-hydraulic core analysis code SV based on the Single Mass Velocity Model. This forms the integrated neutronic/thermal hydraulics code system POWEX-K/SV for the accident analysis. The Training and Research Reactors at Budapest University of Technology and Economics (BME-Reactor) has been taken as a reference reactor. The cross-section generation procedure based on WIMS. The code uses an implicit difference approach for both the diffusion equations and thermal-hydraulics modules, with reactivity feedback effects due to coolant and fuel temperatures. The code system was applied to analyzing power excursion accidents initiated by ramp reactivity insertion of 1.2 $. The results show that the reactor is inherently safe in case of such accidents i.e. no core melt is expected even if the safety rods do not fall into the core

  2. CEA's research programmes on future nuclear power systems

    International Nuclear Information System (INIS)

    The CEA (Commissariat a l'energie atomique et aux energies alternatives) is at the crossroads between sciences and technologies. In collaboration with corporate leaders and academics, it is working to improve the competitiveness of the existing fleet of nuclear facilities (PWR reactors and EPR) and to develop both a fourth generation of nuclear power reactors and technologies for processing spent fuel. Concerning the PWR reactors most of the work focuses on the extension of reactor operating life (till 60 years), a better use of uranium fuel in the reactor core, a better safety standard, a better reliability of fuel assemblies. This work is both theoretical and experimental with the possibility to use irradiation rigs at the OSIRIS reactor. Concerning the EPR most of the work is dedicated to sustain the commissioning and start of the first EPR in France on the Flamanville site. Concerning the fuel cycle, CEA's teams are working to improve every stage of the cycle from uranium extraction to the processing of spent fuels. In the nuclear industry, industrial cycles are very long so it is today's work to prepare the fourth generation of reactors even if the first reactor of the third generation is not yet in operation. CEA's research focuses on 2 types of fast reactors, one is sodium-cooled (with ASTRID prototype) while the other is gas-cooled (with ALLEGRO prototype). (A.C.)

  3. Reduced enrichment neutronic study on high power research reactor

    International Nuclear Information System (INIS)

    The FG2DB two dimensional two group diffusion/burnup code and the CELL few group cell parameter code with 69 groups neutron cross section database have been used for reduced enrichment neutronic study on high power research reactor with LEU fuel elements of uranium density 3.6-7.2 g/cm3 and cladding thickness 0.38-0.56 mm. Results show the equivalence of fuel meat uranium density on the thickness changing. Control rod worth and other operation safety parameters of core are acceptable. Parts of the results have been fitted to linear or quadratic expression for easy application. The minimum critical value, excess reactivity, cycle length, fast and thermal fluxes and integrated fluxes, etc. are given. Analysis of these parameters shows that with the U-235 content increased by 20% or more, the LEU core main physical characteristics are similar to those of the HEU core; reduced enrichment almost has no influence on the fast neutron flux; the decreasing rate of the thermal neutron fluxes proportional approximately to the increasing rate of the U-235 content in fuel element; because of the cycle length prolonging, common radioisotope production and fuel element irradiation testing are apparently not influenced. (author)

  4. Tolerating Zero Tolerance?

    Science.gov (United States)

    Moore, Brian N.

    2010-01-01

    The concept of zero tolerance dates back to the mid-1990s when New Jersey was creating laws to address nuisance crimes in communities. The main goal of these neighborhood crime policies was to have zero tolerance for petty crime such as graffiti or littering so as to keep more serious crimes from occurring. Next came the war on drugs. In federal…

  5. Zero-Based Budgeting.

    Science.gov (United States)

    Wichowski, Chester

    1979-01-01

    The zero-based budgeting approach is designed to achieve the greatest benefit with the fewest undesirable consequences. Seven basic steps make up the zero-based decision-making process: (1) identifying program goals, (2) classifying goals, (3) identifying resources, (4) reviewing consequences, (5) developing decision packages, (6) implementing a…

  6. Research on process management of nuclear power technological innovation

    International Nuclear Information System (INIS)

    Different from the other technological innovation processes, the technological innovation process of nuclear power engineering project is influenced deeply by the extensive environmental factors, the technological innovation of nuclear power engineering project needs to make an effort to reduce environmental uncertainty. This paper had described the mechanism of connection technological innovation process of nuclear power engineering project with environmental factors, and issued a feasible method based on model of bargaining to incorporate technological innovation process management of nuclear power engineering project with environmental factors. This method has realistic meanings to guide the technological innovation of nuclear power engineering project. (authors)

  7. The Research on the Soft Power of City Culture

    OpenAIRE

    HONG, XIAONAN; Li, Wenjuan; Lin, Dan

    2012-01-01

    The soft power of city culture is the core of the city soft power. It refers to the influence, cohesion and appeal that a city possesses, which is the main element of the competitiveness and interacts with hard power, for example economy and technology. The soft power of city culture contains the cohesion of city culture, the appeal of city culture, the innovation of city culture, the integration force of city culture and the radiation of city culture. To improve the soft power of ci...

  8. On Power Relation in the Design of Language Research Project and the Analysis of Data

    Science.gov (United States)

    Zhang, Wei

    2009-01-01

    How to deal with the relationship between the researcher and the "researched" is a crucial thing in design of a language research project and the analysis of data. The paper mainly focuses the influence of power relations between the researcher and the "researched" people. To do social research "on, for and with" the…

  9. Laboratory research on combined cooling, heating and power (CCHP) systems

    Energy Technology Data Exchange (ETDEWEB)

    Fu, L.; Zhao, X.L.; Zhang, S.G.; Jiang, Y.; Li, H.; Yang, W.W. [Department of Building Science, School of Architecture, Tsinghua University, Beijing (China)

    2009-04-15

    Combined cooling, heating and power (CCHP) systems offer the potential for a significant increase in fuel use efficiency by generating electricity onsite and recycling the exhaust gas for heating, cooling, or dehumidifying. A challenge for CCHP system is the efficient integration of distributed generation (DG) equipment with thermally-activated (TA) technologies. The China Ministry of Science and Technology and Tsinghua University launched the 863 Hi-Tech Program in 2007 to focus on laboratory and demonstration research to study the critical issues of CCHP systems, advance the technology and accelerate its application. The research performed at the Building Energy Research Center (BERC) Laboratory focuses on assessing the operational performance and energy efficiency of the integration of current DG and TA technologies; developing and verifying mathematical models of the individual devices and all the systems. The test laboratory is a flexible test-bed for the configuration of DG (presently a 70-kW natural gas-fired internal combustion engine (ICE) with various heat recovery units, such as an flue gas-to-water heat recovery unit (FWRU), a jacket water heat recovery unit (JRU), liquid desiccant dehumidification systems (LDS), an exhaust-gas-driven double-effect absorption heat pump (EDAHP), and a condensation heat recovery unit (CRU)). In the winter, the exhaust gas from the ICE is used in the FWRU or used to drive the EDAHP directly, and the exhaust gas from the EDAHP is used in the CRU. The water flows from the CRU can be directed to the evaporator side of the EDAHP as the low-grade heat source. The water flows from the condensation side of the EDAHP, in conjunction with the jacket water flows from the JRU, is used for heating. In the summer, the exhaust gas from the ICE is used to drive the EDAHP for cooling directly, the exhaust gas from the EDAHP is bypassed to the exit via automated damper controls. The waste heat of the jacket water is used to drive the

  10. A study of electrical power network of renewable energies and water desalination research center using power quality phenomena and indices

    International Nuclear Information System (INIS)

    Renewable energies and water distillation research center (REWDRC) is a very strategic research facility and contains many important and critical industrial and electrical loads that must to be operated as a group to fulfill the requirements and the needs of the center in the operation of the main research facility of the center which a 10 MW reactor. Faults on the electrical or the industrial system can occur on many ways such as a malfunction in the questioned system, power quality related problem, or a failure of any of the loads (such as central ventilation or water circulation system or one of the substations) have a great diverse effect on the operation of the main research facility (reactor). In this research common problems due to power quality phenomena were studied, assessed through a assigning some power quality indices to the electrical network of the center so that the operational condition of the REWDRC electrical and industrial network could be evaluated. power quality indices (PQI) were assigned based on results of real time measurements at the points of common coupling of the network (PCC) and the initial power quality survey report. indices analysis was done using three methods which were the normalization method, method of comparing to the limit value and analysis of measurement data time function profile. As a result of this research a recommendation for safe operation against power quality disturbances was pointed out through a continuous monitoring of assigned power quality indices. (Author)

  11. Exergy-based Comparative Assessment of “Zero CO2 Emission” Coal Gasification Processes Feeding H2 –Fueled Power Plants

    Directory of Open Access Journals (Sweden)

    Paolo Fiorini

    2006-03-01

    Full Text Available A modular Process Simulator, CAMEL®, developed by the University of Roma 1, has been applied to analyse a series of “zero emissions” high efficiency cycles. This paper compares three different cycles integrated with CO2 separation technologies based on chemical or physical absorption upstream of the combustion process: pure hydrogen is burnt in presence of pure oxygen to produce superheated steam. All solutions are based on nonconventional plant configurations: two of them are H2/O2 cycles and the third one is the so called ZECOTECH® cycle. The main features of all three configurations are presented and their thermodynamic cycles are simulated in order to perform an exergy analysis.

  12. High Energy Physics Division semiannual report of research activities, January 1, 1990--June 30, 1990

    International Nuclear Information System (INIS)

    This report discusses research programs at ANL in High Energy Physics. The major categories of this research are: experimental programs; theoretical program; experimental facilities research; accelerator research and development; and SSC detector research and development

  13. NASA Net Zero Energy Buildings Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Pless, S.; Scheib, J.; Torcellini, P.; Hendron, B.; Slovensky, M.

    2014-10-01

    In preparation for the time-phased net zero energy requirement for new federal buildings starting in 2020, set forth in Executive Order 13514, NASA requested that the National Renewable Energy Laboratory (NREL) to develop a roadmap for NASA's compliance. NASA detailed a Statement of Work that requested information on strategic, organizational, and tactical aspects of net zero energy buildings. In response, this document presents a high-level approach to net zero energy planning, design, construction, and operations, based on NREL's first-hand experience procuring net zero energy construction, and based on NREL and other industry research on net zero energy feasibility. The strategic approach to net zero energy starts with an interpretation of the executive order language relating to net zero energy. Specifically, this roadmap defines a net zero energy acquisition process as one that sets an aggressive energy use intensity goal for the building in project planning, meets the reduced demand goal through energy efficiency strategies and technologies, then adds renewable energy in a prioritized manner, using building-associated, emission- free sources first, to offset the annual energy use required at the building; the net zero energy process extends through the life of the building, requiring a balance of energy use and production in each calendar year.

  14. Research on the pricing system of online nuclear power

    International Nuclear Information System (INIS)

    National Development and Reform Commission Issues 'Long-term Nuclear Power Development Plan (2005-2020)' in October, 2007. It is the milestone for great development of the nuclear power plant. By the end of the first half of 2009, the nuclear power companies, mainly leading by CNNC and CGNPC, are busy in expanding the new project investment scale of the nuclear power. They gradually initialize the enormous nuclear investment in Zhejiang, Liaoning, Shandong, Guangxi Province and some other place. Along with the development of the nuclear plant and the reformation of the electricity price, the online electricity price of the nuclear power plant will likely be revised. How long will the price policy of 'One to one price' for each type of plant be hold? How will the online electricity price be set in the future? What kind of theories will be followed in the new pricing policy? And what kind of influence will it have on the operating and constructing nuclear power plants? All these will be the problem to the nuclear power plant. There are a lot of uncertainties in front of the nuclear power enterprise in the future. The article analyzes the cost structure of the nuclear power enterprise. Based on the price theory of the market economy, and after benchmarking with the coal power and some other industries, the article studies the future pricing policy of the nuclear power enterprise. And the article analyzes the future management risk of the nuclear power enterprise after the pricing policy reformation. And through the management improvement, the nuclear power company could response effectively to the price regulation, and minimize the uncertainty caused by the pricing policy reformation to the enterprise operation and management. (author)

  15. Human factors research in Central Research Institute of Electric Power Industry creation of safety culture

    Energy Technology Data Exchange (ETDEWEB)

    Horie, Yasuo [Central Research Inst. of Electric Power Industry, Tokyo (Japan)

    2002-03-01

    To prevent accident of nuclear power plant, Human Factors Center was built in the Central Research Institute of Electric Power Industry in July 1987. It developed an evaluation method of human error cases and an application method of human factors information. Now it continues analysis and application of human factors information, development of training/work support tools and research/experiment of human behavior. Japan-Human Performance Evaluation System (J-HPES) was developed as an analytical system for analysis and evaluation of human factors related to the trouble and for using the result as the common property by storage the analytical results. J-HPES has a standard procedure consisted of collecting and analyzing data and proposing the countermeasures. The analytical results are arranged by 4 kinds of charts by putting into the form of a diagram. Moreover, it tries to find the causes with indirect and potential causes. Two kinds of materials, Caution Report and Human Factors Precept by means of Illustrations, are published. People can gain access to HFC database by URL http://criepi.denken.or.jp/CRIEPI/HFC/DB. To prevent these accidents, creation of human factors culture has been required. Five kinds of teaching materials and the training method are developed. (S.Y.)

  16. Human factors research in Central Research Institute of Electric Power Industry creation of safety culture

    International Nuclear Information System (INIS)

    To prevent accident of nuclear power plant, Human Factors Center was built in the Central Research Institute of Electric Power Industry in July 1987. It developed an evaluation method of human error cases and an application method of human factors information. Now it continues analysis and application of human factors information, development of training/work support tools and research/experiment of human behavior. Japan-Human Performance Evaluation System (J-HPES) was developed as an analytical system for analysis and evaluation of human factors related to the trouble and for using the result as the common property by storage the analytical results. J-HPES has a standard procedure consisted of collecting and analyzing data and proposing the countermeasures. The analytical results are arranged by 4 kinds of charts by putting into the form of a diagram. Moreover, it tries to find the causes with indirect and potential causes. Two kinds of materials, Caution Report and Human Factors Precept by means of Illustrations, are published. People can gain access to HFC database by URL http://criepi.denken.or.jp/CRIEPI/HFC/DB. To prevent these accidents, creation of human factors culture has been required. Five kinds of teaching materials and the training method are developed. (S.Y.)

  17. [Aiming for zero blindness].

    Science.gov (United States)

    Nakazawa, Toru

    2015-03-01

    comprehensive expression analyses or imaging data. This is an important area of research, since it promises to enable the exploration of targets for drug discovery and the identification of new biomarkers to efficiently detect glaucoma progression by applying new analysis strategies to the complex mass data. The project not only depends on the collaborative efforts of various types of clinical settings including private practices, medical centers and university hospitals, but also contributions of the pharmaceutical and the medical device industries. Thus, uniting a wide range of Japanese interests and resources is the key for success. In summary, in order to aim for ZERO BLINDNESS, a drastic improvement in the quality of our patient care, drug development research for unmet medical demands, and a strategic collaboration of various professionals in the ophthalmic industry are essential. With the deep appreciation we fell towards the selfless support extended during the earthquake disaster, we wish to translate our "gratitude" into "power" from Tohoku. In doing so, we as academicians are determined to keep on contributing to the society by making progress in the medicine. PMID:25854109

  18. ANL ITER high-heat-flux blanket-module heat transfer experiments. Fusion Power Program

    Energy Technology Data Exchange (ETDEWEB)

    Kasza, K.E.

    1992-02-01

    An Argonne National Laboratory facility for conducting tests on multilayered slab models of fusion blanket designs is being developed; some of its features are described. This facility will allow testing under prototypic high heat fluxes, high temperatures, thermal gradients, and variable mechanical loadings in a helium gas environment. Steady and transient heat flux tests are possible. Electrical heating by a two-sided, thin stainless steel (SS) plate electrical resistance heater and SS water-cooled cold panels placed symmetrically on both sides of the heater allow achievement of global one-dimensional heat transfer across blanket specimen layers sandwiched between the hot and cold plates. The heat transfer characteristics at interfaces, as well as macroscale and microscale thermomechanical interactions between layers, can be studied in support of the ITER engineering design effort. The engineering design of the test apparatus has shown that it is important to use multidimensional thermomechanical analysis of sandwich-type composites to adequately analyze heat transfer. This fact will also be true for the engineering design of ITER.

  19. Power start up of the Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    After accomplishing the physical start-up of the reactor, the power start-up was carried out in February 1984. The power of the reactor has reached: 10 KW on 6/2/1984, 100 KW on 7/2/1984, 200 KW and 300 KW on 8/2/1984; 400 KW and nominal power 500 KW on 9/2/1984. The reactivity temperature coefficient and the xenon poisoning were determined. 3 figs., 12 tabs

  20. Power

    DEFF Research Database (Denmark)

    Elmholdt, Claus Westergård; Fogsgaard, Morten

    2016-01-01

    In this chapter, we will explore the dynamics of power in processes of creativity, and show its paradoxical nature as both a bridge and a barrier to creativity in organisations. Recent social psychological experimental research (Slighte, de Dreu & Nijstad, 2011) on the relation between power and...... creativity suggests that when managers give people the opportunity to gain power and explicate that there is reason to be more creative, people will show a boost in creative behaviour. Moreover, this process works best in unstable power hierarchies, which implies that power is treated as a negotiable and...... floating source for empowering people in the organisation. We will explore and discuss here the potentials, challenges and pitfalls of power in relation to creativity in the life of organisations today. The aim is to demonstrate that power struggles may be utilised as constructive sources of creativity. It...

