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Sample records for plant stations eventually

  1. Opportunities for the operation of the Comision Federal de Electricidad`s fossil fuel power plant stations eventually to be retired as cogeneration units; Oportunidades de operar las centrales termoelectricas de la Comision Federal de Electricidad, eventualmente retirables como unidades de cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Buendia Dominguez, E. H. [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Merlos Rueda, R. M. [Programa de Ahorro de Energia para el Sector Electrico, Mexico, D. F. (Mexico)

    1995-12-31

    The Programa de Ahorro de Energia para el Sector Electrico (PAESE) (Program for Energy Conservation for the Electric Sector) in collaboration with the Instituto de Investigaciones Electricas (IIE), decided to evaluate technically and economically the possibilities of operating the Comision Federal de Electricidad`s Thermoelectric Power Stations (TPS), eventually to be retired as cogeneration units in supplying thermal energy to industry. The study was focussed to the Monterrey and San Jeronimo Power Stations, determining in a first stage, the optimum radius for handling and transporting steam and/or hot water and so to define the industries that potentially could obtain heat energy from the TPS, in this stage the thermal needs of the evaluated industries were determined (pressure, temperature and flow). In a second stage, the different arrangements to be made to operate the selected TPS, so as to be in position of satisfying such thermal energy demands were evaluated. This paper presents the results of this study. [Espanol] El Programa de Ahorro de Energia para el Sector Electrico (PAESE), en colaboracion con el Instituto de Investigaciones Electricas, decidieron evaluar tecnica y economicamente las posibilidades de operar las centrales termoelectricas (CT`s) de la Comision Federal de Electricidad, eventualmente retirables, como unidades de cogeneracion al ofrecer calor a la industria. El estudio se enfoco en las centrales de Monterrey y San Jeronimo, determinado en una primera etapa el radio optimo para el manejo y transporte de vapor y/o agua caliente y asi definir a las industrias que potencialmente podrian recibir calor de las CT`s, en esta etapa se determinaron las necesidades termicas de las industrias evaluadas (presion, temperatura y flujo). En una segunda etapa se evaluo los diferentes arreglos para operar las CT`s seleccionadas para que pudieran satisfacer dichas demandas termicas. En este trabajo se presentaron los resultados de dicho estudio.

  2. Opportunities for the operation of the Comision Federal de Electricidad`s fossil fuel power plant stations eventually to be retired as cogeneration units; Oportunidades de operar las centrales termoelectricas de la Comision Federal de Electricidad, eventualmente retirables como unidades de cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Buendia Dominguez, E H [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Merlos Rueda, R M [Programa de Ahorro de Energia para el Sector Electrico, Mexico, D. F. (Mexico)

    1996-12-31

    The Programa de Ahorro de Energia para el Sector Electrico (PAESE) (Program for Energy Conservation for the Electric Sector) in collaboration with the Instituto de Investigaciones Electricas (IIE), decided to evaluate technically and economically the possibilities of operating the Comision Federal de Electricidad`s Thermoelectric Power Stations (TPS), eventually to be retired as cogeneration units in supplying thermal energy to industry. The study was focussed to the Monterrey and San Jeronimo Power Stations, determining in a first stage, the optimum radius for handling and transporting steam and/or hot water and so to define the industries that potentially could obtain heat energy from the TPS, in this stage the thermal needs of the evaluated industries were determined (pressure, temperature and flow). In a second stage, the different arrangements to be made to operate the selected TPS, so as to be in position of satisfying such thermal energy demands were evaluated. This paper presents the results of this study. [Espanol] El Programa de Ahorro de Energia para el Sector Electrico (PAESE), en colaboracion con el Instituto de Investigaciones Electricas, decidieron evaluar tecnica y economicamente las posibilidades de operar las centrales termoelectricas (CT`s) de la Comision Federal de Electricidad, eventualmente retirables, como unidades de cogeneracion al ofrecer calor a la industria. El estudio se enfoco en las centrales de Monterrey y San Jeronimo, determinado en una primera etapa el radio optimo para el manejo y transporte de vapor y/o agua caliente y asi definir a las industrias que potencialmente podrian recibir calor de las CT`s, en esta etapa se determinaron las necesidades termicas de las industrias evaluadas (presion, temperatura y flujo). En una segunda etapa se evaluo los diferentes arreglos para operar las CT`s seleccionadas para que pudieran satisfacer dichas demandas termicas. En este trabajo se presentaron los resultados de dicho estudio.

  3. Plant diagnostics in power stations

    International Nuclear Information System (INIS)

    Sturm, A.; Doering, D.

    1985-01-01

    The method of noise diagnostics is dealt with as a part of plant diagnostics in nuclear power stations. The following special applications are presented: (1) The modular noise diagnostics system is used for monitoring primary coolant circuits and detecting abnormal processes due to mechanical vibrations, loose parts or leaks. (2) The diagnostics of machines and plants with antifriction bearings is based on bearing vibration measurements. (3) The measurement of the friction moment by means of acoustic emission analysis is used for evaluating the operational state of slide bearings

  4. Design Provisions for Withstanding Station Blackout at Nuclear Power Plants

    International Nuclear Information System (INIS)

    2015-08-01

    International operating experience has shown that the loss of off-site power supply concurrent with a turbine trip and unavailability of the standby alternating current power system is a credible event. Lessons learned from the past and recent station blackout events, as well as the analysis of the safety margins performed as part of the ‘stress tests’ conducted on European nuclear power plants in response to the Fukushima Daiichi accident, have identified the station blackout event as a limiting case for most nuclear power plants. The magnitude 9.0 earthquake and consequential tsunami which occurred in Fukushima, Japan, in March 2011, led to a common cause failure of on-site alternating current electrical power supply systems at the Fukushima Daiichi nuclear power plant as well as the off-site power grid. In addition, the resultant flooding caused the loss of direct current power supply, which further exacerbated an already critical situation at the plant. The loss of electrical power resulted in the meltdown of the core in three reactors on the site and severely restricted heat removal from the spent fuel pools for an extended period of time. The plant was left without essential instrumentation and controls, and this made accident management very challenging for the plant operators. The operators attempted to bring and maintain the reactors in a safe state without information on the vital plant parameters until the power supply was eventually restored after several days. Although the Fukushima Daiichi accident progressed well beyond the expected consequences of a station blackout, which is the complete loss of all alternating current power supplies, many of the lessons learned from the accident are valid. A failure of the plant power supply system such as the one that occurred at Fukushima Daiichi represents a design extension condition that requires management with predesigned contingency planning and operator training. The extended loss of all power at a

  5. Plant computer system in nuclear power station

    International Nuclear Information System (INIS)

    Kato, Shinji; Fukuchi, Hiroshi

    1991-01-01

    In nuclear power stations, centrally concentrated monitoring system has been adopted, and in central control rooms, large quantity of information and operational equipments concentrate, therefore, those become the important place of communication between plants and operators. Further recently, due to the increase of the unit capacity, the strengthening of safety, the problems of man-machine interface and so on, it has become important to concentrate information, to automate machinery and equipment and to simplify them for improving the operational environment, reliability and so on. On the relation of nuclear power stations and computer system, to which attention has been paid recently as the man-machine interface, the example in Tsuruga Power Station, Japan Atomic Power Co. is shown. No.2 plant in the Tsuruga Power Station is a PWR plant with 1160 MWe output, which is a home built standardized plant, accordingly the computer system adopted here is explained. The fundamental concept of the central control board, the process computer system, the design policy, basic system configuration, reliability and maintenance, CRT display, and the computer system for No.1 BWR 357 MW plant are reported. (K.I.)

  6. Pilot plant experiments at Wairakei Power Station

    International Nuclear Information System (INIS)

    Brown, Kevin L.; Bacon, Lew G.

    2009-01-01

    In the mid-1990s, several pilot plants were constructed at Wairakei to either improve the operational and economic performance of the power station or to mitigate the environmental effects of discharges to the Waikato River. The results of the following investigations are discussed: (1) fluid flow dynamic effects on silica scaling; (2) production of silica sols of predetermined particle size to evaluate the potential for generating commercial grade silica products; (3) use of 'sulfur oxidising bacteria' for the abatement of dissolved hydrogen sulphide in cooling water; (4) removal of arsenic from separated geothermal water; (5) steam line condensate corrosion; and (6) measurement and modelling of steam scrubbing in Wairakei's long steamlines. (author)

  7. The plant efficiency of fusion power stations

    International Nuclear Information System (INIS)

    Darvas, J.; Foerster, S.

    1976-01-01

    Due to the circulating energy, lower efficiencies are to be expected with fusion power plants than with nuclear fission power plants. According to the systems analysis, the mirror machine is not very promising as a power plant. The plant efficiency of the laser fusion strongly depends on the laser efficiency about which one can only make speculative statements at present. The Tokamak requires a relatively low circulating energy and is certainly able to compete regarding efficiency as long as the consumption time can be kept large (> 100 sec) and the dead time between the power pulses small ( [de

  8. Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant

    International Nuclear Information System (INIS)

    Silva, Diogo Neves Gomes da

    2016-01-01

    When a radiological or nuclear accident that leads to the release of radioactive material to the environment occurs, it is important to implement protective and remediation measures in order to reduce human exposure to radionuclides. Therefore, it is necessary that the procedures to be chosen by the affected country authorities are the most efficient ones, which can only be defined based on previously established criteria. In Brazil, since the radiological accident in Goiania, in 1987, the development of tools to support decision-making in emergencies of this nature was started. The main objective of this work was to establish an acting basis for contaminated areas, in order to protect the individuals of public in case of any accident related to Almirante Alvaro Alberto nuclear power plant, in the municipality of Angra dos Reis (RJ), which leads to contamination to the environment and the consequent exposure of local population or from more distant regions to ionizing radiation. Initially, the high-risk areas near the location of the nuclear power plant were defined. Typical urban environments found in the main cities of these municipalities were surveyed, including homes, streets and recreation areas. The main characteristics of the study area were evaluated using images from Google Earth® and web pages of the municipalities. After the types of areas to be simulated were selected, these were quantified in terms of the number of residents, the size of the streets, and the number of trees, among others, per unit area. Considering the different housing characteristics for the selected municipalities, six main standard scenarios were developed for urban areas, including homes with different shielding, buildings and parks. The simulation of the procedures for each scenario was made with SIEM model, developed by the Institute of Radiation Protection and Dosimetry (IRD/CNEN), formed by the integration of various models including CORAL, focusing on agricultural areas

  9. Ab initio vel ex eventu

    Science.gov (United States)

    Thiessen, P. A.; Treder, H.-J.

    Der gegenwärtige Stand der physikalischen Erkenntnis, in Sonderheit die Atomistik und die Quantentheorie, ermöglicht (in wohldefinierten Energie-Bereichen) eine ab initio-Berechnung aller physikalischen und chemischen Prozesse und Strukturen. Die Schrödinger-Gleichung erlaubt zusammen mit den Prinzipien der Quantenstatistik (Pauli-Prinzip) aus dem Planckschen Wirkungsquantum h und den atomischen Konstanten die Berechnung aller Energieumsätze, Zeitabläufe etc., die insbesondere die chemische Physik bestimmen. Die Rechenresultate gelten auch quantitativ bis auf die unvermeidliche Stochastik.Die ab initio-Berechnungen korrespondieren einerseits und sind andererseits komplementär zu den auf den Methoden der theoretischen Chemie und der klassischen Thermodynamik beruhenden Ergebnissen ex eventu. Die theoretische Behandlung ab initio führt zu mathematischen Experimenten, die die Laboratoriums-Experimente ergänzen oder auch substituieren.Translated AbstractAb initio vel ex eventuThe present state of physical knowledge, in peculiar atomistic and quantum theory, makes an ab initio calculation of all physical and chemical processes and structures possible (in well defined reaches of energy). The Schrödinger equation together with the principles of quantum statistics (Pauli principle) permits from the Planck and atomistic constants to calculate all exchanges of energy, courses of time, etc. which govern chemical physics. The calculated results are valid even quantitatively apart from the unavoidable stochastics.These ab initio calculations on the one hand correspond and are on the other complimentary to results ex eventu based on the methods of theoretical chemistry and classical thermodynamics. Theoretical treatment ab initio leads to mathematical experiments which add to or even substitute experiments in the laboratory.

  10. Computer functions in overall plant control of candu generating stations

    International Nuclear Information System (INIS)

    Chou, Q.B.; Stokes, H.W.

    1976-01-01

    System Planning Specifications form the basic requirements for the performance of the plant including its response to abnormal situations. The rules for the computer control programs are devised from these, taking into account limitations imposed by the reactor, heat transport and turbine-generator systems. The paper outlines these specifications and the limitations imposed by the major items of plant equipment. It describes the functions of each of the main programs, their interactions and the control modes used in the existing Ontario Hydro's nuclear station or proposed for future stations. Some simulation results showing the performance of the overall unit control system and plans for future studies are discussed. (orig.) [de

  11. Final site environmental statement: Blue Hills Station, Unit Nos. 1 and 2. Related to the determination of the suitability of Site G for eventual construction. Docket Nos. 50-510 and 50-511

    International Nuclear Information System (INIS)

    1978-07-01

    The site suitability analysis is based on the assumption that the Blue Hills Station will employ two pressurized water reactors to produce outputs of approximately 2814 MWt each. Two steam turbine generators will use the heat produced to provide approximately 957 MWe (gross) each. The exhaust steam will be cooled by four low-profile round mechanical-draft cooling towers. Assuming construction of a nuclear station at site G, a summary of environmental impacts and adverse effects is presented

  12. Growth Chambers on the International Space Station for Large Plants

    Science.gov (United States)

    Massa, Gioia D.; Wheeler, Raymond M.; Morrow, Robert C.; Levine, Howard G.

    2016-01-01

    The International Space Station (ISS) now has platforms for conducting research on horticultural plant species under LED (Light Emitting Diodes) lighting, and those capabilities continue to expand. The Veggie vegetable production system was deployed to the ISS as an applied research platform for food production in space. Veggie is capable of growing a wide array of horticultural crops. It was designed for low power usage, low launch mass and stowage volume, and minimal crew time requirements. The Veggie flight hardware consists of a light cap containing red (630 nanometers), blue, (455 nanometers) and green (530 nanometers) LEDs. Interfacing with the light cap is an extendable bellowsbaseplate for enclosing the plant canopy. A second large plant growth chamber, the Advanced Plant Habitat (APH), is will fly to the ISS in 2017. APH will be a fully controllable environment for high-quality plant physiological research. APH will control light (quality, level, and timing), temperature, CO2, relative humidity, and irrigation, while scrubbing any cabin or plant-derived ethylene and other volatile organic compounds. Additional capabilities include sensing of leaf temperature and root zone moisture, root zone temperature, and oxygen concentration. The light cap will have red (630 nm), blue (450 nm), green (525 nm), far red (730 nm) and broad spectrum white LEDs (4100K). There will be several internal cameras (visible and IR) to monitor and record plant growth and operations. Veggie and APH are available for research proposals.