  1. Fuel Cells: Power System Option for Space Research

    Science.gov (United States)

    Shaneeth, M.; Mohanty, Surajeet

    2012-07-01

    Fuel Cells are direct energy conversion devices and, thereby, they deliver electrical energy at very high efficiency levels. Hydrogen and Oxygen gases are electrochemically processed, producing clean electric power with water as the only by product. A typical, Fuel Cell based power system involve a Electrochemical power converter, gas storage and management systems, thermal management systems and relevant control units. While there exists different types of Fuel cells, Proton Exchange Membrane (PEM) Fuel Cells are considered as the most suitable one for portable applications. Generally, Fuel Cells are considered as the primary power system option in space missions requiring high power ( > 5kW) and long durations and also where water is a consumable, such as manned missions. This is primarily due to the advantage that fuel cell based power systems offer, in terms of specific energy. Fuel cells have the potential to attain specific energy > 500Wh/kg, specific power >500W/kg, energy density > 400Whr/L and also power density > 200 W/L. This apart, a fuel cell system operate totally independent of sun light, whereas as battery based system is fully dependent on the same. This uniqueness provides added flexibility and capabilities to the missions and modularity for power system. High power requiring missions involving reusable launch vehicles, manned missions etc are expected to be richly benefited from this. Another potential application of Fuel Cell would be interplanetary exploration. Unpredictable and dusty atmospheres of heavenly bodies limits sun light significantly and there fuel cells of different types, eg, Bio-Fuel Cells, PEMFC, DMFCs would be able to work effectively. Manned or unmanned lunar out post would require continuous power even during extra long lunar nights and high power levels are expected. Regenerative Fuel Cells, a combination of Fuel Cells and Electrolysers, are identified as strong candidate. While application of Fuel Cells in high power

  2. Net-Zero Energy Technical Shelter

    DEFF Research Database (Denmark)

    Zhang, Chen; Heiselberg, Per; Jensen, Rasmus Lund

    2014-01-01

    technical shelter, this study will apply the net-zero energy concept into the technical shelter design. The energy conservation can be achieved by proper design of building envelop and optimization of the cooling strategies. Both experiments and numerical simulations are carried out to investigate the...... indoor environment and energy performance of the technical shelter. Finally, a wind-solar hybrid energy system is designed as an alternative power solution for technical shelter, in order to achieve a net-zero energy target....

  3. Theory model and experiment research about the cognition reliability of nuclear power plant operators

    International Nuclear Information System (INIS)

    In order to improve the reliability of NPP operation, the simulation research on the reliability of nuclear power plant operators is needed. Making use of simulator of nuclear power plant as research platform, and taking the present international reliability research model-human cognition reliability for reference, the part of the model is modified according to the actual status of Chinese nuclear power plant operators and the research model of Chinese nuclear power plant operators obtained based on two-parameter Weibull distribution. Experiments about the reliability of nuclear power plant operators are carried out using the two-parameter Weibull distribution research model. Compared with those in the world, the same results are achieved. The research would be beneficial to the operation safety of nuclear power plant

  4. The nuclear power corporation's foreign exchange risk management research

    International Nuclear Information System (INIS)

    To manage and control foreign exchange rate risk under the floating exchange rate system, historical simulation method of VaR model has been utilized to evaluate the nuclear power corporation's foreign exchange risk and the risk causation has been analyzed. Finally, the measure of enhancing the nuclear power corporation's foreign exchange rate risk management level has been exposed for sharing. (author)

  5. The research and development of the automatic solar power tracker

    Directory of Open Access Journals (Sweden)

    Li Yan Ping

    2016-01-01

    Full Text Available The article describes a kind of automatic tracker using solar power. It depends on two important parts which are servo system and adjusting mechanism system to keep the tracker operating normally. The article focuses on describing the characteristics and functions of two systems and the operating details of the automatic solar power tracker.

  6. Outline of the safety research results, in the power reactor field, fiscal year 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    The Power Reactor and Nuclear Fuel Development Corporation (PNC) has promoted the safety research in fiscal year of 1996 according to the Fundamental Research on Safety Research (fiscal year 1996 to 2000) prepared on March, 1996. Here is described on the research results in fiscal year 1996, the first year of the 5 years programme, and whole outline of the fundamental research on safety research, on the power reactor field (whole problems on the new nuclear converter and the fast breeder reactor field and problems relating to the power reactor in the safety for earthquake and probability theoretical safety evaluation field). (G.K.)

  7. Outline of the safety research results, in the power reactor field, fiscal year 1996

    International Nuclear Information System (INIS)

    The Power Reactor and Nuclear Fuel Development Corporation (PNC) has promoted the safety research in fiscal year of 1996 according to the Fundamental Research on Safety Research (fiscal year 1996 to 2000) prepared on March, 1996. Here is described on the research results in fiscal year 1996, the first year of the 5 years programme, and whole outline of the fundamental research on safety research, on the power reactor field (whole problems on the new nuclear converter and the fast breeder reactor field and problems relating to the power reactor in the safety for earthquake and probability theoretical safety evaluation field). (G.K.)

  8. Research on risk communication after the Fukushima nuclear power plant accident

    International Nuclear Information System (INIS)

    This report is about the risk communication cases that the author participated in after the Fukushima nuclear power plant accident. The research aims to clarify the content of information that should be provided in risk communication and to develop a risk communication tool specifically designed for this purpose. The risk communication cases were explanatory meetings intended for the residents in Fukushima Prefecture and the advisory council on radiation health effects sponsored by Tochigi Prefecture. To clarify the kinds of information necessary to provide at such meetings, we conducted a questionnaire survey of 31 food sanitation inspectors using the Delphi method. A gaming simulation was used for the development of the communication tool. We used public disclosure materials at the meetings and the survey was conducted only among those whom we obtained written informed consent. The content regarding the radioactive substances in food which was found to be the most important for the consumers to learn was ''zero risk is impossible'' (84 points), followed by ''radioactive substances and other risks (e.g. smoking and excessive alcohol intake)'' (70 points). To develop the communication tool, we used ''Quartetto (card game)'' and the contents were such as ''daily life'', ''radioactive substances'', and ''measurement''. Considering the questions raised from the residents at the meetings, an information portal such as homepages did not provide clear information on how to evaluate risks by themselves. The results from the questionnaire survey shows that it is difficult to solve this matter unless the public learns to think about the risks of various matters on their own. The lack of experts will make it necessary for the local government officials to provide more information, and therefore training on risk communication is essential. We need to evaluate the Quartetto game and revise the content considering the audience. (author)

  9. Fire Environment Mechanism of Lightning-groundfire for Daxing anling Mountains

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    Ground fire is an igniting phenomenon that is difficult to control and lightning is the main cause of ground fire. The mechanism of lightning-ground fire is very complex. Daxing'anling Mountains forest region is the place that lighting-groundfire occurs more often and regularly. Our study on lightning-groundfire of this zone in 2002 shows: much more soil near the surface and the ground fuel is the matter preconditions of lightning-groundfire, and the weather conditions hasten the occurrence of lightning...

  10. Review of the status of low power research reactors and considerations for its development

    Energy Technology Data Exchange (ETDEWEB)

    Lim, In Cheol; Wu, Sang Ik; Lee, Byung Chul; Ha, Jae Joo [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    At present, 232 research reactors in the world are in operation and two thirds of them have a power less than 1 MW. Many countries have used research reactors as the tools for educating and training students or engineers and for scientific service such as neutron activation analysis. As the introduction of a research reactor is considered a stepping stone for a nuclear power development program, many newcomers are considering having a low power research reactor. The IAEA has continued to provide forums for the exchange of information and experiences regarding low power research reactors. Considering these, the Agency is recently working on the preparation of a guide for the preparation of technical specification possibly for a member state to use when wanting to purchase a low power research reactor. In addition, ANS has stated that special consideration should be given to the continued national support to maintain and expand research and test reactor programs and to the efforts in identifying and addressing the future needs by working toward the development and deployment of next generation nuclear research and training facilities. Thus, more interest will be given to low power research reactors and its role as a facility for education and training. Considering these, the status of low power research reactors was reviewed, and some aspects to be considered in developing a low power research reactor were studied.

  11. A COMPREHENSIVE MODEL FOR THE POWER TRANSFORMER DIGITAL DIFFERENTIAL PROTECTION FUNCTIONING RESEARCH

    OpenAIRE

    Yu. V. Rumiantsev

    2016-01-01

    This article presents a comprehensive model for the two-winding power transformer digital differential protection functioning research. Considered comprehensive model is developed in MatLab-Simulink dynamic simulation environment with the help of SimPowerSystems component library and includes the following elements: power supply, three-phase power transformer, wye-connected current transformers and two-winding power transformer digital differential protection model. Each element of the presen...

  12. 集成氧离子传输膜的CO2零排放固体氧化物燃料电池复合动力系统%Study on Zero CO2 Emission Solid Oxide Fuel Cell Hybrid Power Systems Integrated With Oxygen Ion Transport Membrane

    Institute of Scientific and Technical Information of China (English)

    2013-01-01

    In order to further reduce the energy consumption of CO2 recovery in the solid oxide fuel cell (SOFC) hybrid system, a new zero CO2 emission SOFC hybrid power system integrated with oxygen ion transport membrane (OTM) was proposed in this paper. With the method of unit consumption analysis, the energy consumption distribution characteristics of overall system were obtained, and then the effects of key operation parameters on the overall system performance were investigated. This paper also compared the performances of the new system with the zero CO2 emission SOFC hybrid power system integrated with the traditional cryogenic air separation unit. The results show that the new system still has high efficiency after CO2 recovery. Compared with other systems, the efficiency of the zero CO2 emission SOFC hybrid power system integrated with OTM is around 64.71%, only 2.16 percentage lower than that of the traditional SOFC hybrid power system (66.87%) without CO2 capture and 0.74 percentage higher than that of the zero CO2 emission SOFC hybrid system with the cryogenic air separation unit (63.97%). The research achievements provide valuable reference for further study on zero CO2 emissions SOFC hybrid power systems with higher efficiency.%  为了进一步降低固体氧化物燃料电池(solid oxide fuel cell,SOFC)复合系统回收 CO2的能耗,该文提出一个新型的集成氧离子传输膜(oxygen ion transport membrane,OTM)的 CO2零排放 SOFC 复合动力系统。利用单耗分析方法得到系统各单元的能耗分布情况,分析了SOFC的主要参数对整个系统性能的影响,并与集成传统深冷空分系统的零CO2排放SOFC复合动力系统进行了比较研究。研究结果表明:与不回收CO2的传统SOFC复合动力系统相比,与OTM集成的复合动力系统效率下降仅2.16个百分点,比与传统深冷空分系统集成的复合动力系统效率高0.74个百分点。该文研究成果可以为研究更高效

  13. Poster abstract: A decentralized routing scheme based on a zero-sum game to optimize energy in solar powered sensor networks

    KAUST Repository

    Dehwah, Ahmad H.

    2014-04-01

    This poster is aimed at solving the problem of maximizing the energy margin of a solar-powered sensor network at a fixed time horizon, to maximize the network performance during an event to monitor. Using a game theoretic approach, the optimal routing maximizing the energy margin of the network at a given time under solar power forcing can be computed in a decentralized way and solved exactly through dynamic programming with a low overall complexity. We also show that this decentralized algorithm is simple enough to be implemented on practical sensor nodes. Such an algorithm would be very useful whenever the energy margin of a solar-powered sensor network has to be maximized at a specific time. © 2014 IEEE.

  14. Starting From Ground Zero

    Science.gov (United States)

    Fischer, William B.; Stauffer, Robert A.

    1978-01-01

    Erie County Community College (New York) has developed a zero-based program budgeting system to meet current fiscal problems and diminished resources. The system allocates resources on the basis of program effectiveness and market potential. (LH)

  15. Microgravity Spray Cooling Research for High Powered Laser Applications

    Science.gov (United States)

    Zivich, Chad P.

    2004-01-01

    An extremely powerful laser is being developed at Goddard Space Flight Center for use on a satellite. This laser has several potential applications. One application is to use it for upper atmosphere weather research. In this case, the laser would reflect off aerosols in the upper atmosphere and bounce back to the satellite, where the aerosol velocities could be calculated and thus the upper atmosphere weather patterns could be monitored. A second application would be for the US. Air Force, which wants to use the laser strategically as a weapon for satellite defense. The Air Force fears that in the coming years as more and more nations gain limited space capabilities that American satellites may become targets, and the laser could protect the satellites. Regardless of the ultimate application, however, a critical step along the way to putting the laser in space is finding a way to efficiently cool it. While operating the laser becomes very hot and must be cooled to prevent overheating. On earth, this is accomplished by simply running cool tap water over the laser to keep it cool. But on a satellite, this is too inefficient. This would require too much water mass to be practical. Instead, we are investigating spray cooling as a means to cool the laser in microgravity. Spray cooling requires much less volume of fluid, and thus could be suitable for use on a satellite. We have inherited a 2.2 second Drop Tower rig to conduct our research with. In our experiments, water is pressurized with a compressed air tank and sprayed through a nozzle onto our test plate. We can vary the pressure applied to the water and the temperature of the plate before an experiment trial. The whole process takes place in simulated microgravity in the 2.2 second Drop Tower, and a high speed video camera records the spray as it hits the plate. We have made much progress in the past few weeks on these experiments. The rig originally did not have the capability to heat the test plate, but I did

  16. Space Solar Power Satellite Technology Development at the Glenn Research Center: An Overview

    Science.gov (United States)

    Dudenhoefer, James E.; George, Patrick J.

    2000-01-01

    NASA Glenn Research Center (GRC). is participating in the Space Solar Power Exploratory Research and Technology program (SERT) for the development of a solar power satellite concept. The aim of the program is to provide electrical power to Earth by converting the Sun's energy and beaming it to the surface. This paper will give an overall view of the technologies being pursued at GRC including thin film photovoltaics, solar dynamic power systems, space environmental effects, power management and distribution, and electric propulsion. The developmental path not only provides solutions to gigawatt sized space power systems for the future, but provides synergistic opportunities for contemporary space power architectures. More details of Space Solar Power can be found by reading the references sited in this paper and by connecting to the web site http://moonbase.msfc.nasa.gov/ and accessing the "Space Solar Power" section "Public Access" area.

  17. The research on the material management system in nuclear power plant construction process

    International Nuclear Information System (INIS)

    According to the module construction speciality of nuclear power plant, this article analyzes the relationship between the actual amount of the material transported to the construction site and the planed needs of the material, and points out the zero inventory management target in the nuclear power plant construction site. Based on this, the article put forward a nuclear power plant material management system which is based on the 'pull' information driver. This system is composed by material coding sub-system, procurement and site material integrated management sub-system and project control sub-system, and is driven by the material demand from construction site to realize the JIT purchasing. This structure of the system can reduce the gap between the actual amount of the material transported to the site and the planed needs of the material and achieve the target of reducing storage at construction site. (authors)

  18. Assessment Using ANL Experiments on Void Fraction in a Vertical Tube

    Energy Technology Data Exchange (ETDEWEB)

    Han, KyuHyun; Bang, YoungSeok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    A licensing application of a safety analysis code, SPACE, was submitted and is currently under KINS' review. This code was developed to consider three fluid fields, i.e. liquid, vapor and droplet, for a realistic simulation of accident phenomena. Therefore, there may be a concern that this code could predict different behavior compared to the existing codes. To assess the important performance independently and to compare with prediction results of SPACE might be helpful to regulatory review for identifying validity of the code. The interfacial friction could largely affect prediction of thermal hydraulic phenomena during LOCA or non- LOCA. This paper provides MARS-KS prediction of void fraction experiments in a vertical tube by ANL and compares with SPACE prediction results. It was found that the similar interfacial friction model adopting the drift flux correlations were implemented in both codes. Experimental void fractions of the ANL test presented in this paper correspond to bubbly, slug and churn flow regions. Agreements in general sense between the experiment and the predicted values were identified through calculations. Thus, similar accuracy for this experiment can be expected in SPACE and MARS-KS. It was also shown that drift flux interfacial friction model for intermediate flow channel (diameter of 7cm) is valid.

  19. Research on stochastic power-flow study methods. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Heydt, G. T. [ed.

    1981-01-01

    A general algorithm to determine the effects of uncertainty in bus load and generation on the output of conventional power flow analysis is presented. The use of statistical moments is presented and developed as a means for representing the stochastic process. Statistical moments are used to describe the uncertainties, and facilitate the calculations of single and multivarlate probability density functions of input and output variables. The transformation of the uncertainty through the power flow equations is made by the expansion of the node equations in a multivariate Taylor series about an expected operating point. The series is truncated after the second order terms. Since the power flow equations are nonlinear, the expected values of output quantities is in general not the solution to the conventional load flow problem using expected values of input quantities. The second order transformation offers a correction vector and allows the consideration of larger uncertainties which have caused significant error in the current linear transformation algorithms. Voltage controlled busses are included with consideration of upper and lower limits. The finite reactive power available at generation sites, and fixed ranges of transformer tap movement may have a significant effect on voltage and line power flow statistics. A method is given which considers limitation constraints in the evaluation of all output quantities. The bus voltages, line power flows, transformer taps, and generator reactive power requirements are described by their statistical moments. Their values are expressed in terms of the probability that they are above or below specified limits, and their expected values given that they do fall outside the limits. Thus the algorithm supplies information about severity of overload as well as probability of occurrence. An example is given for an eleven bus system, evaluating each quantity separately. The results are compared with Monte Carlo simulation.

  20. Zero emission city. Preliminary study; Null-Emissions-Stadt. Sondierungsstudie

    Energy Technology Data Exchange (ETDEWEB)

    Diefenbach, N.; Enseling, A.; Werner, P.; Flade, A.; Greiff, R.; Hennings, D.; Muehlich, E.; Wullkopf, U.; Sturm, P.; Kieslich, W.; Born, R.; Grossklos, M.; Hatteh, R.; Mueller, K.; Ratschow, A.; Valouch-Fornoff, C.

    2002-10-01

    The idea of a 'zero emission city' is investigated by the Institut Wohnen und Umwelt on behalf of the Federal Minister of Education and Research. After describing the current situation and defining the key parameters of a 'zero emission city', settlement structures, power supply, production processes and transportation are analyzed and linked with the communal action level to obtain a framework for research, activities and actions. The study ends with recommendations for a research programme 'zero emission city'. (orig.) [German] Die von den Staedten der Industrielaender ausgehenden Emissionen stellen im Hinblick auf die globalen Belastungen wie z.B. Treibhauseffekt, Ozonabbau und Versauerung das Hauptproblem dar. Aus diesem Grunde bietet es sich an, den Gedanken der 'Null-Emissions-Stadt', der Vision einer moeglichst emissionsfreien Stadt, aufzugreifen und auf seine Tragfaehigkeit fuer innovative Handlungsmodelle forschungsstrategisch zu ueberpruefen. Das Bundesministerium fuer Bildung und Forschung hat das Institut Wohnen und Umwelt beauftragt, in einer Sondierungsstudie dieser Fragestellung nachzugehen. Nach der Festlegung der Ausgangsbedingungen und Eckpunkte der Vision 'Null-Emissions-Stadt' und der Analyse der vier Handlungsfelder Siedlungsstrukturen, Energieversorgung, Produktionsprozesse (Kreislaufwirtschaft) und Verkehr werden diese aufgegriffen und mit der kommunalen Handlungsebene verknuepft und zu einem Forschungs-, Handlungs- und moeglichen Aktionsrahmen zusammengefuegt. Die Studie schliesst mit Hinweisen fuer die Gestaltung eines Forschungsprogramms 'Null-Emissions-Stadt'. (orig.)

  1. Advanced underground Vehicle Power and Control: The locomotive Research Platform

    Energy Technology Data Exchange (ETDEWEB)

    Vehicle Projects LLC

    2003-01-28

    Develop a fuelcell mine locomotive with metal-hydride hydrogen storage. Test the locomotive for fundamental limitations preventing successful commercialization of hydride fuelcells in underground mining. During Phase 1 of the DOE-EERE sponsored project, FPI and its partner SNL, completed work on the development of a 14.4 kW fuelcell power plant and metal-hydride energy storage. An existing battery-electric locomotive with similar power requirements, minus the battery module, was used as the base vehicle. In March 2001, Atlas Copco Wagner of Portland, OR, installed the fuelcell power plant into the base vehicle and initiated integration of the system into the vehicle. The entire vehicle returned to Sandia in May 2001 for further development and integration. Initial system power-up took place in December 2001. A revision to the original contract, Phase 2, at the request of DOE Golden Field Office, established Vehicle Projects LLC as the new prime contractor,. Phase 2 allowed industry partners to conduct surface tests, incorporate enhancements to the original design by SNL, perform an extensive risk and safety analysis, and test the fuelcell locomotive underground under representative production mine conditions. During the surface tests one of the fuelcell stacks exhibited reduced power output resulting in having to replace both fuelcell stacks. The new stacks were manufactured with new and improved technology resulting in an increase of the gross power output from 14.4 kW to 17 kW. Further work by CANMET and Hatch Associates, an engineering consulting firm specializing in safety analysis for the mining industry, both under subcontract to Vehicle Projects LLC, established minimum requirements for underground testing. CANMET upgraded the Programmable Logic Control (PLC) software used to monitor and control the fuelcell power plant, taking into account locomotive operator's needs. Battery Electric, a South Africa manufacturer, designed and manufactured (at no cost

  2. Variable-Speed Power-Turbine Research at Glenn Research Center

    Science.gov (United States)

    Welch, Gerard E.; McVetta, Ashlie B.; Stevens, Mark A.; Howard, Samuel A.; Giel, Paul W.; Ameri, Ali, A.; To, Waiming; Skoch, Gary J.; Thurman, Douglas R.

    2012-01-01

    The main rotors of the NASA Large Civil Tilt-Rotor (LCTR) notional vehicle operate over a wide speed-range, from 100 percent at takeoff to 54 percent at cruise. The variable-speed power turbine (VSPT) offers one approach by which to effect this speed variation. VSPT aerodynamics challenges include high work factors at cruise, wide (40 to 60 ) incidence-angle variations in blade and vane rows over the speed range, and operation at low Reynolds numbers. Rotordynamics challenges include potential responsiveness to shaft modes within the 50 percent VSPT speed-range. A research effort underway at NASA Glenn Research Center, intended to address these key aerodynamic and rotordynamic challenges, is described. Conceptual design and 3-D multistage RANS and URANS analyses, conducted internally and under contract, provide expected VSPT sizing, stage-count, performance and operability information, and maps for system studies. Initial steps toward experimental testing of incidence-tolerant blading in a transonic linear cascade are described, and progress toward development/improvement of a simulation capability for multistage turbines with low Reynolds number transitional flow is summarized. Preliminary rotordynamics analyses indicate that viable concept engines with 50 percent VSPT shaft-speed range. Assessments of potential paths toward VSPT component-level testing are summarized.

  3. A Novel Low-Power, High-Performance, Zero-Maintenance Closed-Path Trace Gas Eddy Covariance System with No Water Vapor Dilution or Spectroscopic Corrections

    Science.gov (United States)

    Sargent, S.; Somers, J. M.

    2015-12-01

    Trace-gas eddy covariance flux measurement can be made with open-path or closed-path analyzers. Traditional closed-path trace-gas analyzers use multipass absorption cells that behave as mixing volumes, requiring high sample flow rates to achieve useful frequency response. The high sample flow rate and the need to keep the multipass cell extremely clean dictates the use of a fine-pore filter that may clog quickly. A large-capacity filter cannot be used because it would degrade the EC system frequency response. The high flow rate also requires a powerful vacuum pump, which will typically consume on the order of 1000 W. The analyzer must measure water vapor for spectroscopic and dilution corrections. Open-path analyzers are available for methane, but not for nitrous oxide. The currently available methane analyzers have low power consumption, but are very large. Their large size degrades frequency response and disturbs the air flow near the sonic anemometer. They require significant maintenance to keep the exposed multipass optical surfaces clean. Water vapor measurements for dilution and spectroscopic corrections require a separate water vapor analyzer. A new closed-path eddy covariance system for measuring nitrous oxide or methane fluxes provides an elegant solution. The analyzer (TGA200A, Campbell Scientific, Inc.) uses a thermoelectrically-cooled interband cascade laser. Its small sample-cell volume and unique sample-cell configuration (200 ml, 1.5 m single pass) provide excellent frequency response with a low-power scroll pump (240 W). A new single-tube Nafion® dryer removes most of the water vapor, and attenuates fluctuations in the residual water vapor. Finally, a vortex intake assembly eliminates the need for an intake filter without adding volume that would degrade system frequency response. Laboratory testing shows the system attenuates the water vapor dilution term by more than 99% and achieves a half-power band width of 3.5 Hz.

  4. Research and application of Automatic Voltage Control in Tongbai Pumped Storage Power Station

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    The Automatic Voltage Control is significant technique of modem power grid operation, and it is one of important function of intelligent grid management, it plays an important role to ensure the security, high quality and economical operation of power grid. This paper introduces the research and application of Automatic Voltage Control in Tongtai Pumped Storage Power Station.

  5. 旋转编码器找零安装装置研制%Research on Adjustment Device to Find Zero Position for Rotary Encoder

    Institute of Scientific and Technical Information of China (English)

    丁仕燕

    2013-01-01

    为了使旋转编码器安装时在零位,设计了找零位装置,该装置包括电子手轮、步进电机、蜗杆、斜齿轮和磁力表座组件.斜齿轮安装在旋转编码器的空心转轴上;磁力表座组件依靠磁铁吸力固定在自动化设备上,蜗杆安装在轴套中,该轴套被夹在磁力表座组件的弹性孔夹头中.电子手轮输出信号接入步进电机驱动器,步进电机跟随电子手轮转动进而驱动蜗杆转动,蜗杆驱动斜齿轮,进而驱动旋转编码器空心转轴;同时计算机读取旋转编码器输出信号以判断其是否在零位,如在零位,则立刻停止转动电子手轮.实验结果表明:利用该装置可方便、快捷地把旋转编码器安装在零位.%The adjustment device was designed in order that rotary encoder could be installed at zero position.The adjustment device was composed of a electronic handwheel,a step motor,a helical gear,a worm and a magnetic table block.The helical gear was installed on hollow shaft of rotary encoder,the magnetic table block was fixed on automated equipment by means of magnetic suction,the worm was installed in axle sleeve,which was clamped in elastic hole chuck of the magnetic table block.Output signals of the electronic handwheel was connected to step motor driver,the worm was driven by the step motor,which rotated following the electronic handwheel.The helical gear was driven by the worm,the hollow shaft of rotary encoder was driven by the helical gear.At the same time,output signals of the rotary encoder was read by software and used to judge whether the rotary encoder was at zero position.The rotation of the electronic handwheel was stopped immediately if the rotary encoder was at zero position.Experimental results show that the rotary encoder can be installed at zero position efficiently and easily with the adjustment device.

  6. Research on the fusion diagnosis system of nuclear power plants

    International Nuclear Information System (INIS)

    The work condition of nuclear power plants (NPP) is terrible, so it has faults frequently. In order to guarantee the safety of nuclear power plants, the fusion fault diagnosis system has built. Multi-sensors data fusion technology is applied to the fault diagnosis system. The data fusion level module mainly handles the metrical data of multi-sensors and extracts the feature of faults. The feature level module adopts three parallel neural networks, and its function is to do local diagnosis and to get Basic Probability Assignment (BPA) of D-S evidence theory. The decision fusion level module uses D-S evidence theory. Several main faults of gas turbine rotor and the primary loop of nuclear power plants are diagnosed by the system on the tester and simulator respectively. The analyses of the results indicate that the diagnosis system can diagnose the faults exactly in real time, and the precision is very high. (authors)

  7. Neutron beam applications using low power research reactor Malaysia perspectives

    International Nuclear Information System (INIS)

    The TRIGA MARK II Research reactor at the Malaysian Institute for Nuclear Research (MINT) was commissioned in July 1982. Since then various works have been performed to utilise the neutrons produced from this steady state reactor. One area currently focussed on is the utilisation of neutron beam ports available at this 1MW reactor. Projects undertaken are the development and utilisation of the Neutron Radiography (myNR), Small Angle Neutron Scattering (mySANS) and Boron Neutron Capture Therapy (BNCT) - preliminary study. In order to implement active research programmes, a group comprised of researcher from research institutes and academic institutions, has formed: known as Malaysian Reactor Interest Group (MRIG). This paper describes the recent status the above neutron beam facilities and their application in industrial, health and material technology research and education. The related activities of MRIG are also highlighted. (author)

  8. A basic research on wireless communication in nuclear power plants

    International Nuclear Information System (INIS)

    The use of wireless communication systems in nuclear power plants has been limited due to their interference with the operation of safety-related digital instrumentation and control (I et C) systems. If wireless communication systems could avoid that interference, their use in nuclear power plants would have many benefits. In this paper, we measured the electromagnetic field intensity for the operation of a portable transceiver near safety-related system cabinets, and then we calculated the field intensity limits within which a portable transceiver could be used without causing unwanted behaviour in digital I et C systems. (Author)

  9. Discourses of power in mathematics education research: Concepts and possibilities for action

    DEFF Research Database (Denmark)

    Valero, Paola

    2008-01-01

    Mathematics education is powerful. This is an assertion that appears often in mathematics education research papers. However, the meaning of the assertion is far from being clear. An analysis of different ways of talking about power in relation to mathematics education, in research literature...

  10. 船载雷达角度零值动态标定方法研究%Research on angle zero dynamic calibration method for ship radar

    Institute of Scientific and Technical Information of China (English)

    李志坚; 胡金辉; 陈小刚

    2013-01-01

    针对船载雷达海上动态环境下角度标校的难题,介绍了船载雷达角度零值动态标定新方法——星体测量法,该方法以高精度的经纬仪为基准,通过雷达与经纬仪联合测量恒星,在同一坐标系下进行数据处理,得到角度零值.同时,本文对各种标定方法的优劣进行研究分析,通过试验验证,与传统坞内标定等方法相比,动态标定新方法优势显著,提高了测角精度.%Aimed at the problem of angle calibration dynamically on the sea for ship radar, the article introduced a new method of angle zero dynamic calibration-star measurement. As a reference,the precision of theodolite was higher. Ship radar and theodolite measured star together and the data was processed in the same coordinate system to get angle zero of radar. The advantages and disadvantages of various calibration method was analyzed. Via the results of experimentation,the angular accuracy of new method was raised obviously compared with traditional dock calibration.

  11. Causality in Statistical Power: Isomorphic Properties of Measurement, Research Design, Effect Size, and Sample Size

    OpenAIRE

    R. Eric Heidel

    2016-01-01

    Statistical power is the ability to detect a significant effect, given that the effect actually exists in a population. Like most statistical concepts, statistical power tends to induce cognitive dissonance in hepatology researchers. However, planning for statistical power by an a priori sample size calculation is of paramount importance when designing a research study. There are five specific empirical components that make up an a priori sample size calculation: the scale of measurement of t...

  12. Research Of The Efficiency Of The Wireless Power Transfer With The Employment Of DD Inductance Coils

    OpenAIRE

    Krainyukov Alexander; Lyaksa Igor; Saltanovs Rodions

    2015-01-01

    The paper is devoted to using of DD inductance coils for the wireless power transfer. The aim of the given research is to determine influence of the parameters of resonance transformer on the efficiency of the wireless power transfer with the use of the DD inductance coils. Experimental installation of the wireless power transfer by a resonance inductive method was constructed. Experiments were performed with it help. Research results show influence of the distance between the coils of induct...

  13. Research on calorimeter for high-power microwave measurements

    International Nuclear Information System (INIS)

    Based on measurement of the volume increment of polar liquid that is a result of heating by absorbed microwave energy, two types of calorimeters with coaxial capacitive probes for measurement of high-power microwave energy are designed in this paper. The first is an “inline” calorimeter, which is placed as an absorbing load at the end of the output waveguide, and the second is an “offline” calorimeter that is placed 20 cm away from the radiation horn of the high-power microwave generator. Ethanol and high density polyethylene are used as the absorbing and housing materials, respectively. Results from both simulations and a “cold test” on a 9.3 GHz klystron show that the “inline” calorimeter has a measurement range of more than 100 J and an energy absorption coefficient of 93%, while the experimental results on a 9.3 GHz relativistic backward-wave oscillator show that the device’s power capacity is approximately 0.9 GW. The same experiments were also carried out for the “offline” calorimeter, and the results indicate that it can be used to eliminate the effects of the shock of the solenoid on the measurement curves and that the device has a higher power capacity of 2.5 GW. The results of the numerical simulations, the “cold tests,” and the experiments show good agreement

  14. Research and development of advanced robots for nuclear power plants

    International Nuclear Information System (INIS)

    Social and economic demands have been pressing for automation of inspection tasks, maintenance and repair jobs of nuclear power plants, which are carried out by human workers under circumstances with high radiation level. Since the plants are not always designed for introduction of automatic machinery, sophisticated robots shall play a crucial role to free workers from hostile environments. We have been studying intelligent robot systems and regarded nuclear industries as one of the important application fields where we can validate the feasibility of the methods and systems we have developed. In this paper we firstly discuss on the tasks required in nuclear power plants. Secondly we introduce current status of R and D on special purpose robots, versatile robots and intelligent robots for automatizing the tasks. Then we focus our discussions on three major functions in realizing robotized assembly tasks under such unstructured environments as in nuclear power plants; planning, vision and manipulation. Finally we depict an image of a prototype robot system for nuclear power plants based on the advanced functions. (author) 64 refs

  15. Does zero really mean nothing?-first experiences with the new PowerQuant(TM) system in comparison to established real-time quantification kits.

    Science.gov (United States)

    Poetsch, Micaela; Konrad, Helen; Helmus, Janine; Bajanowski, Thomas; von Wurmb-Schwark, Nicole

    2016-07-01

    DNA quantification is an important step in the molecular genetic analysis of a forensic sample, hopefully providing reliable data on DNA content for a subsequent generation of reproducible STR profiles for identification. For several years, this quantification has usually been done by real-time PCR protocols and meanwhile a variety of assays are commercially available from different companies. The newest one is the PowerQuant(TM) assay by Promega Inc. which is advertised with the promise that a determined DNA concentration of 0 ng/μl in a forensic sample guarantees the impossibility to achieve true STR results, thus allowing to exclude such samples from STR analysis to save time and money. Thus, the goal of this study was to thoroughly verify the quantification step with regard to its suitability as a screening method. We have evaluated the precision and reliability of four different real-time PCR quantification assays by systematically testing DNA dilutions and forensic samples with various DNA contents. Subsequently, each sample was subjected to the Powerplex® ESX 17 fast kit to determine a reliable cutoff level for exclusion of definitely negative samples from STR analysis. An accurate quantification of different cell line DNA dilutions was not possible with any kit. However, at least the PowerQuant(TM) assay provided suitable data analyzing forensic samples, whereas in other systems up to 46 % of negative samples still displayed reliable STR analysis results. All in all, the PowerQuant(TM) assay represents a big step forward, but the evaluation of real-time PCR quantification results has still to be done with great care. PMID:26972802

  16. A general evaluation of poisoning cases occured from 1990 to 1996in Şanlıurfa

    OpenAIRE

    OCAK, Dr. Seyfullah O. ARSLAN Dr. Mustafa KÖSE

    1998-01-01

    The aim of this study is to evaluate the causes and the results of acute poisoning cases occurred in Şanlıurfa. Record books of emergency departments of State and Children Hospital from 1990 to 1996 in Şanlı/ifa were retrospectively investigated. Acute poisoning cases were evaluated with regard to sex, age, poisoning causes and results. Of total 2379 poisoning cases, 818 (34.4 %) were in childhood and 1561 (65.6 %) were in adolescents. The incidence of acute poisoning cases was 0.97 %. The mo...

  17. Building and Researching the Bidding Model Based on the Cost of Power Plant

    Institute of Scientific and Technical Information of China (English)

    秦春申; 叶春; 赵景峰

    2004-01-01

    A bidding model of neural network was presented to pursue the largest benefit according to the policy of separating power plants from network and bidding transaction. This model bases on the cost of power plant and its research object is a power plant in the market. The market clearing price (MCP) can be predicted and an optimized load curve can be decided in this model. The model may provide technical support for the power plant.

  18. Materials for advanced power engineering 2010. Proceedings

    International Nuclear Information System (INIS)

    The 9th Liege Conference on ''Materials for Advanced Power Engineering'' presents the results of the materials related COST Actions 536 ''Alloy Development for Critical Components of Environmentally Friendly Power Plants'' and 538 ''High Temperature Plant Lifetime Extension''. In addition, the broad field of current materials research perspectives for high efficiency, low- and zero- emission power plants and new energy technologies for the next decades are reported. The Conference proceedings are structured as follows: 1. Materials for advanced steam power plants; 2. Gas turbine materials; 3. Materials for nuclear fission and fusion; 4. Solid oxide fuel cells; 5. Corrosion, thermomechanical fatigue and modelling; 6. Zero emission power plants.

  19. AP1000® PWR reactor physics analysis with VERA-CS and KENO-VI. Part 1. Zero power physics tests

    International Nuclear Information System (INIS)

    Westinghouse has applied the Core Simulator of the Virtual Environment for Reactor Applications, VERA-CS, under development by the Consortium for Advanced Simulation of LWRs (CASL) to the core physics analysis of the AP1000® PWR. The AP1000 PWR features and advanced first core with radial and axial heterogeneities, including enrichment zoning, multiple burnable absorbers, and a combination of light and heavy control banks to enable the MSHIMTM advanced operational strategy. These advanced features make application of VERA-CS to the AP1000 PWR first core especially relevant to qualify VERA performance. A companion paper at this conference describes the power distribution analysis of the AP1000 PWR with VERA-CS and the KENO Monte-Carlo code. This paper describes the results obtained for the startup physics tests simulations of the AP1000 PWR first core (critical boron, rod worth and reactivity coefficients), supporting the excellent numerical agreement reported in the companion paper for the power distribution. (author)

  20. Understanding Net Zero Energy Buildings

    DEFF Research Database (Denmark)

    Salom, Jaume; Widén, Joakim; Candanedo, José;

    2011-01-01

    Although several alternative definitions exist, a Net-Zero Energy Building (Net ZEB) can be succinctly described as a grid-connected building that generates as much energy as it uses over a year. The “net-zero” balance is attained by applying energy conservation and efficiency measures and by...... incorporating renewable energy systems. While based on annual balances, a complete description of a Net ZEB requires examining the system at smaller time-scales. This assessment should address: (a) the relationship between power generation and building loads and (b) the resulting interaction with the power grid....... This paper presents and categorizes quantitative indicators suitable to describe both aspects of the building’s performance. These indicators, named LMGI - Load Matching and Grid Interaction indicators, are easily quantifiable and could complement the output variables of existing building simulation...