  13. U.S. Central Station Nuclear Power Plants: operating history

    International Nuclear Information System (INIS)

    1976-01-01

    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission

  14. Safety aspects of station blackout at nuclear power plants

    International Nuclear Information System (INIS)

    1985-03-01

    The principal focus of this report is on existing light water reactor nuclear power plants. However, many of the considerations discussed herein can be equally applied to new plants, i.e. those not yet in construction. This report is organized to provide a description of design and procedural factors which safety assessments and reviews of operating experience have shown to be important. These are divided into the off-site power system, the on-site AC power systems and alternate (or nearby) sources of power. The latter may be used in the unlikely event that both normal off-site and on-site sources fail. It must be emphasized that first priority should be placed on designing and maintaining high reliability of both the off-site and on-site AC power systems. This basic concept also applies to the capabilities for restoring power sources which failed and making use of all available alternative and nearby power sources during an emergency, to restore AC power in a prompt manner. Discussions on these aspects are provided in chapters 2 and 3 of this report. Because the expected event frequency and associated confidence in such estimations of station blackout are uncertain, preparations should be made to deal with a station blackout. The nature of those preparations, whether they be optimizing emergency procedures to use existing equipment, modifying this equipment to enhance capabilities, or adding new components or systems to cope with station blackout, must be made in light of plant-specific assessments and regulatory safety philosophies/requirements. Discussions on these matters are provided in chapter 4. General and specific conclusions and recommendations are provided in chapter 5. Appendix A provides a description of several case studies on station blackout and loss of off-site power. Abstracts of papers and presentations are provided in Appendix B with authors and affiliations identified to facilitate personal contact. The References and Bibliography contain a

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

    International Nuclear Information System (INIS)

    Ching-Hui Wu; Tsu-Jen Lin; Tsu-Mu Kao

    2002-01-01

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

  16. Design Provisions for Station Blackout at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Duchac, Alexander

    2015-01-01

    A station blackout (SBO) is generally known as 'a plant condition with complete loss of all alternating current (AC) power from off-site sources, from the main generator and from standby AC power sources important to safety to the essential and nonessential switchgear buses. Direct current (DC) power supplies and un-interruptible AC power supplies may be available as long as batteries can supply the loads. Alternate AC power supplies are available'. A draft Safety Guide DS 430 'Design of Electrical Power Systems for Nuclear Power Plants' provides recommendations regarding the implementation of Specific Safety Requirements: Design: Requirement 68 for emergency power systems. The Safety Guide outlines several design measures which are possible as a means of increasing the capability of the electrical power systems to cope with a station blackout, without providing detailed implementation guidance. A committee of international experts and advisors from numerous countries is currently working on an IAEA Technical Document (TECDOC) whose objective is to provide a common international technical basis from which the various criteria for SBO events need to be established, to support operation under design basis and design extension conditions (DEC) at nuclear power plants, to document in a comprehensive manner, all relevant aspects of SBO events at NPPs, and to outline critical issues which reflect the lessons learned from the Fukushima Dai-ichi accident. This paper discusses the commonly encountered difficulties associated with establishing the SBO criteria, shares the best practices, and current strategies used in the design and implementation of SBO provisions and outline the structure of the IAEA's SBO TECDOC under development. (author)

  17. Cooling methods of station blackout scenario for LWR plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The objective of this study is to analyze the cooling method of station blackout scenario for both the BWR and PWR plants by RELAP5 code and to check the validity of the cooling method proposed by the utilities. In the BWR plant cooling scenario, the Reactor Core Isolation Cooling System (RCIC), which is operated with high pressure steam from the reactor, injects cooling water into the reactor to keep the core water level. The steam generated in the core is released into the suppression pool at containment vessel to condense. To restrict the containment vessel pressure rising, the ventilation from the wet-well is operated. The scenario is analyzed by RELAP5 code. In the PWR plant scenario, the primary pressure is decreased by the turbine-driven auxiliary feed water system operated with secondary side steam of the steam generators (SGs). And the core cooling is kept by the natural circulation flow at the primary loop. From the RELAP5 code analysis, it was shown that the primary system cooling was practicable by using the turbine-driven auxiliary feed water system. (author)

  18. Cooling methods of station blackout scenario for LWR plants

    International Nuclear Information System (INIS)

    2012-01-01

    The objective of this study is to analyze the cooling method of station blackout scenario for both the BWR and PWR plants by RELAP5 code and to check the validity of the cooling method proposed by the utilities. In the BWR plant cooling scenario, the Reactor Core Isolation Cooling System (RCIC), which is operated with high pressure steam from the reactor, injects cooling water into the reactor to keep the core water level. The steam generated in the core is released into the suppression pool at containment vessel to condense. To restrict the containment vessel pressure rising, the ventilation from the wet-well is operated. The scenario is analyzed by RELAP5 and CONTEMPT-LT code. In the PWR plant scenario, the primary pressure is decreased by the turbine-driven auxiliary feed water system operated with secondary side steam of the steam generators (SGs). And the core cooling is kept by the natural circulation flow at the primary loop. The analytical method of un-uniform flow behavior among the SG U-tubes, which affects the natural circulation flow rate, is developed. (author)

  19. Low-Cost Methane Liquefaction Plant and Vehicle Refueling Station

    International Nuclear Information System (INIS)

    Wilding, B.; Bramwell, D.

    1999-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is currently negotiating a collaborative effort with Pacific Gas and Electric (PG and E) that will advance the use of liquefied natural gas (LNG) as a vehicle fuel. We plan to develop and demonstrate a small-scale methane liquefaction plant (production of 5,000 to 10,000 gallons per day) and a low-cost ($150,000) LNG refueling station to supply fuel to LNG-powered transit buses and other heavy-duty vehicles. INEEL will perform the research and development work. PG and E will deploy the new facilities commercially in two demonstration projects, one in northern California, and one in southern California

  20. Trempel hydropower station - renewal and extension of the existing plant

    International Nuclear Information System (INIS)

    Binder, F.M.; Burri, J.

    2003-01-01

    This final report for the Swiss Federal Office of Energy (SFOE) presents the results of a study made on the refurbishment and/or extension of a 450 kW hydropower plant near Krummenau, Switzerland. Three possible variants are presented, one involving the renewal of the installation and two variants for enhancing production to provide 1 MW and 2.25 MW of power respectively. Details on the hydrology of the location are given and the equipment of the existing two-turbine power station is described. Residual water questions are discussed and the civil works envisaged are described. The report also presents data on the economics of the project and assesses the effects on the environment, landscape and ground water it would bring with it

  1. Station black out analysis for CANDU 6 plant

    International Nuclear Information System (INIS)

    Baburajan, P.K.; Rao, R.S.; Gupta, S.K.

    2011-01-01

    As part of International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP), 'Benchmarking severe accident computer codes for pressurised heavy water reactor applications', thermal hydraulic analysis of severe accident station black out (SBO) is carried out for a generic CANDU 6 plant. The CRP is conducted in order to improve severe accident analysis capability for heavy water reactors (HWRs) through the benchmarking exercise. The plant simulation is carried out using RELAP5/Mod3.4 best estimate system thermal hydraulic code. The total thermal power of the plant is 2064 MW. There are 380 fuel channels in the core, 12 fuel bundles per channel and each bundle assembly has 37 fuel elements. The primary heat transport system (HTS) consists of two loops. Each loop consist of inlet and exit headers, feeder lines, fuel channels, hot leg and cold leg of steam generator, pumps, pump suction and discharge lines. Ninety five fuel channels in each pass of the loop are simulated as a single channel. The steam generator as the secondary side heat sink consists of annulus down-comer, riser, steam separator, steam drum, steam header and steam lines. Fuel channels (pressure tube) and calandria tube are simulated using SCDAPSIM to study the severe accident code behaviour. The SBO transient is initiated after obtaining the steady state conditions. Present analysis is carried out till the pressure tube failure. Analysis results show that the secondary inventory is lost in about 6500 seconds of the transient. The primary inventory is lost in 10370 seconds of the transient and subsequently the pressure tube failure is predicted as the tube wall temperature exceeded 900 K. Further analysis is to be carried out by incorporating changes in the calandria model and including the modeling of calandria vault and containment. (author)

  2. Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant; Estabelecimento de criterios para a classificacao de medidas de remediacao de areas contaminadas apos um eventual acidente nuclear na usina de Angra dos Reis (RJ)

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2016-07-01

    When a radiological or nuclear accident that leads to the release of radioactive material to the environment occurs, it is important to implement protective and remediation measures in order to reduce human exposure to radionuclides. Therefore, it is necessary that the procedures to be chosen by the affected country authorities are the most efficient ones, which can only be defined based on previously established criteria. In Brazil, since the radiological accident in Goiania, in 1987, the development of tools to support decision-making in emergencies of this nature was started. The main objective of this work was to establish an acting basis for contaminated areas, in order to protect the individuals of public in case of any accident related to Almirante Alvaro Alberto nuclear power plant, in the municipality of Angra dos Reis (RJ), which leads to contamination to the environment and the consequent exposure of local population or from more distant regions to ionizing radiation. Initially, the high-risk areas near the location of the nuclear power plant were defined. Typical urban environments found in the main cities of these municipalities were surveyed, including homes, streets and recreation areas. The main characteristics of the study area were evaluated using images from Google Earth® and web pages of the municipalities. After the types of areas to be simulated were selected, these were quantified in terms of the number of residents, the size of the streets, and the number of trees, among others, per unit area. Considering the different housing characteristics for the selected municipalities, six main standard scenarios were developed for urban areas, including homes with different shielding, buildings and parks. The simulation of the procedures for each scenario was made with SIEM model, developed by the Institute of Radiation Protection and Dosimetry (IRD/CNEN), formed by the integration of various models including CORAL, focusing on agricultural areas

  3. Gene expression from plants grown on the International Space Station

    Science.gov (United States)

    Stimpson, Alexander; Pereira, Rhea; Kiss, John Z.; Correll, Melanie

    Three experiments were performed on the International Space Station (ISS) in 2006 as part of the TROPI experiments. These experiments were performed to study graviTROPIsm and photoTROPIsm responses of Arabidopsis in microgravity (µg). Seedlings were grown with a variety of light and gravitational treatments for approximately five days. The frozen samples were returned to Earth during three space shuttle missions in 2007 and stored at -80° C. Due to the limited amount of plant biomass returned, new protocols were developed to minimize the amount of material needed for RNA extraction as a preparation for microarray analysis. Using these new protocols, RNA was extracted from several sets of seedlings grown in red light followed by blue light with one sample from 1.0g treatment and the other at µg. Using a 2-fold change criterion, microarray (Affymetrix, GeneChip) results showed that 613 genes were upregulated in the µg sample while 757 genes were downregulated. Upregulated genes in response to µg included transcription factors from the WRKY (15 genes), MYB (3) and ZF (8) families as well as those that are involved in auxin responses (10). Downregulated genes also included transcription factors such as MYB (5) and Zinc finger (10) but interestingly only two WRKY family genes were down-regulated during the µg treatment. Studies are underway to compare these results with other samples to identify the genes involved in the gravity and light signal transduction pathways (this project is Supported By: NASA NCC2-1200).

  4. Nuclear generating station and heavy water plant cost estimates for strategy studies

    International Nuclear Information System (INIS)

    Archinoff, G.H.

    1979-07-01

    Nuclear generating station capital, operating and maintenance costs are basic input data for strategy analyses of alternate nuclear fuel cycles. This report presents estimates of these costs for natural uranium CANDU stations, CANDU stations operating on advanced fuel cycles, and liquid metal fast breeder reactors. Cost estimates for heavy water plants are also presented. The results show that station capital costs for advanced fuel cycles are not expected to be significantly greater than those for natural uranium stations. LMFBR capital costs are expected to be 25-30 percent greater than for CANDU's. (auth)

  5. Will black holes eventually engulf the Universe?

    International Nuclear Information System (INIS)

    Martin-Moruno, Prado; Jimenez Madrid, Jose A.; Gonzalez-Diaz, Pedro F.

    2006-01-01

    The Babichev-Dokuchaev-Eroshenko model for the accretion of dark energy onto black holes has been extended to deal with black holes with non-static metrics. The possibility that for an asymptotic observer a black hole with large mass will rapidly increase and eventually engulf the Universe at a finite time in the future has been studied by using reasonable values for astronomical parameters. It is concluded that such a phenomenon is forbidden for all black holes in quintessential cosmological models

  6. Management of the Tobruk power station and seawater desalination plant

    Energy Technology Data Exchange (ETDEWEB)

    Homann, H J

    1983-01-01

    BBC and two consortium firms provided, for one year, the management personnel for operation and maintenance of the power and seawater desalination plant in Tobruk, Libya, constructed under the leadership of BBC. The plant organisation was established at site in cooperation with the client. Following thorough training, the client's staff took over plant management after one year according to contract.

  7. Medicinal plants: traditions and study prospects (devoted to the 100th anniversary of establishing the Experimental Station of Medicinal Plants

    Directory of Open Access Journals (Sweden)

    О. С. Дем’янюк

    2016-12-01

    Full Text Available Historical review was done concerning the formation and development of scientific research of the Experimental Station of Medicinal Plants over the period 1916–2016. The main stages of experimenting in the direction of “medicinal plant cultivation’’ in Ukraine were covered. Role and importance of the Experimental Station of Medicinal Plants in the scientific and methodological support of such scientific directions as breeding, seed production, cultivation technologies, pharmacognosy in medicinal plant cultivation were shown. For the needs of the branch, over 100 species of introduced medicinal plants were studied at the Station and agricultu­ral techniques of their growing were developed, in addition, more than 50 varieties of medicinal plants were crea­ted, a number of machines and devices for growing, harves­ting and initial treatment of raw materials and seeds of the most important medicinal plants was designed. Other scientific achievements of the Station were mentioned and promising areas of medicinal plant research in Ukraine were outlined.

  8. General Analysis of System Efficiency in Application of Combined Power Plants for Gas-Distribution Station

    Directory of Open Access Journals (Sweden)

    A. D. Kachan

    2004-01-01

    Full Text Available The paper proposes utilization of discharged heat of gas-piston engine (GPE or contact steam-gas plants (SGP with the purpose to heat up gas at gas-distribution stations (GDS of combined power plants with turbine and gas-expansion units. Calculations prove significant economic efficiency of the proposed variant in comparison with the application of ordinary gas- turbine units. Technical and economic calculation is used to determine gas-piston engine or contact steam-gas plant power for specific operational conditions of gas-distribution stations and utilization rate of discharged heat.