  1. ALICE Zero Degree Calorimeter

    CERN Multimedia

    De Marco, N

    2013-01-01

    Two identical sets of calorimeters are located on both sides with respect to the beam Interaction Point (IP), 112.5 m away from it. Each set of detectors consists of a neutron (ZN) and a proton (ZP) Zero Degree Calorimeter (ZDC), positioned on remotely controlled platforms. The ZN is placed at zero degree with respect to the LHC beam axis, between the two beam pipes, while the ZP is positioned externally to the outgoing beam pipe. The spectator protons are separated from the ion beams by means of the dipole magnet D1.

  2. Fossil fuel power plant combustion control: Research in Italy

    International Nuclear Information System (INIS)

    Electric power demand forecasts for Italy to the year 2000 indicate an increase of about 50% which, due to the current moratorium on nuclear energy, should be met entirely by fossil fuel power plants. Now, there is growing public concern about possible negative health impacts due to the air pollution produced through the combustion of fossil fuels. In response to these concerns, ENEL (Italian National Electricity Board) is investing heavily in air pollution abatement technology R ampersand D. The first phase involves the investigation of pollution mechanisms in order to develop suitable mathematical models and diagnostic techniques. The validity of the models is being tested through through measurements made by sophisticated instrumentation placed directly inside the combustion chambers of steam generator systems. These are allowing engineers to develop improved combustion control methods designed to reduce air pollution at source

  3. A Reduced Wind Power Grid Model for Research and Education

    Energy Technology Data Exchange (ETDEWEB)

    Akhmatov, V. [Energinet.dk, Fjordvejen 1-11, DK-7000 Fredericia (Denmark); Lund, T.; Hansen, A.D.; Sorensen, P.E. [Risoe National Laboratory, DK-4000 Roskilde (Denmark); Nielsen, A.H. [Centre for Electric Technology, Technical University of Denmark, DK-2800 Kgs. Lyngby (Denmark)

    2006-07-01

    A reduced grid model of a transmission system with a number of central power plants, consumption centers, local wind turbines and a large offshore wind farm is developed and implemented in the simulation tool PowerFactory (DIgSILENT). The reduced grid model is given by Energinet.dk, Transmission System Operator of Denmark (TSO) for Natural Gas and Electricity, to the Danish Universities and the Risoe National Laboratory. Its intended usage is education and studying of interaction between electricity-producing wind turbines and a realistic transmission system. Focus in these studies is on voltage stability issues and on the ride-through capability of different wind turbine concepts, equipped with advanced controllers, developed by the Risoe National Laboratory.

  4. Research on the Countermeasures against Electromagnetic Interface in Power Systems

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Won Bin; Kang, Young Suk; Choi, Hyo Yul; Cha, Ok Hyun [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Lee, Gi Chul; Le, Jae Bok; Ha, Tae Hyun; Kim, Suk Joo; Na, Dae Yul; Kim, Yong Ho; Jeong, Kyo Beom [Korea Electrotechnology Research Institute, Changwon (Korea, Republic of)

    1996-12-31

    As the results of widespread use of microelectronics in electric power system, electric environment of power operation facilities in substation has become more weak and severe for surge voltages. Electromagnetic coupled overvoltage caused by HV bus switching operating lead to the malfunction or destruction of low voltage control circuit which mostly used signal. To scope with this transients overvoltage, it is necessary to be investigated transient source and propagation path and analysed its effects to low voltage circuit such as relay. This study is to analysis source of conducted EMP(electromagnetic pulse) on the low voltage control circuit and to acquits transient voltage waveforms, and to provide countermeasures against transient voltage, and EMP filtering method according to each EMP each type. With this, gradual improvement of EMI countermeasure will be achieved. (author). 49 refs., figs.

  5. Nuclear power and the public: analysis of collected survey research

    International Nuclear Information System (INIS)

    This executive summary highlights the major findings of a comprehensive synthesis and analysis of over 100 existing surveys dealing with public attitudes toward nuclear power issues. Questions of immediate policy relevance to the nuclear debate are posed and answered on the basis of these major findings. For each issue area, those sections of the report in which more-detailed discussion and presentation of relevant data may be found are indicated

  6. Nuclear power and the public: analysis of collected survey research

    Energy Technology Data Exchange (ETDEWEB)

    Melber, B.D.; Nealey, S.M.; Hammersla, J.; Rankin, W.L.

    1977-11-01

    This executive summary highlights the major findings of a comprehensive synthesis and analysis of over 100 existing surveys dealing with public attitudes toward nuclear power issues. Questions of immediate policy relevance to the nuclear debate are posed and answered on the basis of these major findings. For each issue area, those sections of the report in which more-detailed discussion and presentation of relevant data may be found are indicated.

  7. Reflexively exploring knowledge and power in collaborative research

    DEFF Research Database (Denmark)

    Olesen, Birgitte Ravn; Pedersen, Chistina Hee; Frølunde, Lisbeth; Phillips, Louise Jane; Nordentoft, Helle Merete

    processes of mutual learning. There are also tensions between processes of opening up for a plurality of knowledges and processes of closure in order to achieve strategic ends in the form of some kind of outcome. The basic premise underpinning this workshop is that we as researchers can best deal with the......The proposed workshop will take its starting point in the challenges which collaborative research practices share. The aim of the workshop is to work with, and further develop, a range of critical, reflexive strategies for understanding, analysing and dealing with those challenges. The workshop...... complexities and tensions of collaborative research through reflexive analyses of how “dialogue” and “participation” are played out concretely in collaborative research practices. Therefore, the workshop will be designed as a forum in which we go into depth with the different problems, dilemmas, ambivalences...

  8. Downstream Research Joint Venture with Upstream Market Power

    OpenAIRE

    Constantine Manasakis; Emmanuel Petrakis; Vasileios Zikos

    2014-01-01

    In a vertically related industry, we examine the downstream firms' incentives to invest in cost-reducing Research and Development (R&D), and to form a Research Joint Venture (RJV), under two alternative structures of input supply: exclusive vertical relations and a single supplier. In contrast to the “hold-up” argument, in which downstream firms invest non-cooperatively and spillovers are low, R&D investments are higher under a single supplier than under competing vertical chains. Downstream ...

  9. Human factors in maintenance: Development and research in Swedish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Salo, I. [Lund Univ. (Sweden). Dept. of Psychology; Svensson, Ola [Stockholm Univ. (Sweden). Dept. of Psychology

    2001-11-01

    The present report investigated previously completed, ongoing, and planned research and development projects focusing human factors and maintenance work carried out at Swedish nuclear power plants and SKI. In addition, needs for future research and development works were also investigated. Participants from all nuclear power plants and SKI were included in the study. Participants responded to a set of questions in an interview. The interviews also generated a list of future research and development projects.

  10. Human factors in maintenance: Development and research in Swedish nuclear power plants

    International Nuclear Information System (INIS)

    The present report investigated previously completed, ongoing, and planned research and development projects focusing human factors and maintenance work carried out at Swedish nuclear power plants and SKI. In addition, needs for future research and development works were also investigated. Participants from all nuclear power plants and SKI were included in the study. Participants responded to a set of questions in an interview. The interviews also generated a list of future research and development projects

  11. Human factors in maintenance: development and research in Swedish nuclear power plants

    International Nuclear Information System (INIS)

    The report investigated previously completed, ongoing, and planned research and development projects focusing human factors and maintenance work carried out at Swedish nuclear power plants and SKI. In addition, needs for future research and development works were also investigated. Participants from all nuclear power plants and SKI were included in the study. Participants responded to a set of questions in an interview. The interviews also generated a list of future research and development projects. (au)

  12. European research and development strategy for clean power

    International Nuclear Information System (INIS)

    We need more rather than less money for research, energy research in particular, research being an important contributor to progress, in order to achieve peak performance, comply with the quest for knowledge about the structure of the world, or to be able to further improve our quality of life at far less expense of materials and energy. This latter concept is in line with European identity. If we succeed in demonstrating to the world that people can live a better life if they manage their affairs sustainably, we Europeans will have won a new trademark: a sustainable Europe which can be left to future generations. For this purpose Europeans, more than before, must perceive Europe as a space of knowledge. Science policy must be geared to Europe, not just to a national territory. Also, Europe should devote more attention to fundamental research. Some outstanding projects are needed, particularly in energy research, with the participation of industry in order to reduce materials consumption and avoid emissions. Education, too, must be given much attention. In the absence of enthusiastic young scientists, engineers, and skilled workers who know their neighboring countries and their technologies and languages from an early age, European energy policy is bound to remain fragmented. (orig.)

  13. Zero Base Budgeting.

    Science.gov (United States)

    Sarndal, Anne G.

    1979-01-01

    Traditional budgeting starts with the previous year's budget, but zero base budgeting demands that each activity be justified from "scratch," and establishes a number of increments for each unit, in order of priority. Given the set of increments and the money available, management can determine what activities to finance. (Author)

  14. Zero-leak valve

    Science.gov (United States)

    Macglashan, W. F., Jr.

    1980-01-01

    Zero-leakage valve has fluid-sealing diaphragm support and flat sievelike sealing surface. Diaphragm-support valve is easy to fabricate and requires minimum maintenance. Potential applications include isolation valve for waste systems and remote air-actuated valve. Device is also useful in controlling flow of liquid fluorine and corrosive fluids at high pressures.

  15. Parrot "Understands" Zero

    Science.gov (United States)

    Journal of College Science Teaching, 2005

    2005-01-01

    The walnut sized brain of the African grey parrot may actually be capable of comprehending abstract mathematical concepts. The bird seems to understand a numerical concept akin to zero--an abstract notion that humans don't typically understand until they are three or four years old. Alex, the 28-year-old parrot who lives in a Brandeis University…

  16. Echoes at Ground Zero

    Science.gov (United States)

    Chronicle of Higher Education, 2006

    2006-01-01

    An excerpt from the opening piece in "Everything That Rises: A Book of Convergences" by Lawrence Weschler is presented where the author is talking with Joel Meyerowitz, the only photographer granted unimpeded access to the clean-up operations at ground zero after the terrorist attacks of September 11, 2001. The two discuss the parallels between…

  17. Shadow of ground zero

    Energy Technology Data Exchange (ETDEWEB)

    Haaland, C.M.

    1984-01-01

    The history of the development of nuclear weapons starting with the detonation of the A-bombs on Japan is reviewed. An overview of nuclear weapon effects is presented. The effects of electromagnetic pulse (EMP), initial nuclear radiation, thermal radiation and blast are discussed with reference to how people outside can survive when ground zero is only a few miles away. 8 references. (ACR)

  18. ANL Technical Support Program for DOE Environmental Restoration and Waste Management

    International Nuclear Information System (INIS)

    This report provides an overview of progress during FY 1991 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE, Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defenses Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are likely to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: (1) to review and evaluate available information on parameters that will be important in establishing the long-term performance of glass in a repository environment; (2) to perform testing to further quantify the effects of important variables where there are deficiencies in the available data; and (3) to initiate long-term testing that will bound glass performance under a range of conditions applicable to repository disposal

  19. Revised ANL-reported tensile data for V-Ti and V-Cr-Ti alloys

    Energy Technology Data Exchange (ETDEWEB)

    Billone, M.C. [Argonne National Lab., IL (United States)

    1997-08-01

    The tensile for all irradiated vanadium alloy samples and several unirradiated vanadium alloys tested at Argonne National Laboratory (ANL) have been critically reviewed and revised, as necessary. The review and revision are based on re-analyzing the original load-displacement strip-chart recording using a methodology consistent with current ASTM standards. No significant difference has been found between the newly-revised and previously-reported values of yield strength (YS) and ultimate tensile strength (UTS). However, by correctly subtracting the non-gauge-length displacement and linear gauge-length displacement from the total cross-head displacement, the uniform elongation (UE) of the gauge length decreases by 4-9% strain and the total elongation (TE) of the gauge length decreases by 1-7% strain. These differences are more significant for lower-ductility irradiated alloys than for higher-ductility alloys.

  20. Nuclear power plant safety research 1999-2002. A proposal for the content and organisation of the new research programme

    International Nuclear Information System (INIS)

    The Working Group was appointed by the Advisory Committee on Nuclear Energy to propose a framework scheme and possibly a new organization for the existing nuclear power plant safety research programme for the period 1999 to 2002. While planning the programme, account has been taken of the recent changes in the framework, the opportunity to participate in the research and development-programmes of the European Union in the first place. The principal aim of the national nuclear power plant safety research is to create the necessary conditions to ensure and even enhance the high safety level of the running nuclear power plants in Finland. In addition, the research programme should take care of the national know-how especially for the needs of the safety authorities and it should also maintain the capability for the research and development-needs in the case of new power plant projects. The dissemination of the results obtained in terms of the national research programme and via international cooperation as well as the education and training of the researchers are also part of the programme

  1. Nuclear power plant severe accident research plan. Revision 1

    International Nuclear Information System (INIS)

    Subsequent to the Three Mile Island Unit 2 accident, recommendations were made by a number of review committees to consider regulatory changes which would provide better protection of the public from severe accidents. Over the past six years a major research effort has been underway by the NRC to develop an improved understanding of severe accidents and to provide a technical basis to support regulatory decisions. The purpose of this report is to describe current plans for the completion and extension of this research in support of ongoing regulatory actions in this area

  2. Research Of The Efficiency Of The Wireless Power Transfer With The Employment Of DD Inductance Coils

    Directory of Open Access Journals (Sweden)

    Krainyukov Alexander

    2015-12-01

    Full Text Available The paper is devoted to using of DD inductance coils for the wireless power transfer. The aim of the given research is to determine influence of the parameters of resonance transformer on the efficiency of the wireless power transfer with the use of the DD inductance coils. Experimental installation of the wireless power transfer by a resonance inductive method was constructed. Experiments were performed with it help. Research results show influence of the distance between the coils of inductance, of the resonance transformer frequency, of the storage source voltage and of the temperature conditions on the efficiency of the wireless power transfer.

  3. Research of on-line detection system for power capacitor

    Science.gov (United States)

    Yao, Junda; Qian, Zheng; Yu, Hao; Xia, Jiuyun

    2016-01-01

    The hidden danger exists in the power capacitor of power system due to long-time operation under the environment of high voltage. Thus, it is possible to induce serious fault, and the on-line detection system is urgently required. In this paper, two methods of the on-line detection system are compared in order to realize the better real-time condition detection. The first method is based on the STM microprocessor with an internal 12 bit A/D converter, which converts analog signals which is arrived from the sample circuit into digital signals, and then the FFT algorithm is used to accomplish the measurement of the voltage and current values of the capacitor. The second method is based on the special electric energy metering IC, which can obtain RMS (Root Mean Square) of voltage and current by processing the sampled data of the voltage and current, and store RMS of voltage and current in its certain registers. The operating condition of the capacitor can be obtained after getting the values of voltage and current. By comparing the measuring results of two methods, the second method could achieve a higher measurement accuracy and more simple construction.

  4. Rurality Research and Rural Education: Exploratory and Explanatory Power

    Science.gov (United States)

    Balfour, Robert J.

    2012-01-01

    This article presents analysed data from the first year of the Rural Teacher Education Project (RTEP 2007-2009) with a view to illustrating how a generative theory of rurality as education research was developed, and for which ends it might be utilised. The article suggests that data from projects in rural communities, which take the rural as…

  5. Propulsion Investigation for Zero and Near-Zero Emissions Aircraft

    Science.gov (United States)

    Snyder, Christopher A.; Berton, Jeffrey J.; Brown, Gerald v.; Dolce, James L.; Dravid, Marayan V.; Eichenberg, Dennis J.; Freeh, Joshua E.; Gallo, Christopher A.; Jones, Scott M.; Kundu, Krishna P.; Marek, Cecil J.; Millis, Marc G.; Murthy, Pappu L.; Roach, Timothy M.; Smith, Timothy D.; Stefko, George L.; Sullivan, Roy M.; Tornabene, Robert T.; Geiselhat, Karl A.; Kascak, Albert F.

    2009-01-01

    As world emissions are further scrutinized to identify areas for improvement, aviation s contribution to the problem can no longer be ignored. Previous studies for zero or near-zero emissions aircraft suggest aircraft and propulsion system sizes that would perform propulsion system and subsystems layout and propellant tankage analyses to verify the weight-scaling relationships. These efforts could be used to identify and guide subsequent work on systems and subsystems to achieve viable aircraft system emissions goals. Previous work quickly focused these efforts on propulsion systems for 70- and 100-passenger aircraft. Propulsion systems modeled included hydrogen-fueled gas turbines and fuel cells; some preliminary estimates combined these two systems. Hydrogen gas-turbine engines, with advanced combustor technology, could realize significant reductions in nitrogen emissions. Hydrogen fuel cell propulsion systems were further laid out, and more detailed analysis identified systems needed and weight goals for a viable overall system weight. Results show significant, necessary reductions in overall weight, predominantly on the fuel cell stack, and power management and distribution subsystems to achieve reasonable overall aircraft sizes and weights. Preliminary conceptual analyses for a combination of gas-turbine and fuel cell systems were also performed, and further studies were recommended. Using gas-turbine engines combined with fuel cell systems can reduce the fuel cell propulsion system weight, but at higher fuel usage than using the fuel cell only.