  9. Statistical inquiry on the reliability of emergency diesel stations in German nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    This statistic inquiry is based on 692 occurrances in 40 diesel stations of 10 German nuclear power plants. Various parameters influencing the failure behaviour of diesel stations were investigated on only significant plant-specific influences and the impact of diesel station circuitry on failure behaviour were established. According to the results of this inquiry, running time, start-up number and increasing operational experience do not apparently influence the failure behaviour of diesel stations. The expected failure probability of diesel stations varies with the different nuclear power plants. Taking into account both start-up and operational failures, (with monthly inspections and running times of up to 2 h), this value is in the range of 1.6 x 10 -2 to 1.7 x 10 -3 per application. Considering failure data of all diesel stations, the failure probability (start-up and operational failures) is 8.1 x 10 -3 per application. On account of the two common-mode failures registered, a common-mode failure probability of 10 -3 was established. The inquiry also showed that non-availability of diesel stations is essentially determined by maintenance intervals. (orig.) [de

  10. Plant and animal accommodation for Space Station Laboratory

    Science.gov (United States)

    Olson, Richard L.; Gustan, Edith A.; Wiley, Lowell F.

    1986-01-01

    An extended study has been conducted with the goals of defining and analyzing relevant parameters and significant tradeoffs for the accommodation of nonhuman research aboard the NASA Space Station, as well as conducting tradeoff analyses for orbital reconfiguring or reoutfitting of the laboratory facility and developing laboratory designs and program plans. The two items exerting the greatest influence on nonhuman life sciences research were identified as the centrifuge and the specimen environmental control and life support system; both should be installed on the ground rather than in orbit.

  11. Plant habitability assessment for Point Lepreau Generating Station during a severe accident resulting from station blackout conditions

    International Nuclear Information System (INIS)

    Mullin, D.

    2015-01-01

    In response to the CNSC Fukushima Action Plan, the CANDU Owners Group (COG) developed a methodology for assessing nuclear power plant habitability under Joint Project 4426 and to determine if any improvement actions are necessary to provide a high degree of assurance that a severe accident can be managed from a human and organizational performance perspective. NB Power has applied the methodology considering a station black-out scenario (representative case), and assessed the effects of non-radiological hazards and radiological hazards in the context of operator dose relative to emergency dose limits. The paper will discuss the overall methodology, findings and recommendations. (author)

  12. Plant habitability assessment for Point Lepreau Generating Station during a severe accident resulting from station blackout conditions

    Energy Technology Data Exchange (ETDEWEB)

    Mullin, D., E-mail: dmullin@nbpower.com [New Brunswick Power Corporation, Point Lepreau Generating Station, Lepreau, NB (Canada)

    2015-07-01

    In response to the CNSC Fukushima Action Plan, the CANDU Owners Group (COG) developed a methodology for assessing nuclear power plant habitability under Joint Project 4426 and to determine if any improvement actions are necessary to provide a high degree of assurance that a severe accident can be managed from a human and organizational performance perspective. NB Power has applied the methodology considering a station black-out scenario (representative case), and assessed the effects of non-radiological hazards and radiological hazards in the context of operator dose relative to emergency dose limits. The paper will discuss the overall methodology, findings and recommendations. (author)

  13. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1997)

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1997 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1997; (4) Capital construction; (5) Nuclear safety; (6) Radiation safety; (7) Work safety and health protection at work; (9) Fire protection; (10) Units upgrading - safety measures; (11) Maintenance; (12) Operation; (13) Environmental impacts of operations; (14) List of balances; (15) Human sources; (16) International co-operation; (17) Public relations

  14. Modern power station practice mechanical boilers, fuel-, and ash-handling plant

    CERN Document Server

    Sherry, A; Cruddace, AE

    2014-01-01

    Modern Power Station Practice, Second Edition, Volume 2: Mechanical (Boilers, Fuel-, and Ash-Handling Plant) focuses on the design, manufacture and operation of boiler units and fuel-and ash-handling plants.This book is organized into five main topics-furnace and combustion equipment, steam and water circuits, ancillary plant and fittings, dust extraction and draught plant, and fuel-and ash-handling plant.In these topics, this text specifically discusses the influence of nature of coal on choice of firing equipment; oil-burner arrangements, ignition and control; disposition of the heating surf

  15. An electron beam flue gas treatment plant for a coal fired thermal power station. EBA demonstration plant in Chengdu thermal power station (China EBA Project)

    International Nuclear Information System (INIS)

    Doi, Yoshitaka; Nakanishi, Ikuo; Shi, Jingke

    1999-01-01

    Ebara's electron beam flue gas treatment plant was installed and is being demonstrated in Chengdu Thermal Power Station, Sichuan, China. The demonstration is proving that this plant is fully capable of meeting the target removal of sulfur dioxides from flue gas (flow rate : 300-thousand m 3 /h). Recovered by-products, namely ammonium sulfate and ammonium nitrate, from the treatment were actually tested as fertilizers, the result of which was favorable. The sale and distribution of these by-products are already underway. In May 1995, this plant was presented the certificate of authorization by China's State Power Corporation. It is noted that this was the first time a sulfur dioxide removal plant was certified as such in China. (author)

  16. Re-evaluation of Station Blackout in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eunchan; Shin, Taeyoung [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

    2014-05-15

    This paper proposes a reduction of the uncertainty due to the small number of LOOP events and an estimation of the non-recovery probability after a LOOP event where the operators fail to energize a safety bus using the offsite power recovery during an SBO with recent operating experience. In addition, in this analysis, the CDF is re-evaluated through reflecting the enhancement of the Class-1E battery capacity. For newly constructed KHNP plants, the LOOP frequency and non-recovery probability after a LOOP during an SBO were re-evaluated through integrating the KHNP events into generic data containing broader experiences for PSA. For an initiating event frequency, a new LOOP frequency was calculated through a Bayesian update of the KHNP LOOP frequency using NUREG/CR-6890, which reflects the recent trends and has a large data size. For the non-recovery probability estimation, domestic data were added to the American experiences in the NUREG/CR-6890; these data were fitted to a lognormal distribution in order to reduce the uncertainty due to the small size of the KHNP data. Regarding the battery capacity enhancement, the success criteria during an SBO were re-evaluated considering the longer battery duty time. The CDF was recalculated using the resultant available time for operator action. The changed CDF was reduced by approximately 50% compared with the value before battery improvement. In conclusion, it was quantitatively proven that enlarging the battery capacity to manage SBOs positively affected plant safety. In addition, methods to improve data uncertainty due to the small number of experiences were selected in order to evaluate the LOOP frequency and non-recovery probability after a LOOP for future plants. These efforts contribute to obtaining a realistic risk profile and to prioritizing countermeasures and improvements of vulnerabilities for safety.

  17. Implications of Extension of Station Blackout Cooping Capability on Nuclear Power Plant Safety

    International Nuclear Information System (INIS)

    Volkanovski, Andrija

    2015-01-01

    The safety of the nuclear power plant depends on the availability of the continuous and reliable sources of electrical energy during all modes of operation of the plant. The station blackout corresponds to a total loss of all alternate current (AC) power as a result of complete failure of both offsite and on-site AC power sources. The electricity for the essential systems during station blackout is provided from the batteries installed in the nuclear power plant. The results of the probabilistic safety assessment show that station blackout is one of the main and frequently the dominant contributor to the core damage frequency. Results of the analysis of the implications of the strengthening of the SBO mitigation capability on safety of the NPP will be presented. The assessment is done with state-of-art deterministic and probabilistic methods and tolls with application on reference models of nuclear power plants. The safety analysis is done on reference model of the nuclear power plant. Obtained results show large decrease of the core damage frequency with strengthening of the station blackout mitigation capability. The time extension of blackout coping capability results in the delay of the core heat up for at least the extension time interval. Availability and operation of the steam driven auxiliary feedwater system maintains core integrity up to 72 h after the successful shutdown, even in the presence of the reactor coolant pumps seal leakage. The largest weighted decrease of the core damage frequency considering the costs for the modification is obtained for the modification resulting in extension of the station blackout coping capability. The importance of the common cause failures of the emergency diesel generators for the obtained decrease of the core damage frequency and overall safety of the plant is identified in the obtained results. (authors)

  18. Current experience with central-station nuclear cogeneration plants

    International Nuclear Information System (INIS)

    1981-10-01

    In considering the potential of the HTGR for nuclear cogeneration, a logical element for investigation is the recent history of nuclear cogeneration experience. Little is found in recent literature; however, the twin nuclear cogeneration plant at Midland is nearing completion and this milestone will no doubt be the basis for a number of reports on the unique cogeneration facility and operating experiences with it. Less well known in the US is the Bruce Nuclear Power Development in Ontario, Canada. Originally designed to cogenerate steam for heavy water production, the Bruce facility is the focus of a major initiative to create an energy park on the shores of Lake Huron. To obtain an improved understanding of the status and implications of current nuclear cogeneration experience, GCRA representatives visited the Ontario Hydro offices in Toronto and subsequently toured the Midland site near Midland, Michigan. The primary purpose of this report is to summarize the results of those visits and to develop a series of conclusions regarding the implications for HTGR cogeneration concepts

  19. Bidding Strategy of Virtual Power Plant with Energy Storage Power Station and Photovoltaic and Wind Power

    Directory of Open Access Journals (Sweden)

    Zhongfu Tan

    2018-01-01

    Full Text Available For the virtual power plants containing energy storage power stations and photovoltaic and wind power, the output of PV and wind power is uncertain and virtual power plants must consider this uncertainty when they participate in the auction in the electricity market. In this context, this paper studies the bidding strategy of the virtual power plant with photovoltaic and wind power. Assuming that the upper and lower limits of the combined output of photovoltaic and wind power are stochastically variable, the fluctuation range of the day-ahead energy market and capacity price is stochastically variable. If the capacity of the storage station is large enough to stabilize the fluctuation of the output of the wind and photovoltaic power, virtual power plants can participate in the electricity market bidding. This paper constructs a robust optimization model of virtual power plant bidding strategy in the electricity market, which considers the cost of charge and discharge of energy storage power station and transmission congestion. The model proposed in this paper is solved by CPLEX; the example results show that the model is reasonable and the method is valid.

  20. Nuclear Power Station Kalkar, 300 MWe Prototype Nuclear Power Plant with Fast Sodium Cooled Reactor (SNR-300), Plant description

    International Nuclear Information System (INIS)

    1984-06-01

    The nuclear power station Kalkar (SNR-300) is a prototype with a sodium cooled fast reactor and a thermal power of 762 MW. The present plant description has been made available in parallel to the licensing procedure for the reactor plant and its core Mark-Ia as supplementary information for the public. The report gives a detailed description of the whole plant including the prevention measures against the impact of external and plant internal events. The radioactive materials within the reactor cooling system and the irradiation protection and surveillance measures are outlined. Finally, the operation of the plant is described with the start-up procedures, power operation, shutdown phases with decay heat removal and handling procedures

  1. Water electrolysis plants for hydrogen and oxygen production. Shipped to Tsuruga Power Station Unit No.1, and Tokai No.2 power station, the Japan Atomic Power Co

    International Nuclear Information System (INIS)

    Ueno, Syuichi; Sato, Takao; Ishikawa, Nobuhide

    1997-01-01

    Ebara's water electrolysis plants have been shipped to Tsuruga Power Station Unit No.1, (H 2 generation rate: 11 Nm 3 /h), and Tokai No.2 Power Station (H 2 generation rate: 36 Nm 3 /h), Japan Atomic Power Co. An outcome of a business agreement between Nissho Iwai Corporation and Norsk Hydro Electrolysers (Norway), this was the first time that such water electrolysis plants were equipped in Japanese boiling water reactor power stations. Each plant included an electrolyser (for generating hydrogen and oxygen), an electric power supply, a gas compression system, a dehumidifier system, an instrumentation and control system, and an auxiliary system. The plant has been operating almost continuously, with excellent feedback, since March 1997. (author)

  2. The AP1000R nuclear power plant innovative features for extended station blackout mitigation

    International Nuclear Information System (INIS)

    Vereb, F.; Winters, J.; Schulz, T.; Cummins, E.; Oriani, L.

    2012-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-01

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

  4. Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

    International Nuclear Information System (INIS)

    1987-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

  5. Pumping station design for a pumped-storage wind-hydro power plant

    International Nuclear Information System (INIS)

    Anagnostopoulos, John S.; Papantonis, Dimitris E.

    2007-01-01

    This work presents a numerical study of the optimum sizing and design of a pumping station unit in a hybrid wind-hydro plant. The standard design that consists of a number of identical pumps operating in parallel is examined in comparison with two other configurations, using one variable-speed pump or an additional set of smaller jockey pumps. The aim is to reduce the amount of the wind generated energy that cannot be transformed to hydraulic energy due to power operation limits of the pumps and the resulting step-wise operation of the pumping station. The plant operation for a period of one year is simulated by a comprehensive evaluation algorithm, which also performs a detailed economic analysis of the plant using dynamic evaluation methods. A preliminary study of the entire plant sizing is carried out at first using an optimization tool based on evolutionary algorithms. The performance of the three examined pumping station units is then computed and analyzed in a comparative study. The results reveal that the use of a variable-speed pump constitutes the most effective and profitable solution, and its superiority is more pronounced for less dispersed wind power potential

  6. Hinkley Point 'C' power station public inquiry: proof of evidence on plant parameters

    International Nuclear Information System (INIS)

    George, B.V.

    1988-09-01

    A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom. The overall economics of a nuclear power station depends on many factors which are determined by the design; the effectiveness with which the station is constructed; and the performance of the plant. In this respect the most significant factors are: construction time; capital cost; availability of the plant to produce electricity, taking account of those outages due to either planned or unplanned shutdowns; net electrical power output; and the working life of the plant. In this evidence to the Inquiry, the basis for the values chosen as ''targets'' for these parameters in the design of the plant and the control of the project is set out. The adjustment of the parameters to make them suitable for economic appraisal is explained. The design and project management arrangements are described. (author)

  7. Some environmental effects of emissions from CANDU nuclear generating stations and heavy water plants

    International Nuclear Information System (INIS)

    Effer, W.R.

    Non-radioactive releases during normal operation of Ontario Hydro's nuclear generating stations and heavy water plants are summarized and related to existing regulations and guidelines. Low-grade heat in the circulating cooling water discharge is the most important of the non-radioactive effluents. Some of the hydrological, biological and water quality aspects of thermal discharges are discussed in relation to the operation of Ontario Hydro's thermal generating stations on the Great Lakes. Chemical releases to air or water include chlorine, hydrogen sulphide, water treatment plant effluents, oily waste water and sewage lagoon effluents. The significance of the first two of these releases to the environment is reviewed, particularly in relation to Great Lakes water quality and biological concerns. (author)

  8. Water management requirements for animal and plant maintenance on the Space Station

    Science.gov (United States)

    Johnson, C. C.; Rasmussen, D.; Curran, G.

    1987-01-01

    Long-duration Space Station experiments that use animals and plants as test specimens will require increased automation and advanced technologies for water management in order to free scientist-astronauts from routine but time-consuming housekeeping tasks. The three areas that have been identified as requiring water management and that are discusseed are: (1) drinking water and humidity condensate of the animals, (2) nutrient solution and transpired water of the plants, and (3) habitat cleaning methods. Automation potential, technology assessment, crew time savings, and resupply penalties are also discussed.

  9. Darlington tritium removal facility and station upgrading plant dynamic process simulation

    International Nuclear Information System (INIS)

    Busigin, A.; Williams, G. I. D.; Wong, T. C. W.; Kulczynski, D.; Reid, A.

    2008-01-01

    Ontario Power Generation Nuclear (OPGN) has a 4 x 880 MWe CANDU nuclear station at its Darlington Nuclear Div. located in Bowmanville. The station has been operating a Tritium Removal Facility (TRF) and a D 2 O station Upgrading Plant (SUP) since 1989. Both facilities were designed with a Distributed Control System (DCS) and programmable logic controllers (PLC) for process control. This control system was replaced with a DCS only, in 1998. A dynamic plant simulator was developed for the Darlington TRF (DTRF) and the SUP, as part of the computer control system replacement. The simulator was used to test the new software, required to eliminate the PLCs. The simulator is now used for operator training and testing of process control software changes prior to field installation. Dynamic simulation will be essential for the ITER isotope separation system, where the process is more dynamic than the relatively steady-state DTRF process. This paper describes the development and application of the DTRF and SUP dynamic simulator, its benefits, architecture, and the operational experience with the simulator. (authors)

  10. Probabilistic assessment of Juragua Nuclear Power Plant response under station blackout conditions

    International Nuclear Information System (INIS)

    Valhuerdi, C.; Vilaragut, J.J.; Perdomo, M.; Torres, A.

    1995-01-01

    The preliminary results concerning the response of station blackout are shown in this paper. These results have been obtained in the framework of initiator lass of external electrical supply as a aport of the revision o of the current probabilistic safety analysis. The work is also based on the results reported in the thermohydraulic calculations of VVER 440 plants responses under these conditions and the experience of this type of notified incidents. Finally, a comparative analysis with the results obtained for other reactor technologies is presented

  11. Large Plant Growth Chambers: Flying Soon on a Space Station near You!

    Science.gov (United States)

    Massa, Gioia D.; Morrow, Robert C.; Levine, Howard G.

    2014-01-01

    The International Space Station (ISS) now has platforms for conducting research on horticultural plant species, and those capabilities continue to grow. The Veggie vegetable production system will be deployed to the ISS in Spring of 2014 to act as an applied research platform with goals of studying food production in space, providing the crew with a source of fresh food, allowing behavioral health and plant microbiology experimentation, and being a source of recreation and enjoyment for the crew. Veggie was conceived, designed, and constructed by Orbital Technologies Corporation (ORBITEC, Madison, WI). Veggie is the largest plant growth chamber that NASA has flown to date, and is capable of growing a wide array of horticultural crops. It was designed for low energy usage, low launch mass and stowage volume, and minimal crew time requirements. The Veggie flight hardware consists of a light cap containing red (630 nanometers), blue, (455 nanometers) and green (530 nanometers) light emitting diodes. Interfacing with the light cap is an extendable bellows baseplate secured to the light cap via magnetic closures and stabilized with extensible flexible arms. The baseplate contains vents allowing air from the ISS cabin to be pulled through the plant growth area by a fan in the light cap. The baseplate holds a Veggie root mat reservoir that will supply water to plant pillows attached via elastic cords. Plant pillows are packages of growth media and seeds that will be sent to ISS dry and installed and hydrated on orbit. Pillows can be constructed in various sizes for different plant types. Watering will be via passive wicking from the root mat to the pillows. Science procedures will include photography or videography, plant thinning, pollination, harvesting, microbial sampling, water sampling, etcetera. Veggie is one of the ISS flight options currently available for research investigations on plants. The Plant Habitat (PH) is being designed and constructed through a NASA

  12. The effects of fouled anion resin on condensate polishing plant performance at Dungeness B power station

    International Nuclear Information System (INIS)

    Bates, Chris

    2008-01-01

    The return to power, after an outage, at Dungeness B Power Station was delayed because of problems in achieving an in-specification feedwater acid conductivity. Dungeness B has a full flow cation/mixed bed condensate polishing plant (CPP). Investigations showed that the acid conductivity was produced by carbon dioxide and organic impurities both by-passing the CPP and slipping through it. Resin analysis showed that the anion resin had severely impaired sulfate removal kinetics. The paper covers the work done to try and identify the nature and source of the organics and their effect on the anion resin. One significant finding was that the carbonate removal kinetics were as impaired as those for sulfate removal; this had not been previously experienced in the CPP at any British Energy plant. (orig.)

  13. Potential of ORC Systems to Retrofit CHP Plants in Wastewater Treatment Stations

    Directory of Open Access Journals (Sweden)

    Ricardo Chacartegui

    2013-12-01

    Full Text Available Wastewater treatment stations take advantage of the biogas produced from sludge in anaerobic digesters to generate electricity (reciprocating gas engines and heat (cooling water and engine exhaust gases. A fraction of this electricity is used to operate the plant while the remaining is sold to the grid. Heat is almost entirely used to support the endothermic anaerobic digestion and a minimum fraction of it is rejected to the environment at a set of fan coolers. This generic description is applicable to on-design conditions. Nevertheless, the operating conditions of the plant present a large seasonal variation so it is commonly found that the fraction of heat rejected to the atmosphere increases significantly at certain times of the year. Moreover, the heat available in the exhaust gases of the reciprocating engine is at a very high temperature (around 650 oC, which is far from the temperature at which heat is needed for the digestion of sludge (around 40 oC in the digesters. This temperature difference offers an opportunity to introduce an intermediate system between the engines and the digesters that makes use of a fraction of the available heat to convert it into electricity. An Organic Rankine Cycle (ORC with an appropriate working fluid is an adequate candidate for these hot/cold temperature sources. In this paper, the techno-economic effect of adding an Organic Rankine Cycle as the intermediate system of an existing wastewater treatment station is analysed. On this purpose, different working fluids and system layouts have been studied for a reference wastewater treatment station giving rise to optimal systems configurations. The proposed systems yield very promising results with regard to global efficiency and electricity production (thermodynamically and economically.

  14. Towards a Perron--Frobenius Theory for Eventually Positive Operators

    OpenAIRE

    Glück, Jochen

    2016-01-01

    This article is a contribution to the spectral theory of so-called eventually positive operators, i.e.\\ operators $T$ which may not be positive but whose powers $T^n$ become positive for large enough $n$. While the spectral theory of such operators is well understood in finite dimensions, the infinite dimensional case has received much less attention in the literature. We show that several sensible notions of "eventual positivity" can be defined in the infinite dimensional setting, and in con...

  15. Comparison and evaluation of nuclear power plant options for geosynchronous power stations

    International Nuclear Information System (INIS)

    Williams, J.R.

    1975-01-01

    A solution to the safety, safeguards, and radwaste disposal problems of nuclear power is to locate the breeder reactor power plants far out in geosynchronous orbit and beam the power to earth with microwaves. The generation of nuclear power in space is technologically feasible and has already been demonstrated on a small scale. It has also been shown that high efficiency microwave transmission of power from synchronous orbit to earth is feasible and is not hazardous. The reactor safety problem would be virtually eliminated because of the remoteness of the satellite power station in geosynchronous orbit. The worst possible accident at such a plant would have negligible effect on the earth, certainly less than the high altitude nuclear explosions which have been conducted in the past. Accidental re-entry from geosynchronous orbit could not occur because of the very large velocity change required. The safeguards problem can be virtually eliminated by adopting the following procedures: 1) The plant is initially started up using U-235 fuel or bred plutonium or U-233 from another geosynchronous power plant, 2) Once the plant is operating, only nonhazardous fertile materials (thorium or depleted uranium) are shipped up from earth, 3) The fissile fuel is bred and used in space, and none of this highly toxic fissile material is ever returned to earth. The radioactive waste could be concentrated and ejected in canisters into deep space away from the earth. The geosynchronous nuclear power plant offers unlimited nuclear power without nuclear hazards or nuclear pollution, but at somewhat higher cost. Whether or not society will be willing to pay these higher costs of nuclear power from space, or whether new energy resources such as nuclear fusion or solar power become feasible, remains to be seen. A prudent course to follow would be to give careful consideration to all future options for large scale energy generation, including the option of nuclear power from space

  16. The effects of local control station design variation on plant risk

    International Nuclear Information System (INIS)

    O'Hara, J.

    1989-01-01

    The existence of human engineering deficiencies at local control stations (LCSs) was addressed in a study (NUREG/CR-3696) conducted by the Pacific Northwest Laboratory (PNL). PNL concluded that the existence of these human factors deficiencies at safety significant LCSs increases the potential for operator errors that could be detrimental to plant and public safety. However, PNL did not specific analysis to evaluate the effects of LCS design variations on human performance, on plant risk, or on the cost benefit feasibility of upgrading LCSs. The purpose of the present investigation was to conduct such an analysis. The specific objectives of the research were (1) to further define important local control stations, human factors related LCS design variations, and typical human engineering deficiencies (HEDs) at LCSs; (2) to determine the effect of LCS design variations on human performance, i.e., on risk-significant human errors (HEs); (3) to determine the effect of LCS-induced human performance variation on plant risk as measured by core melt frequency (CMF); and (4) to determine whether LCS improvements (upgrades in LCS design to mitigate HEDs) are feasible in a scoping-type value-impact analysis. The results can be summarized as follows. There was an overall effect of LCS variations on human performance. The transition from the worst LCS configuration to the best resulted in an absolute reduction or improvement of 0.82 in mean HEP (reduction by a factor of 20). The transition from low to high levels of FC was associated with a 0.46 (86%) reduction in mean HEP. The majority of the effect was accounted for in the transition from the low to medium levels. The Panel Design dimension also had an effect on human performance although not as large as functional centralization. Upgrading from a low to high panel design resulted in a 0.29 (69%) reduction in mean HEP

  17. Ion exchange substrates for plant cultivation in extraterrestrial stations and space crafts

    Science.gov (United States)

    Soldatov, Vladimir

    2012-07-01

    Ion exchange substrates Biona were specially designed at the Belarus Academy of Sciences for plants cultivation in spacecrafts and extraterrestrial stations. The first versions of such substrates have been successfully used in several space experiments and in a long-term experiment in which three soviet test-spacemen spent a full year in hermetic cabin imitating a lunar station cabin (1067-1968). In this experiment the life support system included a section with about one ton of the ion exchange substrate, which was used to grow ten vegetations of different green cultures used in the food of the test persons. Due to failure of a number of Soviet space experiments, decay of the Soviet Union and the following economic crisis the research in this field carried out in Belarus were re-directed to the needs of usual agriculture, such as adaptation of cell cultures, growing seedlings, rootage of cuttings etc. At present ion exchange substrate Biona are produced in limited amounts at the experimental production plant of the Institute of Physical Organic Chemistry and used in a number of agricultural enterprises. New advanced substrates and technologies for their production have been developed during that time. In the presentation scientific principles of preparation and functioning of ion exchange substrates as well as results of their application for cultivation different plants are described. The ion exchange substrate is a mixture of cation and anion exchangers saturated in a certain proportions with all ions of macro and micro elements. These chemically bound ions are not released to water and become available for plants in exchange to their root metabolites. The substrates contain about 5% mass of nutrient elements far exceeding any other nutrient media for plants. They allow generating 3-5 kg of green biomass per kilogram of substrate without adding any fertilizers; they are sterile by the way of production and can be sterilized by usual methods; allow regeneration

  18. Plant Operation Station for HTR-PM Low Power and Shutdown operation Probabilistic safety analysis

    International Nuclear Information System (INIS)

    Liu Tao; Tong Jiejuan

    2014-01-01

    Full range Probabilistic safety analysis (PSA) is one of key conditions for nuclear power plant (NPP) licensing according to the requirement of nuclear safety regulatory authority. High Temperature Gas Cooled Reactor Pebble-bed Module (HTR-PM) has developed construction design and prepared for the charging license application. So after the normal power operation PSA submitted for review, the Low power and Shutdown operation Probabilistic safety analysis (LSPSA) also begin. The results of LSPSA will together with prior normal power PSA results to demonstrate the safety level of HTR-PM NPP Plant Operation Station (POS) is one of important terms in LSPSA. The definition of POS lays the foundation for LSPSA modeling. POS provides initial and boundary conditions for the following event tree and fault tree model development. The aim of this paper is to describe the state-of-the-art of POS definition for HTR-PM LSPSA. As for the first attempt to the high temperature gas cooled reactor module plant, the methodology and procedure of POS definition refers to the LWR LSPSA guidance, and adds to plant initial status analysis due to the HTR-PM characteristics. A specific set of POS grouping vectors is investigate and suggested for HTR-PM NPP, which reflects the characteristics of plant modularization and on-line refueling. As a result, seven POSs are given according to the grouping vectors at the end of the paper. They will be used to the LSPSA modelling and adjusted if necessary. The papers ’work may provide reference to the analogous NPP LSPSA. (author)

  19. CNSS plant concept, capital cost, and multi-unit station economics

    Energy Technology Data Exchange (ETDEWEB)

    1984-07-01

    United Engineers and Constructors (UE and C) and the Babcock and Wilcox Company (B and W) have performed several studies over the last eight years related to small integral pressurized water reactors. These reactors include the 365 MWt (100 MWe) Consolidated Nuclear Steam Generator (CNSG) and the 1200 MWt Consolidated Nuclear Steam System (CNSS). The studies, mostly performed under contract to the Oak Ridge National Laboratory, have led to a 1250 MWt (400 MWe) Consolidated Nuclear Steam System (CNSS) plant concept, with unique design and cost features. This report contains an update of earlier studies of the CNSS reactor and balance-of-plant concept design, capital costs, and multi-unit plant economics incorporating recent design developments, improvements, and post-TMI-2 upgrades. The economic evaluation compares the total system economic impact of a phased, three stage 400 MWe CNSS implementation program, i.e., a three-unit station, to the installation of a single 1200 MWe Pressurized Water Reactor (PWR) into a typical USA utility system.