  6. A review of ANL base technology studies in support of the U.S. LMFBR vibration program

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) is the center for base technology studies of flow induced vibration for the U.S. LMFBR Program. This paper reviews and summarizes published results, reports on the status of ongoing programs, and discusses future needs as outlined in the U.S. LMFBR Vibrations Program Plan. (author)

  7. A new digital pulse power supply in heavy ion research facility in Lanzhou

    Science.gov (United States)

    Wang, Rongkun; Chen, Youxin; Huang, Yuzhen; Gao, Daqing; Zhou, Zhongzu; Yan, Huaihai; Zhao, Jiang; Shi, Chunfeng; Wu, Fengjun; Yan, Hongbin; Xia, Jiawen; Yuan, Youjin

    2013-11-01

    To meet the increasing requirements of the Heavy Ion Research Facility in Lanzhou-Cooler Storage Ring (HIRFL-CSR), a new digital pulse power supply, which employs multi-level converter, was designed. This power supply was applied with a multi H-bridge converters series-parallel connection topology. A new control model named digital power supply regulator system (DPSRS) was proposed, and a pulse power supply prototype based on DPSRS has been built and tested. The experimental results indicate that tracking error and ripple current meet the requirements of this design. The achievement of prototype provides a perfect model for HIRFL-CSR power supply system.

  8. Research and Design Problems Introduced by Increased Power Output

    Science.gov (United States)

    Kurtz, Oskar

    1937-01-01

    In what follows the question of the number and geometrical arrangement of the cylinders so important in the design of high performance power units will be considered from various points of view. A discussion will be given of the possibilities of the various working processes and an investigation will be made of possible means for improving the continuous operation and take-off performance, particularly the methods of supercharging, increasing the r.p.m., and employing the two-stroke-cycle engine. Finally, the question of lowered fuel consumption will be gone over briefly. The subject will be treated under four headings: I) Considerations on the engine layout; II) Increase in output per given swept volume; III) Improvement in the take-off performance; IV) Lowering of the fuel consumption.

  9. Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX

    International Nuclear Information System (INIS)

    Highlights: ► We model the BFS-62-3A experiment with the MCNPX code and four nuclear libraries. ► We show the impact on reactivity of heterogeneous structures in the reactor. ► We model experimental uncertainties, e.g. in materials dimension and density. ► The model agrees with experiments on k-eff, CR worth, Na voids and fission rates. ► The analysis questions experimental data measured in the reflector region. - Abstract: A 3D full-core heterogeneous model of the BFS-62-3A critical benchmark experiment was developed and validated using the Monte Carlo MCNPX-2.4.0 code. The BFS-2 critical facility at the Institute of Physics and Power Engineering (IPPE) was designed for simulation of fast reactor core neutronics, and for the validation of codes and nuclear data. The BFS-62-3A critical benchmark experiment was set-up as a mock-up of the BN-600 reactor core with (U, Pu) O2 fuel of 17% Pu content and stainless-steel reflectors. It was operated to measure the effective multiplication factor, spectral indices, radial fission rate distributions, control rod worths and sodium void effects. In the present study, special care was taken to run the MCNPX model to make Monte-Carlo confidence intervals comparable with uncertainties reported in the experiments; such as in material dimensions, number densities and isotopic compositions. In addition to the effective multiplication factor, sodium void effect, fission rate distributions and control rod worth were calculated. Simulations were carried out with four different modern nuclear data libraries; the primary aim being to estimate sensitivity of the results to the nuclear data. This task, besides being a library comparison, is also meant as a first step towards a code-to-code verification with deterministic methods. Results agree well with experimental values on most of the nuclear characteristics, even though a discrepancy up to more than 20% was found on the flux distribution in the stainless-steel reflector

  10. High peak power Nd:glass lasers for fusion research

    International Nuclear Information System (INIS)

    This paper briefly reviews the basics of fusion and some of the major problems associated with building a 4 arms 1 kJ, 1 ns Nd:glass laser chain currently under development at the Bhabha Atomic Research Centre(BARC), Bombay. With this laser, it is proposed to study the various laser plasma interaction processes and to obtain compression of glass micro balloon targets filled with DT gas. (author). 15 refs., 8 figs., 3 tabs

  11. Design & Implementation of Zero Voltage Switching Buck Converter

    OpenAIRE

    A.Suresh Kumar; P.Krishna Reddy

    2014-01-01

    Zero voltage switching (ZVS) buck converter is more preferable over hard switched buck converter for low power, high frequency DC-DC conversion applications. In Zero voltage switching converter, turn on & turn off of a switch occurs at zero voltage that results in lower switching losses. In this converter soft switching is achieved by using resonant components. The optimal values of resonant components are determined by using electric functions derived from circuit configurati...

  12. Photovoltaics. [research and development of terrestrial electric power systems

    Science.gov (United States)

    Smith, J. L.

    1981-01-01

    The federal government has sponsored a program of research and development on terrestrial photovoltaic systems that is designed to reduce the costs of such systems through technological advances. There are many potential paths to lower system costs, and successful developments have led to increased private investment in photovoltaics. The prices for photovoltaic collectors and systems that appear to be achievable within this decade offer hope that the systems will soon be attractive in utility applications within the United States. Most of the advances achieved will also be directly applicable to the remote markets in which photovoltaic systems are now commercially successful

  13. Net Zero Energy Buildings

    DEFF Research Database (Denmark)

    Marszal, Anna Joanna; Bourrelle, Julien S.; Musall, Eike;

    2010-01-01

    The international cooperation project IEA SHC Task 40 / ECBCS Annex 52 “Towards Net Zero Energy Solar Buildings”, attempts to develop a common understanding and to set up the basis for an international definition framework of Net Zero Energy Buildings (Net ZEBs). The understanding of such buildings...... and how the Net ZEB status should be calculated differs in most countries. This paper presents an overview of Net ZEBs energy calculation methodologies proposed by organisations representing eight different countries: Austria, Canada, Denmark, Germany, Italy, Norway, Switzerland and the USA. The...... different parameters used in the calculations are discussed and the various renewable supply options considered in the methodologies are summarised graphically. Thus, the paper helps to understand different existing approaches to calculate energy balance in Net ZEBs, highlights the importance of variables...

  14. Zero leakage sealings

    Science.gov (United States)

    Kotesovec, Bernhard; Steinrück, Herbert

    2010-11-01

    The piston rod of a reciprocating compressor is sealed with elastic cylindrical sealing elements. Across the sealings the pressure drops from the operating pressure to the ambient pressure. The lubrication gap between the elastic sealing and reciprocating piston rod is studied with the aim to find conditions of a leakage free sealing. The flow in the lubrication gap and the elastic deformation of the sealing are determined simultaneously. The net-flow during one cycle of the reciprocating piston rod is calculated. It turns out that maintaining zero leakage is very sensible. Indeed the outbound flow during out-stroke has to be equal the inbound flow during the in-stroke. By prescribing a special shape of the undeformed sealing zero leakage can be attained - at least theoretically for certain operating conditions. It turns out that temperature dependent material data and a model for cavitation is necessary. The model, its numerical implementation and results will be discussed.

  15. Research into pulsed power-driven recombination lasers

    International Nuclear Information System (INIS)

    The DNA/PITHON pulsed power generator was used to produce hot, dense, aluminum, and neon plasmas in a Z-pinch configuration. An annulus of neon gas was radially imploded onto a parylene capillary on axis which was coated with aluminum. The pinch produced 3 cm and 5 cm long Al/Ne plasmas with densities --10/sup 20/ cm/sup -3/ and temperatures --500 eV. A time-gated, grazing incidence spectrograph (MCPIGS) was used to image the plasma and to capture three consecutive 25 ns duration spectra. The Al XI, 4f-3d and 4-d-3p lines at 154.4 and 150.4A were observed to be anomalously bright compared to the Al XI, 4d-2p line. This anomaly, which might be suggestive of recombination lasing, may also be explained by opacity, whereby the optically thick 4 → 2 lines are reduced in apparent intensity with respect ot the 4 → 3 lines. The Ne X 4-3 line was observed to be spatially localized on axis where emissions from the Ne X 3-2 line were sharply reduced in intensity. On axis, the anomalous brightness of the Ne X 4-3 line suggests a strong inversion. The interpretation of these Ne lines should not be strongly affected by opacity considerations and is suggestive of inversions in Ne X on axis

  16. Decoherence at zero temperature

    International Nuclear Information System (INIS)

    Most discussions of decoherence in the literature consider the high temperature regime but it is also known that, in the presence of dissipation, decoherence can occur even at zero temperature. Whereas most previous investigations all assumed initial decoupling of the quantum system and bath, we consider that the system and environment are entangled at all times. Here, we discuss decoherence for a free particle in an initial Schroedinger cat state. Memory effects are incorporated by use of the single relaxation time model

  17. Zero energy reactor 'RB'

    International Nuclear Information System (INIS)

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  18. Power Matters: Foucault's "Pouvoir/Savoir" as a Conceptual Lens in Information Research and Practice

    Science.gov (United States)

    Olsson, Michael; Heizmann, Helena

    2015-01-01

    Introduction: This paper advocates Foucault's notion of pouvoir/savoir (power/knowledge) as a conceptual lens that information researchers might fruitfully use to develop a richer understanding of the relationship between knowledge and power. Methods: Three of the authors' earlier studies are employed to illustrate the use of this conceptual lens.…

  19. A critical discussion of null hypothesis significance testing and statistical power analysis within psychological research

    DEFF Research Database (Denmark)

    Jones, Allan; Sommerlund, Bo

    2007-01-01

    The uses of null hypothesis significance testing (NHST) and statistical power analysis within psychological research are critically discussed. The article looks at the problems of relying solely on NHST when dealing with small and large sample sizes. The use of power-analysis in estimating the...

  20. Got Power? A Systematic Review of Sample Size Adequacy in Health Professions Education Research

    Science.gov (United States)

    Cook, David A.; Hatala, Rose

    2015-01-01

    Many education research studies employ small samples, which in turn lowers statistical power. We re-analyzed the results of a meta-analysis of simulation-based education to determine study power across a range of effect sizes, and the smallest effect that could be plausibly excluded. We systematically searched multiple databases through May 2011,…

  1. Exploring the Educative Power of an Experienced Mathematics Teacher Educator-Researcher

    Science.gov (United States)

    Yang, Kai-Lin; Hsu, Hui-Yu; Lin, Fou-Lai; Chen, Jian-Cheng; Cheng, Ying-Hao

    2015-01-01

    This paper aims to explore the educative power of an experienced mathematics teacher educator-researcher (MTE-R) who displayed his insights and strategies in teacher professional development (TPD) programs. To this end, we propose a framework by first conceptualizing educative power based on three constructs--communication, reasoning, and…

  2. CFD research on runaway transient of pumped storage power station caused by pumping power failure

    International Nuclear Information System (INIS)

    To study runaway transient of pumped storage power station caused by pumping power failure, three dimensional unsteady numerical simulations were executed on geometrical model of the whole flow system. Through numerical calculation, the changeable flow configuration and variation law of some parameters such as unit rotate speed,flow rate and static pressure of measurement points were obtained and compared with experimental data. Numerical results show that runaway speed agrees well with experimental date and its error was 3.7%. The unit undergoes pump condition, brake condition, turbine condition and runaway condition with flow characteristic changing violently. In runaway condition, static pressure in passage pulses very strongly which frequency is related to runaway speed

  3. CFD research on runaway transient of pumped storage power station caused by pumping power failure

    Science.gov (United States)

    Zhang, L. G.; Zhou, D. Q.

    2013-12-01

    To study runaway transient of pumped storage power station caused by pumping power failure, three dimensional unsteady numerical simulations were executed on geometrical model of the whole flow system. Through numerical calculation, the changeable flow configuration and variation law of some parameters such as unit rotate speed,flow rate and static pressure of measurement points were obtained and compared with experimental data. Numerical results show that runaway speed agrees well with experimental date and its error was 3.7%. The unit undergoes pump condition, brake condition, turbine condition and runaway condition with flow characteristic changing violently. In runaway condition, static pressure in passage pulses very strongly which frequency is related to runaway speed.

  4. A COMPREHENSIVE MODEL FOR THE POWER TRANSFORMER DIGITAL DIFFERENTIAL PROTECTION FUNCTIONING RESEARCH

    Directory of Open Access Journals (Sweden)

    Yu. V. Rumiantsev

    2016-01-01

    Full Text Available This article presents a comprehensive model for the two-winding power transformer digital differential protection functioning research. Considered comprehensive model is developed in MatLab-Simulink dynamic simulation environment with the help of SimPowerSystems component library and includes the following elements: power supply, three-phase power transformer, wye-connected current transformers and two-winding power transformer digital differential protection model. Each element of the presented model is described in the degree sufficient for its implementation in the dynamic simulation environment. Particular attention is paid to the digital signal processing principles and to the ways of differential and restraining currents forming of the considered comprehensive model main element – power transformer digital differential protection. With the help of this model the power transformer digital differential protection functioning was researched during internal and external faults: internal short-circuit, external short-circuit with and without current transformers saturation on the power transformer low-voltage side. Each experiment is illustrated with differential and restraining currents waveforms of the digital differential protection under research. Particular attention was paid to the digital protection functioning analysis during power transformer abnormal modes: overexcitation and inrush current condition. Typical current waveforms during these modes were showed and their harmonic content was investigated. The causes of these modes were analyzed in details. Digital differential protection blocking algorithms based on the harmonic content were considered. Drawbacks of theses algorithms were observed and the need of their further technical improvement was marked.

  5. Research Group Introduction : Power Electronics Laboratory, Dept. of Electrical, Electronics and Information Engineering, Nagaoka University of Technology

    Science.gov (United States)

    伊東, 淳一

    Our research focuses on power conversion and its control especially matrix converter, multi-level converter, DC-DC converter. Furthermore AC motor drives, wireless power transfer system, high frequency power circuit and new device technology.

  6. Commercial Research and Development: Power to Explore, Opportunities from Discovery

    Science.gov (United States)

    Casas, Joseph C.; Nall, Mark; Powers, C. Blake; Henderson, Robin N. (Technical Monitor)

    2002-01-01

    The technical and economic goals of commercial use of space are laudable, and are addressed as a high priority by almost every national space program and most major aerospace companies the world over. Yet, the focus of most organizational agendas and discussions tends to focus on one or two very narrow enabling aspects of this potentially large technological and economic opportunity. While government sponsored commercial launch activities and private space platforms are an integral part of efforts to leverage the commercial use of space, these activities are possibly one of the smallest parts of creating, a viable and sustainable market for the commercial use of space. Most of the current programs usually do not appropriately address some of the critical issues of the current, already interested, potential space user communities. Current programs place the focus of the majority of the user requirements on the vehicle payload weight and mass performance considerations as the primary payload economical factor in providing a commercial market with a stimulating price for gaining access to the space environment. The larger user challenges of transformation from Earth-based research and development approaches to space environment approaches are not addressed early enough in programs to impact the new business considerations of potential users. Currently, space-based research and development user activities require a large user investment in time, in development of new areas of support expertise, in development of new systems, in risk of schedule to completion, and in long term capital positioning. The larger opportunities for stimulating a strong market driven interest in commercial use of space that could result from the development of vehicle payload "leap ahead technologies" for users are being missed, and there is a real risk of limiting the potentially broader market base to support a more technologically advanced and economically lucrative outcome. A major driving

  7. A new digital pulse power supply in heavy ion research facility in Lanzhou

    International Nuclear Information System (INIS)

    To meet the increasing requirements of the Heavy Ion Research Facility in Lanzhou-Cooler Storage Ring (HIRFL-CSR), a new digital pulse power supply, which employs multi-level converter, was designed. This power supply was applied with a multi H-bridge converters series-parallel connection topology. A new control model named digital power supply regulator system (DPSRS) was proposed, and a pulse power supply prototype based on DPSRS has been built and tested. The experimental results indicate that tracking error and ripple current meet the requirements of this design. The achievement of prototype provides a perfect model for HIRFL-CSR power supply system. -- Highlights: • The converters topology of series-parallel connection improves the power supply's performance. • The SOPC based on dual Nios II processors improves the real-time performance of system. • Pulse mode is implemented in digital power supply based on FPGA, with a smaller tracking error

  8. Research on the characteristics of the vanadium redox-flow battery in power systems applications

    Science.gov (United States)

    Jizhong, Chen; Ziqiang, Xu; Bei, Li

    2013-11-01

    Vanadium redox flow batteries (VRFBs) have power rating and energy durations that are independent of one another, which make them attractive for power systems applications. This paper focuses on the energy and power response capability of the VRFBs, which has been experimentally researched based on 5 kW/10 kWh and 0.5 MW/1 MWh systems. With three experimental operating modes, three threshold values and one baseline have been obtained based on the experimental results. The maximum state of charge (“SOC”), charged by 1.4 times rated power at 1 time ratio (“TR”), is 47% SOC. The minimum TR, charged by times rated power at SOC = 100%, is 1.5. The maximum charge/discharge power rating is 1.35 times rated power. The reserve SOC curves are a baseline on which the VRFB can respond to equally charge/discharge energy demand.

  9. A new digital pulse power supply in heavy ion research facility in Lanzhou

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Rongkun, E-mail: wangrongkun@impcas.ac.cn [Institute of Modern Physics, Lanzhou, 730000 (China); University of Chinese Academy of Sciences, Beijing 100049 (China); Chen, Youxin; Huang, Yuzhen; Gao, Daqing; Zhou, Zhongzu; Yan, Huaihai [Institute of Modern Physics, Lanzhou, 730000 (China); Zhao, Jiang; Shi, Chunfeng; Wu, Fengjun [Institute of Modern Physics, Lanzhou, 730000 (China); University of Chinese Academy of Sciences, Beijing 100049 (China); Yan, Hongbin; Xia, Jiawen; Yuan, Youjin [Institute of Modern Physics, Lanzhou, 730000 (China)

    2013-11-01

    To meet the increasing requirements of the Heavy Ion Research Facility in Lanzhou-Cooler Storage Ring (HIRFL-CSR), a new digital pulse power supply, which employs multi-level converter, was designed. This power supply was applied with a multi H-bridge converters series-parallel connection topology. A new control model named digital power supply regulator system (DPSRS) was proposed, and a pulse power supply prototype based on DPSRS has been built and tested. The experimental results indicate that tracking error and ripple current meet the requirements of this design. The achievement of prototype provides a perfect model for HIRFL-CSR power supply system. -- Highlights: • The converters topology of series-parallel connection improves the power supply's performance. • The SOPC based on dual Nios II processors improves the real-time performance of system. • Pulse mode is implemented in digital power supply based on FPGA, with a smaller tracking error.