  20. CNSS plant concept, capital cost, and multi-unit station economics

    International Nuclear Information System (INIS)

    1984-07-01

    United Engineers and Constructors (UE and C) and the Babcock and Wilcox Company (B and W) have performed several studies over the last eight years related to small integral pressurized water reactors. These reactors include the 365 MWt (100 MWe) Consolidated Nuclear Steam Generator (CNSG) and the 1200 MWt Consolidated Nuclear Steam System (CNSS). The studies, mostly performed under contract to the Oak Ridge National Laboratory, have led to a 1250 MWt (400 MWe) Consolidated Nuclear Steam System (CNSS) plant concept, with unique design and cost features. This report contains an update of earlier studies of the CNSS reactor and balance-of-plant concept design, capital costs, and multi-unit plant economics incorporating recent design developments, improvements, and post-TMI-2 upgrades. The economic evaluation compares the total system economic impact of a phased, three stage 400 MWe CNSS implementation program, i.e., a three-unit station, to the installation of a single 1200 MWe Pressurized Water Reactor (PWR) into a typical USA utility system

  1. The Palo Verde story: a foundation for future multi-station nuclear power plants

    International Nuclear Information System (INIS)

    Brunt, Jr.E.E.Van; Ferguson, C.

    1987-01-01

    In 1973, the design and planning for the Palo Verde Nuclear Generating Station Was started featuring three 3800 MWt Combustion Engineering Standard System 80 Nuclear Steam Supply Systems. Arizona Public Service Company (APS) was the Project Manager and Operating Agent and Bechtel Power Corporation the architect/engineer and constructor. The Palo Verde units are located in a desert environment some 50 miles west of Phoenix, Arizona. It is a 'dry site' in that there are no liquid discharges from the site. The cooling tower makeup water sewage is waste effluent from the City of Phoenix treated at an on site reclamation facility. The effluent has had primary and secondary treatment at the Phoenix plant prior to delivery to PVNGS. The units are physically separate from each other but are of identical design. There are no shared safety systems between the units. Unit 1 and Unit 2 are both in commercial operation (January, 1986 and September, 1986 respectively). Unit 3 is scheduled to load fuel late in the first quarter of 1987. This paper presents some of the engineering and management practices used during design, construction, and startup and operational experiences and other unique features of this multi-unit nuclear station. The site arrangement is shown in Figure 1

  2. Summary of plant life management evaluation for Onagawa Nuclear Power Station Unit-1

    International Nuclear Information System (INIS)

    Nodate, Kazumi

    2014-01-01

    The Onagawa Nuclear Power Station Unit-1 (Onagawa NPS-1) began commercial operation on June 1, 1984, and has reached 30-year from starting of operation on June of 2014. To that end, we implemented the Plant Life Management (PLM) evaluation for Onagawa NPS-1 as our first experience. We decided on a Long-term Maintenance Management Policy from result of the evaluation, and then applied the Safety-Regulations change approval application on November 6, 2013 and its correcting application on April 16, 2014. Our application was approved on May 21, 2014 through investigation by the Nuclear Regulatory Agency. Also at implementation of the PLM evaluation, we considered effects of the Great East Japan Earthquake that occurred on March 11, 2011 against ageing phenomena. In this paper, we introduce summary of PLM evaluation for Onagawa NPS-1 and the evaluation that considered effects of the Great East Japan Earthquake. (author)

  3. Potential human factors deficiencies in the design of local control stations and operator interfaces in nuclear power plants

    International Nuclear Information System (INIS)

    Hartley, C.S.; Levy, I.S.; Fecht, B.A.

    1984-04-01

    The Pacific Northwest Laboratory has completed a project to identify human factors deficiencies in safety-significant control stations outside the control room of a nuclear power plant and to determine whether NUREG-0700, Guidelines for Control Room Design Reviews, would be sufficient for reviewing those local control stations (LCSs). The project accomplished this task by first, reviewing existing data pertaining to human factors deficiencies in LCSs involved in significant safety actions; second, surveying LCSs environments and design features at several operating nuclear power plants; and third, assessing the results of that survey relative to the contents of NUREG-0700

  4. Thermal-hydraulic analysis of NSSS and containment response during extended station blackout for Maanshan PWR plant

    Energy Technology Data Exchange (ETDEWEB)

    Yuann, Yng-Ruey, E-mail: ryyuann@iner.gov.tw; Hsu, Keng-Hsien, E-mail: hardlycampus@iner.gov.tw; Lin, Chin-Tsu, E-mail: jtling@iner.gov.tw

    2015-07-15

    Highlights: • Calculate NSSS and containment transient response during extended SBO of 24 h. • RELAP5-3D and GOTHIC models are developed for Maanshan PWR plant. • Reactor coolant pump seal leakage is specifically modeled for each loop. • Analyses are performed with and without secondary-side depressurization, respectively. • Considering different total available time for turbine driven auxiliary feedwater system. - Abstract: A thermal-hydraulic analysis has been performed with respect to the response of the nuclear steam supply system (NSSS) and the containment during an extended station blackout (SBO) duration of 24 h in Maanshan PWR plant. Maanshan plant is a Westinghouse three-loop PWR design with rated core thermal power of 2822 MWt. The analyses in the NSSS and the containment are based on the RELAP5-3D and GOTHIC models, respectively. Important design features of the plant in response to SBO are considered in the respective models, e.g., the steam generator PORVs, turbine driven auxiliary feedwater system (TDAFWS), accumulators, reactor coolant pump (RCP) seal design, various heat structures in the containment, etc. In the analysis it is assumed that the shaft seal in each RCP failed due to loss of seal cooling and the RCS fluid flows to the containment directly. Some parameters calculated from the RELPA5-3D model are input to the containment GOTHIC model, including the RCS average temperature and the RCP seal leakage flow and enthalpy. The RCS average temperature is used to drive the sensible heat transfer to the containment. It is found that the severity of the event depends mainly on whether the secondary side is depressurized or not. If the secondary side is depressurized in time (within 1 h after SBO) and the TDAFWS is available greater than 19 h, then the reactor core will be covered with water throughout the SBO duration, which ensures the integrity of the reactor core. On the contrary, if the secondary side is not depressurized, then the RCS

  5. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant

    Energy Technology Data Exchange (ETDEWEB)

    Hsu, Keng-Hsien; Yuann, Yng-Ruey; Lin, Ansheng [Atomic Energy Council, Taoyuan City, Taiwan (China). Inst. of Nuclear Energy Research

    2017-11-15

    The Fukushima Daiichi accident occurring on March 11, 2011, reveals that Station Blackout (SBO) may last longer than 8 h. However, the original design may not have sufficient capacity to cope with a SBO for more than 8 h. In view of this, Taiwan Power Company has initiated several enhancements to mitigate the severity of the extended SBO. Based on the improved plant configuration, a SBO coping analysis is performed in this study to assess whether the Kuosheng BWR plant has sufficient capability to cope with SBO for 24 h with respect to maintaining the integrity of the reactor core and containment. The analyses in the Nuclear Steam Supply System (NSSS) and the containment are based on the RETRAN-3D and GOTHIC models, respectively. The flow conditions calculated by RETRAN-3D during the event are retrieved and input to the GOTHIC containment model to determine the containment pressure and temperature response. These boundary conditions include SRV flow rate, SRV flow enthalpy, and total reactor coolant system leakage flow rate.

  6. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant

    International Nuclear Information System (INIS)

    Hsu, Keng-Hsien; Yuann, Yng-Ruey; Lin, Ansheng

    2017-01-01

    The Fukushima Daiichi accident occurring on March 11, 2011, reveals that Station Blackout (SBO) may last longer than 8 h. However, the original design may not have sufficient capacity to cope with a SBO for more than 8 h. In view of this, Taiwan Power Company has initiated several enhancements to mitigate the severity of the extended SBO. Based on the improved plant configuration, a SBO coping analysis is performed in this study to assess whether the Kuosheng BWR plant has sufficient capability to cope with SBO for 24 h with respect to maintaining the integrity of the reactor core and containment. The analyses in the Nuclear Steam Supply System (NSSS) and the containment are based on the RETRAN-3D and GOTHIC models, respectively. The flow conditions calculated by RETRAN-3D during the event are retrieved and input to the GOTHIC containment model to determine the containment pressure and temperature response. These boundary conditions include SRV flow rate, SRV flow enthalpy, and total reactor coolant system leakage flow rate.

  7. Risk-informed profitability-based analysis support of nuclear power station balance-of-plant change management

    Energy Technology Data Exchange (ETDEWEB)

    Liming, J.K. [EQE International, Inc., An ABS Group Company, Irvine, CA (United States); Kee, E.J.; Grantom, C.R.; Richards, A.M. [STP Nuclear Operating Company, Wadsworth, TX (United States)

    2001-07-01

    In this paper, a three-phased method is proposed for the STP Nuclear Operating Company (STPNOC) Risk and Reliability Analysis Section (RRA) to perform analyses and decision-making support for the STPNOC Balance-of-Plant (BOP)Task Force in managing change to simultaneously optimize plant safety and maximize long-term return-on-asset (or profitability) for the South Texas Project Electric Generating Station (STPEGS). (authors)

  8. Risk-informed profitability-based analysis support of nuclear power station balance-of-plant change management

    International Nuclear Information System (INIS)

    Liming, J.K.; Kee, E.J.; Grantom, C.R.; Richards, A.M.

    2001-01-01

    In this paper, a three-phased method is proposed for the STP Nuclear Operating Company (STPNOC) Risk and Reliability Analysis Section (RRA) to perform analyses and decision-making support for the STPNOC Balance-of-Plant (BOP)Task Force in managing change to simultaneously optimize plant safety and maximize long-term return-on-asset (or profitability) for the South Texas Project Electric Generating Station (STPEGS). (authors)

  9. Monitoring equipment environment during nuclear plant operation at Salem and Hope Creek generating stations

    International Nuclear Information System (INIS)

    Blum, A.; Smith, R.J.

    1991-01-01

    Monitoring of environmental parameters has become a significant issue for operating nuclear power plants. While the long-term benefits of plant life extension programs are being pursued with comprehensive environmental monitoring programs, the potential effect of local hot spots at various plant locations needs to be evaluated for its effect on equipment degradation and shortening of equipment qualified life. A significant benefit can be experienced from temperature monitoring when a margin exists between the design versus actual operating temperature. This margin can be translated into longer equipment qualified life and significant reduction in maintenance activities. At PSE and G, the immediate need for monitoring environmental parameters is being accomplished via the use of a Logic Beach Bitlogger. The Bitlogger is a portable data loggings system consisting of a system base, input modules and a communication software package. Thermocouples are installed on selected electrical equipment and cables are run from the thermocouples to the input module of the Bitlogger. Temperature readings are taken at selected intervals, stored in memory, and downloaded periodically to a PC software program, i.e., Lotus. The data is formatted into tabular or graphical documents. Because of their versatility, Bitloggers are being used differently at the authors Nuclear facility. At the Salem Station (2 Units-4 loop Westinghouse PWR), a battery powered, fully portable, calibrated Bitlogger is located in an accessible area inside Containment where it monitors the temperature of various electrical equipment within the Pressurizer Enclosure. It is planned that close monitoring of the local hot spot temperatures in this area will allow them to adjust and reconcile the environmental qualification of the equipment

  10. The "Martian" flora: new collections of vascular plants, lichens, fungi, algae, and cyanobacteria from the Mars Desert Research Station, Utah

    Science.gov (United States)

    Freebury, Colin E.; Hamilton, Paul B.; Saarela, Jeffery M.

    2016-01-01

    Abstract The Mars Desert Research Station is a Mars analog research site located in the desert outside of Hanksville, Utah, U.S.A. Here we present a preliminary checklist of the vascular plant and lichen flora for the station, based on collections made primarily during a two-week simulated Mars mission in November, 2014. Additionally, we present notes on the endolithic chlorophytes and cyanobacteria, and the identification of a fungal genus also based on these collections. Altogether, we recorded 38 vascular plant species from 14 families, 13 lichen species from seven families, six algae taxa including both chlorophytes and cyanobacteria, and one fungal genus from the station and surrounding area. We discuss this floristic diversity in the context of the ecology of the nearby San Rafael Swell and the desert areas of Wayne and Emery counties in southeastern Utah. PMID:27350765

  11. Station blackout transient at the Browns Ferry Unit 1 Plant: a severe accident sequence analysis (SASA) program study

    International Nuclear Information System (INIS)

    Schultz, R.R.

    1982-01-01

    Operating plant transients are of great interest for many reasons, not the least of which is the potential for a mild transient to degenerate to a severe transient yielding core damage. Using the Browns Ferry (BF) Unit-1 plant as a basis of study, the station blackout sequence was investigated by the Severe Accident Sequence Analysis (SASA) Program in support of the Nuclear Regulatory Commission's Unresolved Safety Issue A-44: Station Blackout. A station blackout transient occurs when the plant's AC power from a comemrcial power grid is lost and cannot be restored by the diesel generators. Under normal operating conditions, f a loss of offsite power (LOSP) occurs [i.e., a complete severance of the BF plants from the Tennessee Valley Authority (TVA) power grid], the eight diesel generators at the three BF units would quickly start and power the emergency AC buses. Of the eight diesel generators, only six are needed to safely shut down all three units. Examination of BF-specific data show that LOSP frequency is low at Unit 1. The station blackout frequency is even lower (5.7 x 10 - 4 events per year) and hinges on whether the diesel generators start. The frequency of diesel generator failure is dictated in large measure by the emergency equipment cooling water (EECW) system that cools the diesel generators

  12. The 10 MWe Solar Thermal Central Receiver Pilot Plant: Solar facilities design integration. Pilot-plant station manual (RADL Item 2-1). Volume 1: System description

    Science.gov (United States)

    1982-09-01

    The complete Barstow Solar Pilot Plant is described. The plant requirements and general description are presented, the mechanical, electric power, and control and instrumentation systems as well as civil engineering and structural aspects and the station buildings are described. Included in the mechanical systems are the heliostats, receiver, thermal storage system, beam characterization system, steam, water, nitrogen, and compressed air systems, chemical feed system, fire protection system, drains, sumps and the waste disposal systems, and heating, ventilating, and air conditioning systems.

  13. Performance Evaluation of wastewater treatment plant of Noosh Azar company by online monitoring station

    Directory of Open Access Journals (Sweden)

    leila haddadi

    2018-02-01

    Full Text Available Background& Objective: One of the reuses of wastewater in industries is irrigation of green space. Therefore, with proper treatment and reduction of environmental pollution of wastewater and in compliance with environmental standards, it can be used for irrigation purposes. The present study was aimed to evaluate the performance of Noosh Azar Wastewater Treatment Plant by the online monitoring station in 2016.   Materials and Methods: This descriptive cross-sectional study was performed at Noosh Azar Waste Water Treatment Plant (WWTP in Tehran. The effluent outlet parameters include COD, BOD, TSS, TOC, Turbidity, pH and temperature which were measured 12 times/day by the online monitoring station of the refinery according to the standard methods (the Examinations of Water and Wastewater, and reported at the end of each month. Data were entered into SPSS software and analyzed using statistical indices including mean and standard deviation. Results: The average total of BOD/COD ratio in the wastewater was 0.8. The results of the study showed that the average concentration of COD, BOD and TSS of the wastewater was 1624.91 ±134.85, 1310±75.38 and 283.58± 39.76 mg/L, respectively. The average of total outlet parameters of turbidity, COD, BOD, TSS and TOC were 12.78±2.21, 83.73±12.90, 41.26±6.65, 6.70±2.14, 46.03±7.08 mg/L, and pH=7.80±0.35. The total average of removal efficiencies of COD, BOD and TSS were 93.92±3.62, 96.57±1.002 and 97.57±0.936, respectively. Conclusion: Regarding the proper performance of the activated sludge system of Noosh Azar Company, the effluent  parameters such as COD, BOD, TSS, TOC, turbidity and pH, were in accordance with the standard of the Iranian Environmental Protection Agency for irrigation use. However in order to ensure the quality of the wastewater for reuse, the microbial parameters should also be considered.

  14. Microbiological Contamination at Workplaces in a Combined Heat and Power (CHP Station Processing Plant Biomass

    Directory of Open Access Journals (Sweden)

    Justyna Szulc

    2017-01-01

    Full Text Available The aim of the study was to evaluate the microbial contamination at a plant biomass processing thermal power station (CHP. We found 2.42 × 103 CFU/m3 of bacteria and 1.37 × 104 CFU/m3 of fungi in the air; 2.30 × 107 CFU/g of bacteria and 4.46 × 105 CFU/g of fungi in the biomass; and 1.61 × 102 CFU/cm2 bacteria and 2.39 × 101 CFU/cm2 fungi in filtering facepiece respirators (FFRs. Using culture methods, we found 8 genera of mesophilic bacteria and 7 of fungi in the air; 10 genera each of bacteria and fungi in the biomass; and 2 and 5, respectively, on the FFRs. Metagenomic analysis (Illumina MiSeq revealed the presence of 46 bacterial and 5 fungal genera on the FFRs, including potential pathogens Candida tropicalis, Escherichia coli, Prevotella sp., Aspergillus sp., Penicillium sp.. The ability of microorganisms to create a biofilm on the FFRs was confirmed using scanning electron microscopy (SEM. We also identified secondary metabolites in the biomass and FFRs, including fumigaclavines, quinocitrinines, sterigmatocistin, and 3-nitropropionic acid, which may be toxic to humans. Due to the presence of potential pathogens and mycotoxins, the level of microbiological contamination at workplaces in CHPs should be monitored.

  15. Radioactive effluents from nuclear power stations and nuclear fuel reprocessing plants in the European Community

    International Nuclear Information System (INIS)

    Luykx, F.; Fraser, G.

    1983-01-01

    The report covers operational nuclear power stations of capacity greater than 5C MWe and nucler fuel reprocessing plants in the European Community. Radioactive gaseous and liquid effluent discharges from these installations are given for the period 1976 to 1980, expressed both in absolute terms and normalized to net electricity production from the fuel. An assesssment is then made of exposure of members of the public consequent to the 1980 discharges. Where environmental contamination levels were detectable the results have been taken into account in the dose assessment; however, environmental contamination was in general below the limit of detection. In these circumstances the dose estimates rely entirely on theoretical models which frequently incorporate conservative assumptions; hence these estimates are likely to be greater than the doses actually received. The estimated exposures have then been compared with the dose limits set out in the Euratom Directive of 15th July, 1980. It is concluded that the exposure of members of the public always left an appreciable safety margin relative to the limits and indeed lay within the variations in exposure which result from natural background

  16. Radioactive effluents from nuclear power stations and reprocessing plants in the European Community

    International Nuclear Information System (INIS)

    1978-04-01

    The report presents the available data on radioactive gaseous and liquid effluents discharged by nuclear power stations and nuclear fuel reprocessing plants in the European Community from 1972 to 1976. Discharges are expressed both in absolute terms and relative to the net production of electricity from the fuel. On the basis of the discharges recorded for 1976 the resulting maximum exposure of members of the population is quantified and compared with the dose limits prescribed by Euratom radiological protection standards and with the exposure resulting from natural radioactivity. It is concluded that there is no case in which a discharge could have given rise to an exposure exceeding the relevant prescribed limit. Not only did the possible maximum exposures incurred by individuals leave an appreciable safety margin relative to that limit but, for the vast majority of installations, they were comparable with or were considerably lower than the geographical and temporal variations in exposures resulting from natural radioactivity. Where environmental levels have been detectable the measured results have of course been used but, with few exceptions, the levels have remained less than the very low limits of detection currently possible. In general, where theoretical models are used to evaluate exposure, they are designed to give conservative results and hence it is likely that the true exposures are even less than those calculated

  17. Site preparation works for No.3 plant in Ikata Nuclear Power Station, Shikoku Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Ishihara, Hisashi; Nakajima, Hiroshi; Oshima, Teruhiko

    1986-01-01

    Ikata Power Station is only nuclear power station in Shikoku located at the root of Sadamisaki Peninsula. No.1 plant started the operation in September, 1977, and No.2 plant started the operation in March, 1982. By constructing No.3 plant of 890 MWe output, the total power output will be 2.022 million kW. No.3 plant is installed adjacently to No.1 and No.2 plants on their east side. In this place, the existing facilities of the harbor and others can be effectively utilized, the nature of ground is solid, and the fundamental condition of location is perfect, it is easy to obtain the cooperation of local people as No.1 and No.2 plants have been in operation, and it is advantageous in view of the construction period for the power supply plan. The site preparation works have progressed smoothly since the start in June, 1985. About 100,000 m 2 of the site is created by cutting natural ground, and about 54,000 m 2 is created by sea reclamation. About 5 million m 3 of earth and stone generated by cutting and excavation are utilized for reclamation, revetment and others. The topographic and geological features, sea condition, the outline of geological survey, the layout, and the construction works of revetment, cutting, the creation of substitute seaweed farm, appurtenant works, and the measures for environment preservation are described. (Kako, I.)

  18. Electric Power Plants and Generation Stations, Power Plants - is a seperate layer, however, we have them included in local building layer as well, Published in 2010, 1:2400 (1in=200ft) scale, Effingham County Government.

    Data.gov (United States)

    NSGIC Local Govt | GIS Inventory — Electric Power Plants and Generation Stations dataset current as of 2010. Power Plants - is a seperate layer, however, we have them included in local building layer...

  19. Station blackout at nuclear power plants: Radiological implications for nuclear war

    International Nuclear Information System (INIS)

    Shapiro, C.S.

    1986-12-01

    Recent work on station blackout is reviewed its radiological implications for a nuclear war scenario is explored. The major conclusion is that the effects of radiation from many nuclear weapon detonations in a nuclear war would swamp those from possible reactor accidents that result from station blackout

  20. Experimental investigations of overvoltages in 6kV station service cable networks of thermal power plants

    Energy Technology Data Exchange (ETDEWEB)

    Vukelja, P.I.; Naumov, R.M.; Drobnjak, G.V.; Mrvic, J.D. [Nikola Tesla Inst., Belgrade (Yugoslavia)

    1996-12-31

    The paper presents the results of experimental investigations of overvoltages on 6kV isolated neutral station service cable networks of thermal power plants. The overvoltages were recorded with capacitive voltage measurement systems made at the Nikola Tesla Institute. Wideband capacitive voltage measurement systems recorded a flat response from below power frequencies to 10MHz. Investigations of overvoltages were performed for appearance and interruption of metal earth faults, intermittent earth faults, switching operation of HV motors switchgear, switching operation of transformers switchgear, and transfer of the network supply from one transformer to another. On the basis of these investigations, certain measures are proposed for limiting overvoltages and for the reliability of station service of thermal power plants.

  1. Selective analysis of power plant operation on the Hudson River with emphasis on the Bowline Point Generating Station. Volume 1

    International Nuclear Information System (INIS)

    Barnthouse, L.W.; Cannon, J.B.; Christensen, S.G.

    1977-07-01

    A comprehensive study of the effects of power plant operation on the Hudson River was conducted. The study included thermal, biological, and air quality effects of existing and planned electrical generating stations. This section on thermal impacts presents a comprehensive mathematical modeling and computer simulation study of the effects of heat rejection from the plants. The overall study consisted of three major parts: near-field analysis; far-field analysis; and zone-matched near-field/far-field analysis. Near-field analyses were completed for Roseton, Danskammer, and Bowline Point Generating Stations, and near-field dilution ratios range from a low of about 2 for Bowline Point and 3 for Roseton to a maximum of 6 for both plants. The far-field analysis included a critical review of existing studies and a parametric review of operating plants. The maximum thermal load case, based on hypothetical 1974 river conditions, gives the daily maximum cross-section-averaged and 2-mile-segment-averaged water temperatures as 83.80 0 F in the vicinity of the Indian Point Station and 83.25 0 F in the vicinity of the Bowline Station. This maximum case will be significantly modified if cooling towers are used at certain units. A full analysis and discussion of these cases is presented. A study of the Hudson River striped bass population is divided into the following eight subsections: distribution of striped bass eggs, larvae, and juveniles in the Hudson River; entrainment mortality factor; intake factor; impingement; effects of discharges; compensation; model estimates of percent reduction; and Hudson River striped bass stock

  2. Lebensraum: paradoxically, population growth may eventually end wars.

    Science.gov (United States)

    Simon, J L

    1989-03-01

    Population growth may progressively reduce 1 of the motives for making war. Namely, population growth threatens shortages of resources, and especially land. Impending shortages cause a search for ways to mitigate the shortages. The discoveries eventually produce greater availability of resources than if population growth and pressure on resources had never occurred. The argument runs as follows: 1) Rhetoric about resources scarcity induced by population density has often contributed to international conflict, even if economics has not been the main motive in making war. 2) In the pre-modern era, war to obtain land and other resources may sometimes have been an economically sound policy. 3) Politicians and others in industrially developed nations believe resources may still be a casus belli. 4) Land and other productive resources are no longer worth acquiring at the cost of war.

  3. Evaluation of environmental data relating to selected nuclear power plant sites: the Three Mile Island Nuclear Station Site

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-08-01

    Environmental monitoring data for the years 1973 and 1974 pertaining to the Three Mile Island Nuclear Station Unit 1, which began operation in early 1974, were analyzed by the most practical qualitative and quantitative methods. Terrestrial biotic resources were considered for this plant. The effects of the operation of Unit 1 on the local terrestrial organisms were found to be undetectable. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data acquired, method of analysis, and results obtained are presented in detail along with recommendations for improving monitoring techniques

  4. Management of main generator condition during long term plant shut down at Higashidori Nuclear Power Station Unit 1

    International Nuclear Information System (INIS)

    Kato, Seiji

    2014-01-01

    Higashidori Nuclear Power Station Unit 1 shut down on February 6, 2011 to start 4th refuel outage. On March 11, 2011, we keep going refuel outage on this moment a large earthquake occurred and tsunami was generated following it which called 'Great East Japan Earthquake'. Refuel outage takes 3 ∼ 5 months normally but Higashidori NPS still keeping shut down over 3 years due to some issues. In this paper, we introduce about management of Main generator condition during long term plant shut down situation in addition to normal plant shut down situation to keep well. (author)

  5. Results of evaluation of periodic safety review for No. 1 plant in Mihama Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1994-01-01

    No. 1 plant in Mihama Power Station started the commercial power generation in November, 1970, and has continued the operation for more than 23 years. During this period, the counter measures to troubles, periodic inspections and the maintenance by the electric power company have been carried out. These states of No. 1 plant in Mihama Power Station for more than 23 years are to be recollected from the view-points of the comprehensive evaluation of operation experiences and the reflection of latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Mihama Power Station made by Kansai Electric Power Co., and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor is 43.3% on the average of about 23 years, but in the last 10 years, it was improved to 69.4%. In the last five years, the rate of occurrence of unexpected shutoff was 0.6 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, and radioactive waste management have been carried out properly. The work plan for preventing disasters was established, and the experience of troubles and the latest technological knowledge were well reflected to improve the safety. (K.I.)

  6. Why do even satisfied newlyweds eventually go on to divorce?

    Science.gov (United States)

    Lavner, Justin A; Bradbury, Thomas N

    2012-02-01

    Although divorce typically follows an extended period of unhappiness that begins early in marriage, some couples who are very happy throughout the first several years of marriage will also go on to divorce. This study aimed to identify risk factors early in marriage that distinguish initially satisfied couples who eventually divorce from those who remain married. We identified 136 couples reporting stably high levels of relationship satisfaction in the first 4 years of marriage. We compared the couples who went on to divorce by the 10-year follow-up with the couples who remained married on initial measures of commitment, observed communication, stress, and personality. Divorcing couples displayed more negative communication, emotion, and social support as newlyweds compared with couples who did not divorce. No significant differences were found in the other domains, in relationship satisfaction, or in positive behaviors. Overall, results indicate that even couples who are very successful at navigating the early years of marriage can be vulnerable to later dissolution if their interpersonal exchanges are poorly regulated. We speculate that, paradoxically, the many strengths possessed by these couples may mask their potent interpersonal liabilities, posing challenges for educational interventions designed to help these couples.

  7. Electrolysis with diamond anodes: Eventually, there are refractory species!

    Science.gov (United States)

    Mena, Ismael F; Cotillas, Salvador; Díaz, Elena; Sáez, Cristina; Rodríguez, Juan J; Cañizares, P; Mohedano, Ángel F; Rodrigo, Manuel A

    2018-03-01

    In this work, synthetic wastewater polluted with ionic liquid 1-butyl-3-methylimidazolium (Bmim) bis(trifluoromethanesulfonyl)imide (NTf 2 ) undergoes four electrolytic treatments with diamond anodes (bare electrolysis, electrolysis enhanced with peroxosulfate promoters, irradiated with UV light and with US) and results obtained were compared with those obtained with the application of Catalytic Wet Peroxide Oxidation (CWPO). Despite its complex heterocyclic structure, Bmim + cation is successfully depleted with the five technologies tested, being transformed into intermediates that eventually can be mineralized. Photoelectrolysis attained the lowest concentration of intermediates, while CWPO is the technology less efficient in their degradation. However, the most surprising result is that concentration of NTf 2 - anion does not change during the five advanced oxidation processes tested, pointing out its strong refractory character, being the first species that exhibits this character in wastewater undergoing electrolysis with diamond. This means that the hydroxyl and sulfate radicals mediated oxidation and the direct electrolysis are inefficient for breaking the C-S, C-F and S-N bounds of the NTf 2 - anion, which is a very interesting mechanistic information to understand the complex processes undergone in electrolysis with diamond. Copyright © 2017 Elsevier Ltd. All rights reserved.