  10. IPPE critical facilities and their research programs

    International Nuclear Information System (INIS)

    The 40th anniversary of BFS zero power fast critical facilities family took place in 2001. An extensive neutron physics research program for justification of fast sodium-cooled reactors core physics has been carried out on them. Advanced reactors core physics research is fulfilled today to solve both traditional and non-traditional tasks of nuclear power industry

  11. A neutron tomography facility at a low power research reactor

    CERN Document Server

    Körner, S; Von Tobel, P; Rauch, H

    2001-01-01

    Neutron radiography (NR) provides a very efficient tool in the field of non-destructive testing as well as for many applications in fundamental research. A neutron beam penetrating a specimen is attenuated by the sample material and detected by a two-dimensional (2D) imaging device. The image contains information about materials and structure inside the sample because neutrons are attenuated according to the basic law of radiation attenuation. Contrary to X-rays, neutrons can be attenuated by some light materials, as for example, hydrogen and boron, but penetrate many heavy materials. Therefore, NR can yield important information not obtainable by more traditional methods. Nevertheless, there are many aspects of structure, both quantitative and qualitative, that are not accessible from 2D transmission images. Hence, there is an interest in three-dimensional neutron imaging. At the 250 kW TRIGA Mark II reactor of the Atominstitut in Austria a neutron tomography facility has been installed. The neutron flux at ...

  12. Rhetorical Strategies in Engineering Research Articles and Research Theses: Advanced Academic Literacy and Relations of Power

    Science.gov (United States)

    Koutsantoni, Dimitra

    2006-01-01

    Research articles and research theses constitute two key genres used by scientific communities for the dissemination and ratification of knowledge. Both genres are produced at advanced stages of individuals' enculturation in disciplinary communities present original research aim to persuade the academic community to accept new knowledge claims,…

  13. A neutron tomography facility at a low power research reactor

    Science.gov (United States)

    Koerner, S.; Schillinger, B.; Vontobel, P.; Rauch, H.

    2001-09-01

    Neutron radiography (NR) provides a very efficient tool in the field of non-destructive testing as well as for many applications in fundamental research. A neutron beam penetrating a specimen is attenuated by the sample material and detected by a two-dimensional (2D) imaging device. The image contains information about materials and structure inside the sample because neutrons are attenuated according to the basic law of radiation attenuation. Contrary to X-rays, neutrons can be attenuated by some light materials, as for example, hydrogen and boron, but penetrate many heavy materials. Therefore, NR can yield important information not obtainable by more traditional methods. Nevertheless, there are many aspects of structure, both quantitative and qualitative, that are not accessible from 2D transmission images. Hence, there is an interest in three-dimensional neutron imaging. At the 250 kW TRIGA Mark II reactor of the Atominstitut in Austria a neutron tomography facility has been installed. The neutron flux at this beam position is 1.3×10 5 neutrons/cm 2 s and the beam diameter is 8 cm. For a 3D tomographic reconstruction of the sample interior, transmission images of the object taken from different view angles are required. Therefore, a rotary table driven by a step motor connected to a computerized motion control system has been installed at the sample position. In parallel a suitable electronic imaging device based on a neutron sensitive scintillator screen and a CCD-camera has been designed. It can be controlled by a computer in order to synchronize the software of the detector and of the rotary table with the aim of an automation of measurements. Reasonable exposure times can get as low as 20 s per image. This means that a complete tomography of a sample can be performed within one working day. Calculation of the 3D voxel array is made by using the filtered backprojection algorithm.

  14. A neutron tomography facility at a low power research reactor

    International Nuclear Information System (INIS)

    Neutron radiography (NR) provides a very efficient tool in the field of non-destructive testing as well as for many applications in fundamental research. A neutron beam penetrating a specimen is attenuated by the sample material and detected by a two-dimensional (2D) imaging device. The image contains information about materials and structure inside the sample because neutrons are attenuated according to the basic law of radiation attenuation. Contrary to X-rays, neutrons can be attenuated by some light materials, as for example, hydrogen and boron, but penetrate many heavy materials. Therefore, NR can yield important information not obtainable by more traditional methods. Nevertheless, there are many aspects of structure, both quantitative and qualitative, that are not accessible from 2D transmission images. Hence, there is an interest in three-dimensional neutron imaging. At the 250 kW TRIGA Mark II reactor of the Atominstitut in Austria a neutron tomography facility has been installed. The neutron flux at this beam position is 1.3x105 neutrons/cm2 s and the beam diameter is 8 cm. For a 3D tomographic reconstruction of the sample interior, transmission images of the object taken from different view angles are required. Therefore, a rotary table driven by a step motor connected to a computerized motion control system has been installed at the sample position. In parallel a suitable electronic imaging device based on a neutron sensitive scintillator screen and a CCD-camera has been designed. It can be controlled by a computer in order to synchronize the software of the detector and of the rotary table with the aim of an automation of measurements. Reasonable exposure times can get as low as 20 s per image. This means that a complete tomography of a sample can be performed within one working day. Calculation of the 3D voxel array is made by using the filtered backprojection algorithm

  15. NASA satellite communications application research. Phase 2: Efficient high power, solid state amplifier for EFH communications

    Science.gov (United States)

    Benet, James

    1993-01-01

    The final report describes the work performed from 9 Jun. 1992 to 31 Jul. 1993 on the NASA Satellite Communications Application Research (SCAR) Phase 2 program, Efficient High Power, Solid State Amplifier for EHF Communications. The purpose of the program was to demonstrate the feasibility of high-efficiency, high-power, EHF solid state amplifiers that are smaller, lighter, more efficient, and less costly than existing traveling wave tube (TWT) amplifiers by combining the output power from up to several hundred solid state amplifiers using a unique orthomode spatial power combiner (OSPC).

  16. Design of a battery power supply for the electromagnetic gun experimental research facility

    International Nuclear Information System (INIS)

    A high power and high energy battery power supply is currently being designed to support electromagnetic (EM) launcher research at the Air Force Armament Laboratory, Eglin Air Force Base, Florida. The design goals for this system are to supply megawatts of pulsed power at high current levels for a five second period. This paper discusses the rationale which led to this system selection. The specific system design is also discussed along with the issues of safety, charging, diagnostics, control system configuration, power conditioning and the problem of high-current switching

  17. Study of UO/sub 2/ wafer fuel for very high-power research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hsieh, T.C.; Jankus, V.Z.; Rest, J.; Billone, M.C.

    1980-11-01

    The Reduced Enrichment Research and Test Reactor Program is aimed at reducing fuel enrichment to < 20% in those research and test reactors presently using highly enriched uranium fuel. UO/sub 2/ caramel fuel is one of the most promising new types of reduced-enrichment fuel for use in research reactors with very high power density. Parametric studies have been carried out to determine the maximum specific power attainable without significant fission-gas release for UO/sub 2/ wafers ranging from 0.75 to 1.50 mm in thickness. The results indicate that (1) all the fuel designs considered in this study are predicted not to fail under full-power operation up to a burnup of 1.09 x 10/sup 21/ fis/cm/sup 3/; (2) for all fuel designs, failure is predicted at approximately the same fuel centerline temperature for a given burnup; (3) the thinner the wafer, and wider the margin for fuel specific power between normal operation and increased-power operation leading to fuel failure; (4) increasing the coolant pressure in the reactor core could improve fuel performance by maintaining the fuel at a higher power level without failure for a given burnup; and (5) for a given power level, fuel failure will occur earlier at a higher cladding surface temperature and/or under power-cycling conditions. 12 figures, 7 tables.

  18. High power laser research and development at the Laboratory for Laser Energetics

    International Nuclear Information System (INIS)

    As part of its research mission - to investigate the interaction of intense radiation with matter - the Laboratory for Laser Energetics (LLE) of the University of Rochester is developing a number of high-peak power and high-average-power laser systems. In this paper we highlight some of the LLE work on solid-state laser research, development and applications. Specifically, we discuss the performance and operating characteristics of Omega, a twenty-four beam, 4000 Joule, Nd:glass laser system which is frequently tripled using the polarization mismatch scheme. We also discuss progress in efforts to develop high-average-power solid-state laser systems with active-mirror and slab geometries and to implement liquid-crystal devices in high-power Nd:glass lasers. Finally we present results from a program to develop a compact, ultrahigh-peak-power solid-state laser using the concept of frequency chirped pulse amplification

  19. Superfund record of decision (EPA Region 10): Idaho National Engineering Lab (USDOE) (ANL-W), Operable Unit 9-04, Idaho Falls, ID, September 29, 1998

    International Nuclear Information System (INIS)

    The Argonne National Laboratory-West (ANL-W) Waste Area Group 9 (WAG 9) is one of the ten Idaho National Engineering and Environmental Laboratory (INEEL) WAGs identified in the Federal Facility Agreement and Consent Order (FFA/CO). The eight affected areas at ANL-W include the Sanitary Sewage Lagoons (ANL-04), Industrial Waste Pond, Ditches A, Ditch B, (all from ANL-01), Main Cooling Tower Blowdown Ditch (ANL-01A), Interceptor Canal-Canal and-Mound (sub-portions of ANL-09), and the Industrial Waste Lift Station Discharge Ditch (ANL-35). The major components of the selected remedy for ANL-W are: Completion of phytoremediation workplan for the field-scale testing; Conducting a field-scale phytoremediation test of selected plant species at the sites that pose unacceptable risks; Determining the effectiveness and implementability of phytoremediation based on results of field-scale testing; Collecting soil and plant samples after a two-year field season to be used to determine the effectiveness of phytoremediation on the ANL-W soils; Harvesting, compacting, incinerating, and disposing of the above- and below-ground plant matter that will be sent to a permitted landfill; Continuing the planting, harvesting process for phytoremediation only if completion of the two-year field-scale testing is successful; Installing access restrictions consisting of fences, bird netting, and posting warning signs; Review of the remedy no less than every five years after the RAOs have been met until the year 2098; and Implementing DOE controls which limit residential land use for at least 100 years from now (2098)

  20. Incorporating the operation of a small research reactor facility to support a national nuclear power program

    International Nuclear Information System (INIS)

    A small research reactor similar to the Penn State Breazeale Nuclear Reactor, which is a 1 Megawatt TRIGA, can be invaluable in supporting a national nuclear power programme. The research reactor provides an operating reactor for training nuclear engineers, nuclear operators, and other nuclear specialists required to construct, operate, and maintain the nuclear power plant. When operation of the power plant begins, highly trained, well-qualified and competent personnel will be available to operate, supervise, and maintain a safe and efficient power plant operation. The paper describes the organization of a nuclear science centre as well as research reactor activities. An example of an actual two week training programme of an electric utility is included with a list of experiments and demonstrations. University projects and experiments using the reactor are listed. (author)

  1. Causality in Statistical Power: Isomorphic Properties of Measurement, Research Design, Effect Size, and Sample Size.

    Science.gov (United States)

    Heidel, R Eric

    2016-01-01

    Statistical power is the ability to detect a significant effect, given that the effect actually exists in a population. Like most statistical concepts, statistical power tends to induce cognitive dissonance in hepatology researchers. However, planning for statistical power by an a priori sample size calculation is of paramount importance when designing a research study. There are five specific empirical components that make up an a priori sample size calculation: the scale of measurement of the outcome, the research design, the magnitude of the effect size, the variance of the effect size, and the sample size. A framework grounded in the phenomenon of isomorphism, or interdependencies amongst different constructs with similar forms, will be presented to understand the isomorphic effects of decisions made on each of the five aforementioned components of statistical power. PMID:27073717

  2. Electric Power Infrastructure Reliability And Security Research And Development Initiative. Final report

    International Nuclear Information System (INIS)

    This is the final scientific/technical report for the Electric Power Infrastructure Reliability and Security R and D Initiative sponsored by the U.S. Department of Energy, Office of Electricity Delivery and Energy Reliability, under award number DE-FG02-05CH11292. This report covers results from the FSU-led, multi-institution effort conducted over the period 8/15/05 to 10/14/2007. Building upon existing infrastructure for power systems research, modeling, and simulation, the Center for Advanced Power Systems (CAPS) at Florida State University (FSU) is developing world-class programs in electric power systems research and education to support future electric power system needs and challenges. With U.S. Department of Energy Support, FSU CAPS has engaged in a multi-faceted effort to conduct basic and applied research towards understanding, developing, and deploying technologies and approaches that can lead to improved reliability and security of the North American electric power generation and delivery infrastructure. This wide-reaching project, through a number of carefully selected thrusts cutting across several research disciplines, set out to address key terrestrial electric utility power system issues and challenges. The challenges and the thrusts to address them were arrived at through analysis of a number of national reports and recommendations combined with input from an experienced multi-disciplined team of power systems research staff and faculty at FSU CAPS. The resulting project effort can be grouped into four major areas: - Power Systems and New Technology Insertion - Controls, Protection, and Security - Simulation Development - High Temperature Superconductivity (HTS)

  3. Unique Power Electronics and Drives Experimental Bench (PEDEB) to Facilitate Learning and Research

    Science.gov (United States)

    Anand, S.; Farswan, R. S.; Fernandes, B. G.

    2012-01-01

    Experimentation is important for learning and research in the field of power electronics and drives. However, a great deal of equipment is required to study the various topologies, controllers, and functionalities. Thus, the cost of establishing good laboratories and research centers is high. To address this problem, the authors have developed a…

  4. Research Design and the Predictive Power of Measures of Self-Efficacy

    Science.gov (United States)

    Moriarty, Beverley

    2014-01-01

    The purpose of this enquiry was to examine how research design impacts on the predictive power of measures of self-efficacy. Three cautions for designing research into self-efficacy drawn from the seminal work of Albert Bandura (1986) and a further caution proposed by the current author together form the analytical framework for this enquiry. For…

  5. Beyond "on" or "with": Questioning Power Dynamics and Knowledge Production in "Child-Oriented" Research Methodology

    Science.gov (United States)

    Hunleth, Jean

    2011-01-01

    By taking a reflexive approach to research methodology, this article contributes to discussions on power dynamics and knowledge production in the social studies of children. The author describes and analyzes three research methods that she used with children--drawing, child-led tape-recording and focus group discussions. These methods were carried…

  6. Development of a Publications and Conferences Data Base in the Mexican Electric Power Research Institute.

    Science.gov (United States)

    Ripoll, C. Lopez Cerdan; And Others

    This paper describes the development by the Mexican Electric Power Research Institute (Instituto de Investigaciones Electricas or IIE) over a 10-year period of a publications and conferences database (PCDB) of research and development output of the institute. The paper begins by listing the objectives of the database and describing data coverage…

  7. Zero energy house

    OpenAIRE

    Milián Martínez, Irene; Vink, Willem; Ortiz Braulio, Ruben

    2008-01-01

    The zero energy house project talks about sustainability. In general terms the house is designed to produce as much energy as it consume. If you take a look to the house its possible to find several systems that takes as much profit as possible to the renewable energies like photovoltaic electricity production, geothermal energy used to run a heat pump or a well thought isolated house. First of all it’s possible to find general information about the topics in house, to make people understa...

  8. Research and development efforts in the implementation of nuclear power programme in Indonesia

    International Nuclear Information System (INIS)

    Research and development efforts in the implementation of nuclear power programme in Indonesia are presented. According to Indonesia Law, the National Atomic Energy Agency (BATAN) is an official body which is reponsible for all aspects of nuclear development. In implementing the nuclear power, BATAN together with the State Electricity Corporation (PLN) have pioneered the introduction of nuclear power plant in Indonesia by carrying out various activities, studies, seminars, workshops and report writings. A nuclear power planning study was carried out jointly with the International Atomic Energy Agency. The feasibility studies were also carried out by NIRA, an Italian consultant firm in cooperation with BATAN and PLN. To improve research and development, BATAN has established 5 research nuclear centres which function as centres of basic and applied research, isotope and radiation application, standardization and calibration and uranium exploration. Nowadays BATAN is constructing a sophisticated and multidisciplinary complex at Serpong near Jakarta. It is hoped that the participation of the national industry can be synchronized to the construction of the first nuclear power in Indonesia. To endorse the movement towards the industrial and technological future, the National Centre for Research, Science and Technology (known as PUSPITEK) has been established. There will be 12 different laboratories providing facilities for research and development of all aspects of technology. For training manpower, BATAN has established the Education and Training Centre (PUSDIKLAT). BATAN has also collaborated with universities, such as Gadjahmada University in Yogyakarta, in establishing Nuclear Engineering Division in the School of Engineering. 6 refs, 3 figs

  9. Solar Power and Solar Fuels Synthesis Report. Technology, market and research activities 2006-2011

    Energy Technology Data Exchange (ETDEWEB)

    Ridell, Bengt; Nilsson, Ronny; Rehnlund, Bjoern [Grontmij, Stockholm (Sweden); Kasemo, Bengt [Chalmers Univ. of Technology, Goeteborg (Sweden)

    2012-11-01

    The objectives of the synthesis is to survey the situation and give an accumulated and concentrated knowledge about status, needs and opportunities for Swedish research and Swedish industry within the area of solar power and solar fuels, to be used for prioritisation of further efforts. The synthesis shall identify strengths and weaknesses in areas fundamental for development of solar power and solar fuels, focused on the development in Sweden, but in an international context. The synthesis shall also cover proposals for future Swedish research efforts and organisation of future Swedish research programs.

  10. National Nuclear Power Plant Safety Research 2003-2006. Proposal for the Content and Organisation of a New Research Programme

    International Nuclear Information System (INIS)

    A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating and supervisory organisations of the plants. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. The Steering Group to the Finnish Research Programme on Nuclear Power Plant Safety (FINNUS), which was launched upon the assignment of the Advisory Committee on Nuclear Energy, appointed in spring 2002 a group to plan the contents of the new programme. This report contains a proposal for the general outline of the programme, preliminarily entitled as SAFIR (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2003-2006, but it is based on safety challenges identified for a longer time span as well. The favourable decision-in-principle on a new nuclear power plant unit adopted by Parliament has also been taken into account in the plan. The safety challenges set by the existing plants and the new plant unit, as well as the ensuing research needs do, however, converge to a great extent. The construction of the new power plant unit will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The general plan aims to define the

  11. power quality study of the electrical system of the second research reactor of egypt

    International Nuclear Information System (INIS)

    identifying problems in an electrical network which may results in an extensive damage occur is advisable for any power system. monitoring of power quality is necessary for maintaining accurate operation of sensitive equipment, it also ensures that unnecessary for maintaining accurate operation of sensitive equipment, it also ensures that unnecessary energy losses in a power system are kept at a minimum which lead to more profits. with advanced in technology growing of industrial/commercial facilities in many region. power quality problems have been a major concern among engineers; particularly in an industrial environment, where there are many large-scale type of equipment.thus, it would be useful to monitor and analyze the power quality problems.determination of power quality requires the identification of any anomalous behavior on a power system, which adversely affects the normal operation of electrical or electronic equipment. the choice of monitoring equipment in a survey is also important to ascertain a solution to these power quality problems. a power quality survey involves gathering data resources; analyzing the data (with reference to power quality standard); then , if problems exist, recommendation of mitigation techniques. the main objective of the present work is to identify power quality problems in second research reactor of egypt (ETRR-2). electrical power is supplied to the installation via tow incoming feeders from tow different substations (incoming feeder from new Abo-Zabal substation and incoming feeder from old Abo-Zabal substation ) to keep good reliability , each feeder is designed to carry the full load of ETRR-2. the monitoring investigations were performed at the second research reactor of egypt for both feeders at different operation conditions

  12. Research on Application of Power System Reliability Model Based on Principal-agent Mechanism

    Directory of Open Access Journals (Sweden)

    Shaomei Yang

    2012-02-01

    Full Text Available Power system reliability has been a widespread concern. With the continuous development of the electricity market, there has been a serious conflict, which between social obligations and necessary requirement. The so-called social obligation is that the power industry must ensure the power system operation reliability; the so-called necessary requirement is that the power industry must solve the power market operation economics. The power system operation reliability is serious challenge, so we must establish a new mechanism adapting to the electricity market, and ensure the power system operation reliability. In this paper, we have researched the model and method based on the principal-agent mechanism from three aspects, which are the reliability principal-agent model starting point, principal-agent model analysis and design, and information transparency level impact analysis. On this basis, we proposed the reliability management model based on the principal-agent mechanism, and carried out example analysis. The example analysis shows that through establishing the principal-agent relationship between power enterprises and the user, the entire power system reliability resources would be more efficient configuration to further enhance the entire society electricity reliability benefits. Further evidence that the principal-agent mechanism is scientific and applicability in the power system reliability study.