  8. Works of shifting discharge facilities in construction for adding No.3 and No.4 plants to Oi Nuclear Power Station

    International Nuclear Information System (INIS)

    Matsuoka, Gen-ichi; Yoshida, Atsumu.

    1989-01-01

    At present in Oi Power Station, No.1 and No.2 plants of 1175 MWe output each are in operation, but in order to stabilize electric power supply for a long period, Kansai Electric Power Co., Inc. earnestly advances the construction works for adding No.3 and No.4 plants of each 1180 MWe output PWR. No.3 plant is expected to begin the operation in October, 1991, and No.4 plant in August, 1992. The works for creating the site were started in July, 1985, and the flat land of about 60,000 m 2 and the reclaimed land of about 80,000 m 2 were prepared. Subsequently, the main construction works were started in May, 1987, and the rate of general progress was 21 % in No.3 plant and 2 % in No.4 plant as of the end of October, 1988. Due to the addition of No.3 and No.4 plants, the quantity of condenser cooling water discharge increases to 318 m 3 /s from 150 m 3 /s at present, therefore, the bank having discharge holes is shifted from the present position about 100 m toward sea. As to the problems, the shifting works in flowing water, the method of shifting, the examination on lifting caissons and culverts, the trial construction of chemical anchors and so on were investigated. The execution of the shifting works is reported. (K.I.)

  9. Floating nuclear heat. And power station 'Pevec' with KLT-40S type reactor plant for remote regions of Russia

    International Nuclear Information System (INIS)

    Veshnyakov, K.B.; Kiryushin, A.I.; Panov, Yu.K.; Polunichev, V.I.

    2000-01-01

    Floating small nuclear power plants power for local energy systems of littoral regions of Russia, located far from central energy system, open a new line in nuclear power development. Designing a floating power unit of a lead nuclear heat and power generating station for port Pevec at the Chuckchee national district is currently nearing completion. Most labor-intensive components are being manufactured. The co-generation NPP Pevec is to be created on the basis of a floating power unit with KLT-40S type reactor plant. KLT-40S reactor plant is based on similar propulsion plants, verified at operation of Russia's nuclear-powered civil ships, evolutionary improved by elimination of 'weak points' revealed during its prototypes operation or on the basis of safety analysis. KLT-40S reactor plant uses the most wide-spread and developed in the world practice PWR-type reactor. KLT-40S meets contemporary national and international requirements imposed to future reactor plants. The NHPS description, its main technical-economic data, environmental safety indices, basic characteristics of KLT-40S reactor plant are presented. Prospects of small NPPs utilization outside Russia, particularly as an energy source for sea water desalination, are considered. (author)

  10. Evaluation of Plant- Compost -Microorganisms Synergy for the Remediation of Diesel contaminated Soil: Success Stories from the Field Station

    Science.gov (United States)

    Hussain, Imran; Wimmer, Bernhard; Soja, Gerhard; Sessitsch, Angela; Reichenauer, Thomas G.

    2016-04-01

    Total petroleum hydrocarbons (TPH) contain a mixture of crude oil, gasoline, creosote and diesel is one of the most common groups of persistent organic pollutants. TPH enters into the ecosystem (soil, water and air) through leakage of underground storage tanks (LUST), accidental oil spills, transportation losses and industrial processes. Pollution associated with diesel oil and its refined products is of great concern worldwide due to its threats/damages for human and ecosystem health, soil structure and ground water quality. Extensive soils pollution with petroleum hydrocarbons results in extreme harsh surroundings, produce hydrophobic conditions and infertile soils that ultimately lead towards less plant and microorganisms growth. Among biological methods, bioremediation and phytoremediation are promising technologies that have both technical and ecological benefits as compared to convention methods. Within phytoremediation, rhizoremediation based on stimulation of degrading microorganism's population influenced by plant rhizospheric effect is known as main mechanism for phytoremediation of petroleum polluted soils. Composting along with rhizodegradtion was used to remediate freshly spilled soils at Lysimeter station Siebersdof, Austria. Experiment was started in July 2013 and will be monitored up to September 2016. Field station has 12 Lysimeter in total; each has length, width and depth of 100 cm respectively. Each Lysimeter was filled with normal agricultural soil from Siebersdof (0-70 cm), sand (70-85 cm) and stones (85-100cm). Sand and stones were added to support the normal leaching and percolation of water as we collected leachate samples after regular intervals. After filling, commercial diesel oil (2% w/w of 0-70 cm soil) was spilled on top of each Lysimeter as accidental spill occurs in filed. Compost was added at 0-15 cm layer (5% w/w of soil) to stimulate plant as well as microorganisms growth. Whole Lysimeter station was divided into three treatments

  11. Experience in industrial operation of the plant for immobilizing radioactive wastes in thermosetting resins at the Ardennes Nuclear Power Station

    International Nuclear Information System (INIS)

    Haller, P.; Romestain, P.; Bruant, J.P.

    1983-01-01

    The French Atomic Energy Commission (CEA) has developed, at the Grenoble Centre for Nuclear Studies, a procedure for immobilizing low- and intermediate-level wastes in thermosetting resins of the polyester or epoxy types. To demonstrate feasibility on an industrial scale, a pilot plant has been set up at the effluent treatment station of the Ardennes Franco-Belgium Nuclear Power Station (SENA), which is a 305 MW(e) PWR type. Assembly work began in January 1979. After a period devoted to final adjustments and operation with inactive products, conditioning of active products began in January 1981. In the paper, the methods of conditioning the three types of waste (evaporation concentrates, ion exchange resins and filter cartridges) are described, experience of the start-up and operation of the plant is reported and the principal results of coating characterization tests are given. The results of tests on active and inactive products show that the characteristics of the materials obtained on an industrial scale match those of laboratory products and confirm their high quality with regard to mechanical behaviour, fire resistance, homogeneity and low-leachability. Industrial experience and economic comparisons show that the process of immobilizing waste from nuclear power stations in thermosetting resins offers an extremely interesting alternative to classical methods of conditioning. (author)

  12. Possible efficiency improvement by application of various operating regimes for the cooling water pump station at thermal power plant - Bitola

    Directory of Open Access Journals (Sweden)

    Mijakovski Vladimir

    2012-01-01

    Full Text Available Thermal power plant (TPP - Bitola is the largest electricity producer in the Republic of Macedonia with installed capacity of 691 MW. It is a lignite fired power plant, in operation since 1982. Most of the installed equipment is of Russian origin. Power plant's cold end comprised of a condenser, pump station and cooling tower is depicted in the article. Possible way to raise the efficiency of the cold end by changing the operating characteristics of the pumps is presented in the article. Diagramic and tabular presentation of the working characteristics of the pumps (two pumps working in paralel for one block with the pipeline, as well as engaged power for their operation are also presented in this article.

  13. Monitoring and assessment of health issues at energy plant and gas station Pak steel bin Qasim Karachi

    International Nuclear Information System (INIS)

    Memon, Z.

    2005-01-01

    No doubt Environmental and health safety issues in big cities of Pakistan are developing havoc problems due to mechanized operations by emitting flue gases, effluent and acoustic noise, which it is my topic to discuss in detail. Acoustic noise is one of the major environmental problems in Industrial Plants. The noise study under taken in detail at feed pumps, super heater, exhausters and accumulators of Energy plant (E.P) as the regulators, control room etc. of Gas station (G.S) Pak Steel Bin Qasim Karachi. In light of permissible occupational noise exposure limits, as allowed by the ISO,EEC and other National Standards, some recommendations have been made to provide safety measures for workers against high level noise health hazards like head ache, hearing problem, Irritation, accidents at work, tension, disturbance to work and so many physiological and psychological effects, along with guidelines to overcome the break downs an improve efficiency of the plants. (Orig./A.B.)

  14. Estimating end of life liabilities for plant licensing and financial planning for similarly configured stations

    Energy Technology Data Exchange (ETDEWEB)

    Griffiths, G. [TLG Services, Inc. an Entergy Nuclear Co. (United States); Kennard, J. [Ontario Power Generation Inc. (Canada)

    2008-07-01

    Ontario Power Generation (OPG) is required to update estimated waste management and decommissioning costs on a 5-year cycle within the Canadian Nuclear Safety Commission's (CNSC) regulatory framework and provide a decommissioning cost update and provisions funds status to the Province of Ontario on a similar five-year cycle under the terms of the Ontario Nuclear Funds Agreement (ONFA). The following is an overview of the important steps used to develop OPG's nuclear power station decommissioning cost estimates, including a discussion of the responsibilities of both the owner (OPG) and estimating services vendor (TLG Services). This presentation is related to decommissioning estimating for multi-unit stations; therefore the discussion will be focused on identifying those activities that may be particularly impacted by multi-unit configuration or multiple stations. It should be noted that simultaneously developing decommissioning estimates for multiple multi-unit stations creates the opportunity to achieve economies of scale to more efficiently produce the estimates, and enables the owner and vendor to compare results between stations to identify inconsistencies. However, without careful attention to detail at the planning and execution stage, it also creates the potential liability of backtracking and developing the estimate multiple times, should significant assumptions be revised in mid-project. (authors)

  15. Estimating end of life liabilities for plant licensing and financial planning for similarly configured stations

    International Nuclear Information System (INIS)

    Griffiths, G.; Kennard, J.

    2008-01-01

    Ontario Power Generation (OPG) is required to update estimated waste management and decommissioning costs on a 5-year cycle within the Canadian Nuclear Safety Commission's (CNSC) regulatory framework and provide a decommissioning cost update and provisions funds status to the Province of Ontario on a similar five-year cycle under the terms of the Ontario Nuclear Funds Agreement (ONFA). The following is an overview of the important steps used to develop OPG's nuclear power station decommissioning cost estimates, including a discussion of the responsibilities of both the owner (OPG) and estimating services vendor (TLG Services). This presentation is related to decommissioning estimating for multi-unit stations; therefore the discussion will be focused on identifying those activities that may be particularly impacted by multi-unit configuration or multiple stations. It should be noted that simultaneously developing decommissioning estimates for multiple multi-unit stations creates the opportunity to achieve economies of scale to more efficiently produce the estimates, and enables the owner and vendor to compare results between stations to identify inconsistencies. However, without careful attention to detail at the planning and execution stage, it also creates the potential liability of backtracking and developing the estimate multiple times, should significant assumptions be revised in mid-project. (authors)

  16. Simulations of thermal-hydraulic processes in heat exchangers- station of the cogeneration power plant

    Energy Technology Data Exchange (ETDEWEB)

    Studovic, M.; Stevanovic, V.; Ilic, M.; Nedeljkovic, S. [Faculty of Mechanical Engineering of Belgrade (Croatia)

    1995-12-31

    Design of the long district heating system to Belgrade (base load 580 MJ/s) from Thermal Power Station `Nikola Tesla A`, 30 km southwest from the present gas/oil burning boilers in New Belgrade, is being conducted. The mathematical model and computer code named TRP are developed for the prediction of the design basis parameters of heat exchangers station, as well as for selection of protection devices and formulation of operating procedures. Numerical simulations of heat exchangers station are performed for various transient conditions: up-set and abnormal. Physical model of multi-pass, shell and tube heat exchanger in the station represented is by unique steam volume, and with space discretised nodes both for water volume and tube walls. Heat transfer regimes on steam and water side, as well as hydraulic calculation were performed in accordance with TEMA standards for transient conditions on both sides, and for each node on water side. Mathematical model is based on balance equations: mass and energy for lumped parameters on steam side, and energy balances for tube walls and water in each node. Water mass balance is taken as boundary/initial condition or as specified control function. The physical model is proposed for (s) heat exchangers in the station and (n) water and wall volumes. Therefore, the mathematical model consists of 2ns+2, non-linear differential equations, including equations of state for water, steam and tube material, and constitutive equations for heat transfer on steam and water side, solved by the Runge-Kutt method. Five scenarios of heat exchangers station behavior have been simulated with the TRP code and obtained results are presented. (author)

  17. Development of a Cost-Effective Solar/Diesel Independent Power Plant for a Remote Station

    Directory of Open Access Journals (Sweden)

    Okeolu Samuel Omogoye

    2015-01-01

    Full Text Available The paper discusses the design, simulation, and optimization of a solar/diesel hybrid power supply system for a remote station. The design involves determination of the station total energy demand as well as obtaining the station solar radiation data. This information was used to size the components of the hybrid power supply system (HPSS and to determine its configuration. Specifically, an appropriate software package, HOMER, was used to determine the number of solar panels, deep-cycle batteries, and rating of the inverter that comprise the solar section of the HPSS. A suitable diesel generator was also selected for the HPSS after careful technical and cost analysis of those available in the market. The designed system was simulated using the HOMER software package and the simulation results were used to carry out the optimization of the system. The final design adequately meets the station energy requirement. Based on a life expectancy of twenty-five years, a cost-benefit analysis of the HPSS was carried out. This analysis shows that the HPSS has a lower cost as compared to a conventional diesel generator power supply, thus recommending the HPSS as a more cost-effective solution for this application.

  18. Evaluation of environmental data relating to selected nuclear power plant sites. The Zion Nuclear Power Station site

    International Nuclear Information System (INIS)

    Murarka, I.P.; Policastro, A.; Daniels, E.; Ferrante, J.; Vaslow, F.

    1976-11-01

    Environmental monitoring data for the years 1972 through 1975 pertaining to the Zion Station, which began commercial operation in 1974, were analyzed by the most practical qualitative and quantitative methods. Thermal plume, water chemistry and aquatic biota data were evaluated and the results are presented. The results showed no significant immediate deleterious effects, thus confirming preoperational predictions. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data utilized, the methods of analysis, and the results obtained are presented in detail, along with recommendations for improving monitoring techniques

  19. Proof of safer operation of power station plant during a fire by linking in fire simulation and system technical analysis

    International Nuclear Information System (INIS)

    Hensel, W.; Beyer, H.; Samman, A.

    1997-01-01

    In order to attain the basic aims of protection in power station plant, a series of systems, which must be available also in the event of a fire, are provided. The thermal loads for the systems and components which are necessary to attain the aims of protection are ascertained by means of a simulation of the cause of the fire for the specific scenario. Statements on the availability of the systems and components in the specific scenario are derived from the design values used as the basis. (orig.) [de

  20. Exploration of plant growth and development using the European Modular Cultivation System facility on the International Space Station.