  13. Culture, Power and Social Disparity: Researching Russia’s Upper Class

    OpenAIRE

    Elisabeth Schimpfossl

    2014-01-01

    This article explores the dynamics at play when conducting research on the contemporary upper class in Russia. It examines the effect of economic and social status divide between researcher and subjects on how to gain access to interviewees and how to handle the interview situation. Culturally specific expressions of power in social interaction are sought, their characteristics identified and their raison d’être explored. Furthermore, gender related issues encountered throughout the research ...

  14. Analysis of Moderator Temperature Reactivity Coefficient of the PWR Core Using WIMS-ANL

    International Nuclear Information System (INIS)

    The Moderator Temperature Reactivity Coefficient (MTRC) is an important parameter in design, control and safety, particularly in PWR reactor. It is then very important to validate any new processed library for an accurate prediction of this parameter. The objective of this work is to validate the newly WIMS library based on ENDF/B-VI nuclear data files, especially for the prediction of the MTRC parameter. For this purpose, it is used a set of light water moderated lattice experiments as the NORA experiment and R1-100H critical reactors, both of reactors using UO2 fuel pellet. Analysis is used with WIMSD/4 lattice code with original cross section libraries and WIMS-ANL with ENDF/B-VI cross section libraries. The results showed that the moderator temperatures reactivity coefficients for the NORA reactor using original libraries is - 5.039E-04 %Δk/k/℃ but for ENDF/B-VI libraries is - 2.925E-03 %Δk/k/℃. Compared to the designed value of the reactor core, the difference is in the range of 1.8 - 3.8 % for ENDF/B-IV libraries. It can be concluded that for reactor safety and control analysis, it has to be used ENDF/B- VI libraries because the original libraries is not accurate any more. (author)

  15. Short communication: Aflatoxin M₁ in dairy products sold in Şanlıurfa, Turkey.

    Science.gov (United States)

    Temamogullari, F; Kanici, A

    2014-01-01

    The aim of this study was to detect the presence of aflatoxin M₁ (AFM1) in samples of raw milk (n=38), UHT milk (n=12), white pickled cheese (n=50), and yogurt (n=50) collected from the Şanlıurfa city markets and locally produced dairy products by ELISA. The mean contamination rates were 56.74 ± 40.32, 43.1 ± 23.19, 103.2 ± 29.13, and 55.28 ± 12.68 ng/kg, respectively, for raw milk, UHT milk, white pickled cheese, and yogurt. According to the data, 21 (55%) raw milk, 3 (25%) UHT milk, 10 (20%) white pickled cheese, and 10 (20%) yogurt samples were contaminated with AFM1 over the acceptable levels (≥50 ng/kg), ranging from 0.82 to 130.89 ng/kg. None of the white pickled cheese samples contained AFM1 levels above the Turkish legal limit (250 ng/kg). Consequently, the AFM1 contamination levels determined in this study in white pickled cheese were not considered to pose a serious public health hazard. However, the AFM1 levels in raw and UHT milk and yogurt samples indicate an increased human health risk in Turkey related to high aflatoxin levels. Therefore, milk and dairy products have to be monitored by the Turkish public health authorities continuously to detect AFM1 contamination. PMID:24239070

  16. Life extension for fossil power plants: The EPRI [Electric Power Research Institute] strategy

    International Nuclear Information System (INIS)

    Fossil fuel-fired generating plants have traditionally been built under the assumption of an economic life of 20-30 years. Due to low load growth, escalating interest rates and costs of construction, and increasing regulation, great interest is expressed in retaining these units in service for 50-60 years or longer. Life extension activities are part of an ongoing process that continues throughout the extended lives of a utility's units. The process begins with an initial evaluation of life extension as a generation alternative, resulting in a ranking of units for life extension and a prioritization of components for evaluation. As the process continues, more detailed inspection data are created by a three-level approach, as well as a means for collecting, organizing and scheduling the information. This is implemented through the Integrated Life Extension Management (ILEM) model. This model provides information needed for management decision making such as component performance on unit power rating, availability of components on unit availability, component performance on unit availability and overall costs of the life extension tasks. Risks involved in life extension include the initial unavailability of capacity credits, uncertainty as to the level of availability that can be achieved by the life-extended plant, and uncertainties in environmental compliance. 8 refs., 1 fig., 2 tabs

  17. Overview of NASA's Space Solar Power Technology Advanced Research and Development Program

    Science.gov (United States)

    Howell, Joe; Mankins, John C.; Davis, N. Jan (Technical Monitor)

    2001-01-01

    Large solar power satellite (SPS) systems that might provide base load power into terrestrial markets were examined extensively in the 1970s by the US Department of Energy (DOE) and the National Aeronautics and Space Administration (NASA). Following a hiatus of about 15 years, the subject of space solar power (SSP) was reexamined by NASA from 1995-1997 in the 'fresh look' study, and during 1998 in an SSP 'concept definition study', and during 1999-2000 in the SSP Exploratory Research and Technology (SERT) program. As a result of these efforts, during 2001, NASA has initiated the SSP Technology Advanced Research and Development (STAR-Dev) program based on informed decisions. The goal of the STAR-Dev program is to conduct preliminary strategic technology research and development to enable large, multi-megawatt to gigawatt-class space solar power (SSP) systems and wireless power transmission (WPT) for government missions and commercial markets (in-space and terrestrial). Specific objectives include: (1) Release a NASA Research Announcement (NRA) for SSP Projects; (2) Conduct systems studies; (3) Develop Component Technologies; (4) Develop Ground and Flight demonstration systems; and (5) Assess and/or Initiate Partnerships. Accomplishing these objectives will allow informed future decisions regarding further SSP and related research and development investments by both NASA management and prospective external partners. In particular, accomplishing these objectives will also guide further definition of SSP and related technology roadmaps including performance objectives, resources and schedules; including 'multi-purpose' applications (commercial, science, and other government).

  18. Mapping the Anthocyaninless (anl) Locus in Rapid-Cycling Brassica rapa (RBr) to Linkage Group R9

    OpenAIRE

    Wendell Douglas L; Burdzinski Carrie

    2007-01-01

    Abstract Background Anthocyanins are flavonoid pigments that are responsible for purple coloration in the stems and leaves of a variety of plant species. Anthocyaninless (anl) mutants of Brassica rapa fail to produce anthocyanin pigments. In rapid-cycling Brassica rapa, also known as Wisconsin Fast Plants, the anthocyaninless trait, also called non-purple stem, is widely used as a model recessive trait for teaching genetics. Although anthocyanin genes have been mapped in other plants such as ...

  19. Effect of age on inter and intra-subject variability in acceptable noise level (ANL) in listeners with normal hearing

    OpenAIRE

    Fasanya, Bankole K.; Oluseun Omotoso; Olariyike A. Fasanya

    2013-01-01

    Several industrial engineering and psychological studies have shown that noise affects the important aspects of communication for both adults and children. For speech understanding by hearing aids users and language development in children, an accurate hearing is very important. A metric has been developed for measuring an individual's acceptance of noise while listening to speech in quiet. This metric is known as Acceptable Noise Levels (ANLs). Studies have shown large inter-subject variabil...

  20. Design of a Glenn Research Center Solar Field Grid-Tied Photovoltaic Power System

    Science.gov (United States)

    Eichenberg, Dennis J.

    2009-01-01

    The NASA Glenn Research Center (GRC) designed, developed, and installed, a 37.5 kW DC photovoltaic (PV) Solar Field in the GRC West Area in the 1970s for the purpose of testing PV panels for various space and terrestrial applications. The PV panels are arranged to provide a nominal 120 VDC. The GRC Solar Field has been extremely successful in meeting its mission. The PV panels and the supporting electrical systems are all near their end of life. GRC has designed a 72 kW DC grid-tied PV power system to replace the existing GRC West Area Solar Field. The 72 kW DC grid-tied PV power system will provide DC solar power for GRC PV testing applications, and provide AC facility power for all times that research power is not required. A grid-tied system is connected directly to the utility distribution grid. Facility power can be obtained from the utility system as normal. The PV system is synchronized with the utility system to provide power for the facility, and excess power is provided to the utility for use by all. The project transfers space technology to terrestrial use via nontraditional partners. GRC personnel glean valuable experience with PV power systems that are directly applicable to various space power systems, and provide valuable space program test data. PV power systems help to reduce harmful emissions and reduce the Nation s dependence on fossil fuels. Power generated by the PV system reduces the GRC utility demand, and the surplus power aids the community. Present global energy concerns reinforce the need for the development of alternative energy systems. Modern PV panels are readily available, reliable, efficient, and economical with a life expectancy of at least 25 years. Modern electronics has been the enabling technology behind grid-tied power systems, making them safe, reliable, efficient, and economical with a life expectancy of at least 25 years. The report concludes that the GRC West Area grid-tied PV power system design is viable for a reliable

  1. The Communities' research and development programme on decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    This is the first progress report of the European Community's programme (1979-1983) of research on the decommissioning of nuclear power plants. It shows the status of the programme on 31 December 1980. The programme seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific waste materials: steel, concrete and graphite; large transport containers for radioactive was produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive wastes arising from decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

  2. Zero Temperature Hope Calculations

    International Nuclear Information System (INIS)

    The primary purpose of the HOPE code is to calculate opacities over a wide temperature and density range. It can also produce equation of state (EOS) data. Since the experimental data at the high temperature region are scarce, comparisons of predictions with the ample zero temperature data provide a valuable physics check of the code. In this report we show a selected few examples across the periodic table. Below we give a brief general information about the physics of the HOPE code. The HOPE code is an ''average atom'' (AA) Dirac-Slater self-consistent code. The AA label in the case of finite temperature means that the one-electron levels are populated according to the Fermi statistics, at zero temperature it means that the ''aufbau'' principle works, i.e. no a priory electronic configuration is set, although it can be done. As such, it is a one-particle model (any Hartree-Fock model is a one particle model). The code is an ''ion-sphere'' model, meaning that the atom under investigation is neutral within the ion-sphere radius. Furthermore, the boundary conditions for the bound states are also set at the ion-sphere radius, which distinguishes the code from the INFERNO, OPAL and STA codes. Once the self-consistent AA state is obtained, the code proceeds to generate many-electron configurations and proceeds to calculate photoabsorption in the ''detailed configuration accounting'' (DCA) scheme. However, this last feature is meaningless at zero temperature. There is one important feature in the HOPE code which should be noted; any self-consistent model is self-consistent in the space of the occupied orbitals. The unoccupied orbitals, where electrons are lifted via photoexcitation, are unphysical. The rigorous way to deal with that problem is to carry out complete self-consistent calculations both in the initial and final states connecting photoexcitations, an enormous computational task. The Amaldi correction is an attempt to address this problem by distorting the

  3. Research on visual modeling and simulation of control system in nuclear power plant

    International Nuclear Information System (INIS)

    A block diagram-oriented visual modeling and simulating software is developed and corresponding mathematical models of control system are solved by the discrete similarity method. This software can be used to model and simulate control system in nuclear power plant conveniently, rapidly and accurately in visual mode. Some satisfactory results are obtained. The research works will be of well referential and applied value to the design and analysis of control system in nuclear power plant

  4. The Community's research and development programme on decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The programme, adopted by the Council of the European Communities, seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontaminations for decommissioning purposes; dismantling techniques; treatment of specific waste materials (steel, concrete and graphite); large transport containers for radioactive waste arising from decommissioning of nuclear power plants in the Community; and influence of nuclear power plant design features on decommissioning

  5. Research and development activities for cleanup of the Fukushima Daiichi Nuclear Power Station

    OpenAIRE

    佐々木 紀樹; 上西 修司; 宮本 泰明; 船坂 英之

    2013-01-01

    The Fukushima Daiichi Nuclear Power Station accident and restoration works have produced significant volume of radioactive waste. The waste has very different characteristics from usual radioactive waste produced in nuclear power stations and it requires extensive research and development for management of the waste. R&D works such as radionuclide analysis of the waste, hydrogen generation/diffusion analysis of a storage vessel, corrosion evaluation of storage vessels, etc. have been performe...

  6. Zero Energy Building

    DEFF Research Database (Denmark)

    Marszal, Anna Joanna; Heiselberg, Per; Bourrelle, J.S.;

    2011-01-01

    , (4) the type of energy balance, (5) the accepted renewable energy supply options, (6) the connection to the energy infrastructure and (7) the requirements for the energy efficiency, the indoor climate and in case of gird connected ZEB for the building–grid interaction. This paper focuses on the......The concept of Zero Energy Building (ZEB) has gained wide international attention during last few years and is now seen as the future target for the design of buildings. However, before being fully implemented in the national building codes and international standards, the ZEB concept requires...... clear and consistent definition and a commonly agreed energy calculation methodology. The most important issues that should be given special attention before developing a new ZEB definition are: (1) the metric of the balance, (2) the balancing period, (3) the type of energy use included in the balance...

  7. Results of research and development for nuclear power plants with WWER-1000 type light water reactors

    International Nuclear Information System (INIS)

    The conference met in three sessions: 1. Project designing and construction of nuclear power plants; 2. Materials, technologies and applied mechanics; 3. Physics, thermal physics and control. The proceedings contains 82 papers of which only two have not been inputted in INIS. The final resolutions of session 1 related to the reduction of capital costs for newly built units, processing of project documentation, the introduction of step motors manufactured in Czechoslovakia, in-service diagnostics of nuclear power plants, etc. The final recommendations of session 2 dealt with the centralization of the management of research into the reliability, safety and residual life of nuclear installations, with radiation stability of weld metals, repairs of nuclear power plants by patch welding, with welding in nuclear power plants and stress calculations using mathematical methods. Session 3 centred on questions of the safety, reliability and economy of nuclear power plant operation. It was recommended to make a comparison of the results of theoretical calculations with experiments, to concentrate on the automation of measurement, to extend international division of labour and cooperation of CMEA countries, to extend publishing activities in the field of thermal physics, etc. General recommendations were related to the conception of the construction of nuclear power plants in Czechoslovakia, the implementation of original scientific, research and development work, to the question of personnel for nuclear research, the experimental base of the Czechoslovak nuclear programme and to planning and management of technical development. (E.S.)

  8. Research and design of distributed intelligence fault diagnosis system in nuclear power plant

    International Nuclear Information System (INIS)

    In order to further reduce the misoperation after the faults occurring of nuclear power plant, according to the function distribution of nuclear power equipment and the distributed control features of digital instrument control system, a nuclear power plant distributed condition monitoring and fault diagnosis system was researched and designed. Based on decomposition-integrated diagnostic thinking, a fuzzy neural network and RBF neural network was presented to do the distributed local diagnosis and multi-source information fusion technology for the global integrated diagnosis. Simulation results show that the developed distributed status monitoring and fault diagnosis system can diagnose more typical accidents of PWR to provide effective diagnosis and operation information. (authors)

  9. Funding nuclear power research 1956 to 2015. Update; Forschungsfoerderung Kernenergie 1956 bis 2015. Update

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2016-01-15

    In the debates about the use and the benefits of nuclear power plants the allegation is being made that nuclear power to this day had received public subsidies. That was the only reason why electricity from nuclear power plants was economically viable. That statement is wrong. A brief overview is given about the public funds for nuclear energy research and development. In relation to the electricity production less than 0.16 Euro Cents per kilowatt-hour have been spend by public funds for R and D.

  10. Review and assessment of research relevant to design aspects of nuclear power plant piping systems. Final report

    International Nuclear Information System (INIS)

    Significant research on piping systems is evaluated, and the correlation of that research with design practices is presented. The objective is to quantify the research/design practices in terms of the reliability of piping used in nuclear power plants

  11. Inverse amplitude method and Adler zeros

    OpenAIRE

    Gómez Nicola, Ángel; Peláez Sagredo, José Ramón; Rios, G.

    2008-01-01

    The inverse amplitude method is a powerful unitarization technique to enlarge the energy applicability region of effective Lagrangians. It has been widely used to describe resonances in hadronic physics, combined with chiral perturbation theory, as well as in the strongly interacting symmetry breaking sector. In this work we show how it can be slightly modified to also account for the subthreshold region, incorporating correctly the Adler zeros required by chiral symmetry and eliminating spur...

  12. Aging research impact on component and system reliability and maintenance in nuclear power plants

    International Nuclear Information System (INIS)

    A program of aging research on safety-related components and systems in nuclear power plants is being conducted by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research. Data on the performance and failure of existing components and systems in nuclear power plants, current maintenance practices, and surveillance and monitoring techniques is being collected and evaluated to determine what effect aging could have on plant operation, reliability and maintenance. The results of these studies are being used also in the resolution of NRC generic safety issues, the development of an NRC rule for future plant license extension beyond 40 years and a maintenance rule

  13. The development of nuclear power and the research effort in the Community

    International Nuclear Information System (INIS)

    The development of nuclear power in the European Community up to the present time is reviewed in the light of the 1973 oil crisis. The European Community nuclear energy policy and strategy are described, as well as the future objectives for the development of nuclear power in Europe. The research effort in the Community, concerning energy resources, and including nuclear fission energy, is outlined. Research and development (R and D) work in the field of radioactive waste management is reviewed. Also some achievements of the twelve year Plan of Action, and of the multiannual R and D programmes are presented. (U.K.)

  14. Role of the building research and development in the construction of the power unit and nuclear power plant

    International Nuclear Information System (INIS)

    The following tasks have been solved in connection with the Temelin nuclear power plant construction: optimization of horizontal and vertical transport, the design of own roads of rolled concrete for heavy duty transport, the choice and use of lifting devices, the problems of formwork and reinforcement jobs, the methods of massive structure concreting, the use of geofoils and geotextiles, the system of containment prestressing. In future, the building research and development intends to consider the methods of special foundation engineering, the technology of 180 m high cooling construction, a double containment, a wider use of composites and plastics, and quality problems. (M.D.)

  15. National nuclear power plant safety research 2011-2014. SAFIR2014 framework plan

    Energy Technology Data Exchange (ETDEWEB)

    2010-07-01

    A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating organisations of the plants and a regulatory body. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. Ministry of employment and the economy appointed a group to write the Framework Plan of the new programme. This report contains a proposal for the general outline of the programme, entitled as SAFIR2014 (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2011-2014, but it is based on safety challenges identified for a longer time span as well. Olkiluoto 3, the new nuclear power plant unit under construction and new decisions-in-principle have also been taken into account in the plan. The safety challenges set by the existing plants and the new projects, as well as the ensuing research needs do, however, converge to a great extent. The research programme is strongly based on the Chapter 7a of the Finnish Nuclear Energy Act. The construction of new power plant units will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The Framework Plan aims to define the important research needs related to the safety

  16. SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. (ed.)

    2013-02-15

    The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

  17. SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

    International Nuclear Information System (INIS)

    The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

  18. Power

    OpenAIRE

    Bowles, Samuel; Gintis, Herbert

    2007-01-01

    We consider the exercise of power in competitive markets for goods, labour and credit. We offer a definition of power and show that if contracts are incomplete it may be exercised either in Pareto-improving ways or to the disadvantage of those without power. Contrasting conceptions of power including bargaining power, market power, and consumer sovereignty are considered. Because the exercise of power may alter prices and other aspects of exchanges, abstracting from power may miss essential a...

  19. Current status of R and D of Central Research Institute of Electric Power Industry

    International Nuclear Information System (INIS)

    Three research projects of this industry such as the nuclear power, stable power supply, and environment energy technology are reported. On the nuclear power technology, the irradiation embrittlement, stress corrosion cracking, pipe wall thinning and degradation of light water reactor components, low and high level radioactive disposal technology, improvement of aseismic design, next generation reactor, metal fuel cycle technology, and radiation protection are explained. On the stable power supply, technology for stable operation of aged power distribution facilities, effective utilization of resources for thermal power generation and technologies for reducing CO2 emissions, and power generation system with biomass/waste gasification are stated. On the environmental energy technology, the numerical weather forecast and analysis system (NuWFAS) was improved for forecast weather at global warming, energy-saving technology of low carbon society such as high performance heat pump, low-loss power semiconductors, all solid state lithium polymer secondary buttery, the next generation grid and communication network system have been developed. (S.Y.)

  20. C and I power supply for research reactors (Paper No. CP 33)

    International Nuclear Information System (INIS)

    The safety and availability of a nuclear reactor depends greatly on the quality and reliability of control and instrumentation (C and I) power supply. It may not be practical to incorporate fail-safe philosophy in all safety systems of a reactor due to fact that one has to pay huge penalty for spurious actuation of certain systems. A reliable power supply system can solve this problem. Availability of the status of reactor and various systems is essential for the safe operation of the plant. In small size reactors the C and I is powered from normal power supply. It is not practical to provide battery power backup for the whole C and I due to charging and maintenance problems associated with large batteries. This is more so since the reactor is not operated on a continuous basis. But it becomes mandatory to provide some amount of battery power atleast to indicate certain vital information like reactor status etc. in case of failure of normal power supply. This paper describes various aspects of C and I power supply for the research reactors DHRUVA, PURNIMA and KAMINI and highlights their evolution in order to ensure safe and reliable operation of the reactor. (author). 6 refs

  1. Development and Testing of the Glenn Research Center Visitor's Center Grid-Tied Photovoltaic Power System

    Science.gov (United States)

    Eichenberg, Dennis J.

    2009-01-01

    The NASA Glenn Research Center (GRC) has developed, installed, and tested a 12 kW DC grid-tied photovoltaic (PV) power system at the GRC Visitor s Center. This system utilizes a unique ballast type roof mount for installing the photovoltaic panels on the roof of the Visitor s Center with no alterations or penetrations to the roof. The PV system has generated in excess of 15000 kWh since operation commenced in August 2008. The PV system is providing power to the GRC grid for use by all. Operation of the GRC Visitor s Center PV system has been completely trouble free. A grid-tied PV power system is connected directly to the utility distribution grid. Facility power can be obtained from the utility system as normal. The PV system is synchronized with the utility system to provide power for the facility, and excess power is provided to the utility. The project transfers space technology to terrestrial use via nontraditional partners. GRC personnel glean valuable experience with PV power systems that are directly applicable to various space power systems, and provides valuable space program test data. PV power systems help to reduce harmful emissions and reduce the Nation s dependence on fossil fuels. Power generated by the PV system reduces the GRC utility demand, and the surplus power aids the community. Present global energy concerns reinforce the need for the development of alternative energy systems. Modern PV panels are readily available, reliable, efficient, and economical with a life expectancy of at least 25 years. Modern electronics has been the enabling technology behind grid-tied power systems, making them safe, reliable, efficient, and economical with a life expectancy of at least 25 years. Based upon the success of the GRC Visitor s Center PV system, additional PV power system expansion at GRC is under consideration. The GRC Visitor s Center grid-tied PV power system was successfully designed and developed which served to validate the basic principles

  2. RATU Nuclear power plant structural safety research programme 1990-1994. Final report

    International Nuclear Information System (INIS)

    The major part of nuclear energy research in Finland has been organized as five-year nationally coordinated research programmes. The research programme on the Nuclear Power Plant Structural Safety was carried out during the period from 1990 to 1994. The total volume was about 76 person-years and the expenditure about 49 million FIM. Studies on the structural materials in nuclear power plants created the experimental data and background information necessary for the structural integrity assessments of mechanical components. The research was carried out by developing experimental fracture mechanics methods including statistical analysis methods of material property data, and by studying material ageing and, in particular, mechanisms of material deterioration due to neutron irradiation, corrosion and water chemistry. Besides material studies, new testing methods and sensors for the measurement of loading and water chemistry parameters have been developed

  3. Wind power - research and development. The wind turbine industry's view of the promotion of state-supported research and development

    International Nuclear Information System (INIS)

    The windmill industry in Denmark is currently confronted with making a choice between competing technologies so that the role of the stimulus of state subsidies for research has lately increased in importance. The Ministry of Energy, it is claimed, must be aware of this as possibilities for making use of research results are dictated by the market and competition. The industry is not sympathetic to the idea of state research contracts with specified goals for which manufacturers must produce a technical solution. Consultancy firms should work towards solving general problems which could help the industry as a whole. Wind turbines which are cheap to produce and operate are of more interest to industry than those which are technologically advanced or of a lighter construction. It is not thought to be advantageous to concentrate the allocation of subsidies on one key project chosen by the Ministry itself, such as the current intense interest in turbine blades. Aerodynamics, noise pollution and materials are considered as more vital areas for research. A special interest in smaller windmills is not currently relevant. Evaluations of the quality of research projects demanding subsidies should be more critical. A detailed list of subjects within this field which are considered as being relevant for research is given. The Danish windmill industry advises a centralized wind power research institution and a gradual shift of the test station at Risoe National Laboratory to Jutland as wind conditions at Risoe are not considered satisfactory. A better communication between Risoe test station and the wind power industry is recommended. (AB)

  4. Zero Tolerance Policy in Schools: Rationale, Consequences, and Alternatives.

    Science.gov (United States)

    Casella, Ronnie

    2003-01-01

    Discusses theory/policies supporting zero tolerance policy in schools, including rational choice theory in criminology and national crime policies based on deterrence. Potential consequences of zero tolerance policy implementation are described and shown to involve outcomes similar to those identified by researchers studying national crime policy.…

  5. Research and application of accelerated ageing management for important and susceptible components in nuclear power plants

    International Nuclear Information System (INIS)

    This paper introduced the background of research on accelerated ageing management (AAM) technology for important and susceptible components in Daya Bay nuclear power plant (NPP) and Lingao NPP, and expounded the connotation of AAM, demonstrated the AAM technical route, work architecture and interfaces with existing operation and maintenance system in NPPs. Some representative application examples of AAM technology for verifying the rationality and effectiveness of relevant research achievements also were presented. Development prospect of AAM technology was proposed at the last. (authors)

  6. Recommended research program for improving seismic safety of light-water nuclear power plants

    International Nuclear Information System (INIS)

    Recommendations are presented for research areas concerned with seismic safety. These recommendations are based on an analysis of the answers to a questionnaire which was sent to over 80 persons working in the area of seismic safety of nuclear power plants. In addition to the answers of the 55 questionnaires which were received, the recommendations are based on ideas expressed at a meeting of an ad hoc group of professionals formed by Sandia, review of literature, current research programs, and engineering judgement

  7. Zero Modes and Entanglement Entropy

    CERN Document Server

    Yazdi, Yasaman K

    2016-01-01

    Ultraviolet divergences are widely discussed in studies of entanglement entropy. Also present, but much less understood, are infrared divergences due to zero modes in the field theory. In this note, we discuss the importance of carefully handling zero modes in entanglement entropy. We give an explicit example for a chain of harmonic oscillators in 1D, where a mass regulator is necessary to avoid an infrared divergence due to a zero mode. We also comment on a surprising contribution of the zero mode to the UV-scaling of the entanglement entropy.

  8. Comments on future tasks for Romanian research related to nuclear power

    International Nuclear Information System (INIS)

    Four main research areas are identified: - nuclear safety, - waste management, - fuel cycles and - plant life management. A significant number of tasks are related to each of these areas. Unfortunately, the cost of the needed research is much too high for the current electricity planning of Romania. Up to now, the international co-operation in CANDU field was not very efficient. Canada, India, Korea and Argentina have distinct intentions related to the use of nuclear power potential. Romania is the only European country interested to investigate CANDU reactor problems. Consequently, the author believes that the future Romanian nuclear power research effort must be clearly divided in two main classes: a. CR = 'Concentrated Research' on specific subjects, aimed to a better understanding, and to a complete solving of the associated problems, when possible, and b. CAR = 'Covering Areas Research' to maintain and update the know-how needed in the nuclear power activities. A given research subject may successively pass from one class to another, if needed; however, for a given period of one-to-five years, the class must be stated for each project, from the beginning. No research effort must be planned in the first class, CR, if the needed resources (human, technical and financial) are not ensured. Usually, the power plant leaders and the Institute researchers wish to dedicate their efforts to investigation of the 'hot problems'. Apparently, they are always right. In fact, the allocation of human and financial resources must be based on a very careful evaluation of the 'conditions required for success'. Otherwise, instead of the needed solution, the research will probably offer' a significant number of original methods, successfully applied', 'a more detailed knowledge of phenomena', 'several patents', a few papers 'published or accepted for publication in world over recognized scientific journals' etc. Although valuable, such results are not accepted instead of the needed

  9. Zero emission coal

    Energy Technology Data Exchange (ETDEWEB)

    Ziock, H.; Lackner, K.

    2000-08-01

    We discuss a novel, emission-free process for producing hydrogen or electricity from coal. Even though we focus on coal, the basic design is compatible with any carbonaceous fuel. The process uses cyclical carbonation of calcium oxide to promote the production of hydrogen from carbon and water. The carbonation of the calcium oxide removes carbon dioxide from the reaction products and provides the additional energy necessary to complete hydrogen production without additional combustion of carbon. The calcination of the resulting calcium carbonate is accomplished using the high temperature waste heat from solid oxide fuel cells (SOFC), which generate electricity from hydrogen fuel. Converting waste heat back to useful chemical energy allows the process to achieve very high conversion efficiency from fuel energy to electrical energy. As the process is essentially closed-loop, the process is able to achieve zero emissions if the concentrated exhaust stream of CO{sub 2} is sequestered. Carbon dioxide disposal is accomplished by the production of magnesium carbonate from ultramafic rock. The end products of the sequestration process are stable naturally occurring minerals. Sufficient rich ultramafic deposits exist to easily handle all the world's coal.

  10. The EU as a Normative Power and the Research on External Perceptions: the Missing Link

    DEFF Research Database (Denmark)

    Larsen, Henrik

    2014-01-01

    In research on European foreign policy two important axes of debate have been running relatively independently of each other for more than a decade: the study of the European Union as a normative power (NPE) and the study of external perceptions of the EU. However, the studies of external percept...

  11. Research on EMI Reduction of Multi-stage Interleaved Bridgeless Power Factor Corrector

    DEFF Research Database (Denmark)

    Li, Qingnan; Thomsen, Ole Cornelius; Andersen, Michael A. E.

    2012-01-01

    Working as an electronic pollution eliminator, the Power Factor Corrector's (PFC) own Electromagnetic Interference (EMI) problems have been blocking its performance improvement for long. In this paper, a systematic research on EMI generation of a multi-stage Two-Boost-Circuit Interleaved Bridgeless...

  12. Workshop: Research and development plans for high power spallation neutron testing at BNL

    International Nuclear Information System (INIS)

    This report consists of vugraphs from presentations at the meeting. The papers covered the following topics: (1) APS as a proton source; (2) target status for NSNS (National Spallation Neutron Source); (3) spallation neutron source in Japan; (4) liquid LiBi flow loop; and (5) research and development plans for high power tests at the AGS

  13. A NASA high-power space-based laser research and applications program

    Science.gov (United States)

    Deyoung, R. J.; Walberg, G. D.; Conway, E. J.; Jones, L. W.

    1983-01-01

    Applications of high power lasers are discussed which might fulfill the needs of NASA missions, and the technology characteristics of laser research programs are outlined. The status of the NASA programs or lasers, laser receivers, and laser propulsion is discussed, and recommendations are presented for a proposed expanded NASA program in these areas. Program elements that are critical are discussed in detail.

  14. Preparation of processed nuclear data libraries for thermal, fast and fusion research and power reactor applications

    International Nuclear Information System (INIS)

    A Consultants Meeting on ''Preparation of Processed Nuclear Data Libraries for Thermal, Fast and Fusion Research and Power Reactor Applications'' was convened by the International Atomic Energy Agency and held during December 13-16, 1993 December 8-10, 1993 at the IAEA Headquarters, Vienna. The detailed agenda, the complete list of participants and the recommendations are presented in this report. (author)

  15. Sport Physiology Research and Governing Gender in Sport--A Power-Knowledge Relation?

    Science.gov (United States)

    Larsson, Hakan

    2013-01-01

    This article sets out to show how physiological knowledge about sex/gender relates to power issues within sport. The sport physiology research at the Swedish School of Sport and Health Sciences (Swedish acronym: GIH) during the twentieth century is analysed in relation to the political rationality concerning gender at GIH and within the Swedish…

  16. A survey of critical research areas in the energy segment of restructured electric power markets

    International Nuclear Information System (INIS)

    Availability of a large volume of recent literature on deregulated (a.k.a. restructured) electricity markets underscores the importance of the research needs to ensure proper design and functioning of the markets. Researchers have made significant contributions fueling the evolution of the fundamental market design changes that have taken place since the beginning of the restructuring process. Due to the vast scope, existing survey papers are focused on particular facets of deregulated electricity markets. We adopt a similar approach by focusing on the most important research areas related to the energy market. The contributions of the survey paper lie in the novel approach used in classifying the literature based on critical research areas. Some areas of research such as auction based pricing, bidding strategy formulation, market equilibria, and market power are reviewed in a different light than other existing survey papers. We conclude by providing some future research directions for the energy markets. (author)

  17. Inventory of nuclear power plants and research reactors temporary or definitively stopped in industrialized countries

    International Nuclear Information System (INIS)

    This paper presents data and information on the end of the life of nuclear reactors. One deals more particularly with installations of industrialized countries. This report gives the motivations which have involved the definitive shut down of nuclear power plants and of research reactors in the concerned countries. A schedule of definitive reactor shutdowns is presented. Then, one deals with nuclear power plants of which the construction has been stopped. The reasons of these situations are also given. The temporary difficulties met during the construction or the starting of nuclear power plants these last years are mentioned. Most times, there are economical or political considerations, or safety reasons. Finally, the nuclear power plants stopped for more than two years are mentioned

  18. Research reactor power controller design using an output feedback nonlinear receding horizon control method

    International Nuclear Information System (INIS)

    A constrained, output feedback nonlinear receding horizon control (NRHC) method is applied to design a research reactor power controller. The method uses a nonlinear plant model subject to state, control and terminal set constraints; a nonlinear cost function; and a high gain observer. The controller regulates reactor power from 1% to 100% of full power; considers known disturbances, such as reactivity insertions and changes in core inlet flow and temperature; and includes upper limits constraints on neutron flux, neutron flux rate, core outlet temperature and core inlet-outlet temperature difference. Simulation results show an excellent performance for power regulation and known disturbances rejection: all process variables are kept within the admissible limits avoiding the actuation of the safety systems

  19. State-of-the-art research: optimal investment in market-based electric power systems

    Energy Technology Data Exchange (ETDEWEB)

    Hope, Einar; Skjeret, Frode

    2008-04-15

    The purpose of this state-of-the-art research paper is to surveying the literature on investment in market based electric power systems as a background for identifying and discussing some important issues in the optimal design and operation of such systems. A fundamental distinction has to be made between investment in the competitive part of the power system (generation and trading) on the one hand and the natural monopoly part (network infrastructure) on the other. The paper starts with a listing and discussion on market characteristics and properties of electric power and goes on to discussing performance criteria and potential sources of market failure for optimal electric power investment. After the literature survey there is a discussion of conditions under which optimal investment may occur. (author). 78 refs., figs

  20. Discourse, Power, and Knowledge in the Management of "Big Science": The Production of Consensus in a Nuclear Fusion Research Laboratory.

    Science.gov (United States)

    Kinsella, William J.

    1999-01-01

    Extends a Foucauldian view of power/knowledge to the archetypical knowledge-intensive organization, the scientific research laboratory. Describes the discursive production of power/knowledge at the "big science" laboratory conducting nuclear fusion research and illuminates a critical incident in which the fusion research "discipline" imposes…