    Science.gov (United States)

    Kittang, A-I; Iversen, T-H; Fossum, K R; Mazars, C; Carnero-Diaz, E; Boucheron-Dubuisson, E; Le Disquet, I; Legué, V; Herranz, R; Pereda-Loth, V; Medina, F J

    2014-05-01

    Space experiments provide a unique opportunity to advance our knowledge of how plants respond to the space environment, and specifically to the absence of gravity. The European Modular Cultivation System (EMCS) has been designed as a dedicated facility to improve and standardise plant growth in the International Space Station (ISS). The EMCS is equipped with two centrifuges to perform experiments in microgravity and with variable gravity levels up to 2.0 g. Seven experiments have been performed since the EMCS was operational on the ISS. The objectives of these experiments aimed to elucidate phototropic responses (experiments TROPI-1 and -2), root gravitropic sensing (GRAVI-1), circumnutation (MULTIGEN-1), cell wall dynamics and gravity resistance (Cell wall/Resist wall), proteomic identification of signalling players (GENARA-A) and mechanism of InsP3 signalling (Plant signalling). The role of light in cell proliferation and plant development in the absence of gravity is being analysed in an on-going experiment (Seedling growth). Based on the lessons learned from the acquired experience, three preselected ISS experiments have been merged and implemented as a single project (Plant development) to study early phases of seedling development. A Topical Team initiated by European Space Agency (ESA), involving experienced scientists on Arabidopsis space research experiments, aims at establishing a coordinated, long-term scientific strategy to understand the role of gravity in Arabidopsis growth and development using already existing or planned new hardware. © 2014 German Botanical Society and The Royal Botanical Society of the Netherlands.

  1. LM5000 gas turbine generating plant for Tenaga Nasional Berhad Sultan Salahuddin Abdul Aziz power station (Malaysia)

    Energy Technology Data Exchange (ETDEWEB)

    Ishizuka, T.; Shioya, Y.; Furuya, M.; Saito, K. [Ishikawajima-Harima Heavy Indutries Co. Ltd., Tokyo (Japan)

    1995-01-01

    The LM5000 gas turbine generating plant (35,000 kW) for Tenaga Nasional Berhad Sultan Salahuddin Abdul Aziz Power Station (Malaysia) was outlined. The lightweight power turbine of 16 ton was adopted to reduce an on-site installation time, and integrated into a single package together with the gas generator, while all the auxiliary units were assembled completely before delivery. Because the plant was for peak cut use, the hydraulic starting unit was adopted, in particular, considering starting operation, and the diesel engine generator was provided to drive the unit in complete power failure. The reliability of operation and monitoring was also enhanced by triplicated digital control. The plant output capacity was well beyond the required one during actual operation, and the thermal efficiency of 36.0-36.3% was obtained. Because the power plant was installed in the rainy western part of Malaysia, protective measures of the plant from rain were taken into careful consideration, for example, the air intake port of the air-cooled generator was faced downward, and provided with a condensation eliminator. 4 figs.

  2. Quality assurance grading criteria for plant systems and components: Results from a pilot plant project at Grand Gulf Nuclear Station. Final report

    International Nuclear Information System (INIS)

    Parkinson, W.J.

    1995-12-01

    As part of the original design of a nuclear power plant, the NSSS vendor, architect/engineer and utility identified structures, systems and components (SSCs) as safety related and assigned them to a Q-list. A Q-list is usually very large, e.g. 75,000 components, which creates large ongoing annual operating costs for the utility. Operating experience and the greater knowledge of plant systems safety accumulated during the past 20 years have suggested that many components are not truly important to safety and do not warrant the Q-classification and the associated costs. The completion of Probabilistic Safety Analyses (PSAs) for many nuclear power plants has contributed to this greater knowledge. This report describes a practical application of PSA technology to modify the existing QA program at the Grand Gulf Nuclear Station. Section 1 introduces the term, QA Safety Significant (QASS), and relates it to the existing term, ''safety related''. Section 2 describes six deterministic criteria as a basis for classifying systems as QASS or non-QASS. An expert panel reviewed 421 systems at Grand Gulf Nuclear Station and identified 42 of them as QASS. All components in non-QASS systems are classified as non-QASS. For QASS systems, Section 3 describes five deterministic criteria for classifying components as QASS or non-QASS. By using these two sets of criteria, the expert panel found that the number of components requiring full QA compliance could be reduced by 24%. These results are summarized in Section 4

  3. 78 FR 24666 - Updates to the List of Plant Inspection Stations

    Science.gov (United States)

    2013-04-26

    ... 319 Coffee, Cotton, Fruits, Imports, Logs, Nursery stock, Plant diseases and pests, Quarantine..., laboratory facilities for pest and disease identification, and in some cases, provide facilities for...) division who inspect articles to ensure they are free of plant pests and diseases and otherwise comply with...

  4. Proceedings of the workshop on future control station designs and human performance issues in nuclear power plants

    International Nuclear Information System (INIS)

    2007-01-01

    The nuclear community is currently at a stage where new reactors are being built, advanced reactors are being planned, and existing reactors are undergoing various forms of modernization of their control stations. Nuclear power plants are characterised by a high degree of complexity, where efficient and safe performance is dependent on both a sound technical design and effective teamwork and work practices. Team interactions have long traditions in current nuclear power plants. The way people operate and maintain the plants may need to accommodate technical advances associated with control station modernization and advanced plant control stations. The nuclear community likely to see the introduction of new designs, new tools to support the staff, changes to staffing types and levels, concepts of operation for new reactors that are different from current reactors, e.g., multi-unit control, possible remote operation, distributed decision making, and cooperation across distances. Based on recent experience, there is limited knowledge about human performance issues with regard to upgraded control rooms. However, even less knowledge exists regarding operation and maintenance of control stations for future and more advanced reactor designs. In order to explore these issues, the CSNI Special Experts' Group on Human and Organisational Factors (SEGHOF), now the Working Group on Human and Organizational Factors (WGHOF), and the Halden Reactor Project (HRP) hosted a joint workshop which provided an international forum for utilities, vendors, research bodies and regulators to discuss human performance issues related to control stations for future nuclear power plant designs and for modified control rooms for existing plants. The Norwegian petroleum industry also shared their experiences, especially with integrated and distributed operations among off-shore and on-shore control centres. There were 74 participants from 20 countries at the workshop. Twenty-two papers were

  5. Design improvements to achieve ALARA exposures to plant personnel at Narora Atomic Power Station (NAPS)

    International Nuclear Information System (INIS)

    Mittal, S.; Mehta, H.C.; Roy, S.K.

    2000-01-01

    NAPS is the indigenously designed, constructed and commissioned, first PHWR station of standardized design for 220 MWe station of NPCIL. At NAPS, radiation fields started building up after first start up due to Cobalt-60 and this was a major concern, from collective dose point of view, for carrying out any activity specially around and with in the moderator system. Apart from this system, PHT and fueling machine areas are also vulnerable areas from radiation point of view. To reduce and control the high collective dose consumption, various design modifications; like moderator purification system modifications, changes in heavy water recovery arrangements and FT system, have been carried out at NAPS and these are discussed in this paper. (author)

  6. Sifat Strong Perron-Frobenius Pada Solusi Positif Eventual Sistem Persamaan Differensial Linier Orde Satu

    Directory of Open Access Journals (Sweden)

    Yulian Sari

    2014-12-01

    Full Text Available Artikel ini membicarakan tentang sifat strong Perron-Frobenius pada solusi positif eventual sistem persamaan differensial linier orde satu. Syarat perlu agar solusi positif eventual sistem persamaan differensial linier orde satu diajukan. Beberapa kriteria tentang matriks eksponensial positif eventual dan matriks positif eventual juga akan digunakan dalam teorema.

  7. Sifat Strong Perron-Frobenius Pada Solusi Positif Eventual Sistem Persamaan Differensial Linier Orde Satu

    Directory of Open Access Journals (Sweden)

    Yulian Sari

    2015-04-01

    Full Text Available Artikel ini membicarakan tentang sifat strong Perron-Frobenius pada solusi positif eventual sistem persamaan differensial linier orde satu. Syarat perlu agar solusi positif eventual sistem persamaan differensial linier orde satu diajukan. Beberapa kriteria tentang matriks eksponensial positif eventual dan matriks positif eventual juga akan digunakan dalam teorema.

  8. Coupling of standard condensing nuclear power stations to horizontal aluminium tubes multieffect distillation plants

    International Nuclear Information System (INIS)

    Adar, J.

    1977-01-01

    No large nuclear back-pressure turbines are available to-day. Standard condensing nuclear turbines could operate continuously with a back-pressure of up to 7'' Hg, exhausting huge amounts of steam at 56degC-64degC with a loss of electricity production of only 6%-10%. The horizontal aluminium tube multieffect distillation process developed by 'Israel Desalination Engineering Ltd' is very suitable for the use of such low-grade heat. A special flash-chamber loop constitutes a positive barrier against any possible contamination being carried over by the steam exhausted from the turbine to the desalination plant. The operation is designed to be flexible so that the power plant can be operated either in conjunction with the desalination plant or as a single purpose plant. Flow sheets, heat and mass balances have been prepared for eight different combinations of plants. Only standard equipment is being used in the power plant. The desalination plant consists of 6 to 12 parallel double lines, each of them similar to a large prototype now being designed. Water production varies between 50 and 123 MGD and water cost between 90 and 137 c/1000 gallons. Costs are based on actual bids

  9. Data processing project management in the construction of plants and power stations

    International Nuclear Information System (INIS)

    Huelsen, H.; Hayen, W.

    1987-01-01

    The requirements of project management in plant construction i.e. basic data, supervision and control became more and more detailed. These requirements can only satisfactorily be met with the help of data processing. Piping design requires up to 50% of the whole amount of engineering in design and management of plant construction. We present data processing project management system which explains the connections of single aspects. Its connections consists of: collection of basic data, plant design and installation, supervision of planning and installation, planning and calculation, collection, use, administration and approval of plan data, procurement material, construction of the model (1:25), and installation. (orig.) [de

  10. Effect of fly ash from a fuel oil power station on heavy metal content of wild plants at Tenerife island, the Canarian archipelago, Spain

    International Nuclear Information System (INIS)

    Alvarez, C.E.; Fernandez, M.; Iglesias, E.; Perez, N.; Snelling, R.

    1993-01-01

    Heavy metal analysis have been carried out in wild plants around a Power Station located at the southeastern area of Tenerife Island (Canary Islands, Spain). The concentrations of Fe, Ni, and V in the leaves and terminal stems of three wild plants (Euphorbia obtusifolia, Kleinia neriifolia, and Plocama pendula) which were collected during the spring of 1988 are reported from four different allotments. These sampling sites were located at distances of 0.4, 1, 1, 25, and 34 km from the Electric Generating Facility, and at elevations of 60, 120, 180 and 60 m, respectively. Results show a potential contamination of vanadium in E. obtusifolia and P. pendula plants located close to the Power Station, probably due to dry deposition on fly ash in the surrounding area. The levels of iron and nickel concentrations in the same type of plants did not show any geographical relationship with respect to the location of the Power Station. 19 refs., 4 figs

  11. Principles of education and training of plant engineers for nuclear power stations

    International Nuclear Information System (INIS)

    Ackermann, G.; Meyer, K.; Brune, W.

    1978-01-01

    Experience in education and advanced training of nuclear engineers in the GDR is reviewed. The basic education of engineers is carried out at universities and colleges. Graduate engineers who have been working in non-nuclear industries for a longer time receive their basic education in nuclear engineering through postgraduate studies. Graduate engineers with a basic knowledge of nuclear engineering are trained at the Nuclear Power Plant School of the Rheinsberg nuclear power plant and at the nuclear power plants of the GDR under operational conditions relating to their future job. In addition to basic theoretical knowledge, training at a nuclear power plant simulator plays an important role. This permits training of the staff under normal operating conditions including transient processes and under unusual conditions. Further particular modes of advanced professional training such as courses in radiation protection and further postgraduate studies are described. This system of education has proved successful. It will be developed further to meet the growing demands. (author)

  12. Integrated plant safety assessment, Systematic Evaluation Program: Dresden Nuclear Power Station, Unit 2 (Docket No. 50-237)

    International Nuclear Information System (INIS)

    1989-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0823), under the scope of the Systematic Evaluation Program (SEP), for the Commonwealth Edison Company (CECo) Dresden Nuclear Power Station, Unit 2 located in Grundy County, Illinois. The NRC initiated the SEP to provide the framework for reviewing the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed by means of the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations subsequent to issuing the final IPSAR for Dresden Unit 2. The review was provided for (1) an assessment of the significance of differences between current technical positions on selected issues and those that existed when Dresden Unit 2 was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The final IPSAR and this supplement forms part of the bases for considering the conversion of the existing provisional operating license to a full-term operating license. 83 refs., 9 tabs

  13. Start. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1998)

    International Nuclear Information System (INIS)

    1999-01-01

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1998 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1998; (4) Quality system; (5) Electricity and heat generation; Maintenance; Capital construction; (6) Radiation safety; Environmental impacts of operations; (7) List of balances; Human resources; (8) International co-operation; Public relations

  14. Slovak power stations, Nuclear power plants Jaslovske Bohunice. (Annual report 1997)

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Foreword by the director of Bohunice NPPs; (2) Management of Bohunice NPPs Subsidiary Plant; (3) The most significant events of the year 1997; (4) Electricity and heat production; (5) Safety; (6) Bohunice NPPs operation impact on environment; (7) The V-1 NPP and V-2 NPP upgrading; (8) Maintenance; (9) Capital construction; (10) Economic balance; (11) International co-operation; (12) Human sources; (12) Public relations

  15. The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dong Gu, E-mail: littlewing@kins.re.kr [Korea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon 305-338 (Korea, Republic of); Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Chang, Soon Heung [Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

    2014-08-15

    Highlights: • The combined deterministic and probabilistic procedure (CDPP) was proposed for safety assessment of the BDBAs. • The safety assessment of OPR-1000 nuclear power plant for SBO accident is performed by applying the CDPP. • By estimating the offsite power restoration time appropriately, the SBO risk is reevaluated. • It is concluded that the CDPP is applicable to safety assessment of BDBAs without significant erosion of the safety margin. - Abstract: Station blackout (SBO) is a typical beyond design basis accident (BDBA) and significant contributor to overall plant risk. The risk analysis of SBO could be important basis of rulemaking, accident mitigation strategy, etc. Recently, studies on the integrated approach of deterministic and probabilistic method for nuclear safety in nuclear power plants have been done, and among them, the combined deterministic and probabilistic procedure (CDPP) was proposed for safety assessment of the BDBAs. In the CDPP, the conditional exceedance probability obtained by the best estimate plus uncertainty method acts as go-between deterministic and probabilistic safety assessments, resulting in more reliable values of core damage frequency and conditional core damage probability. In this study, the safety assessment of OPR-1000 nuclear power plant for SBO accident was performed by applying the CDPP. It was confirmed that the SBO risk should be reevaluated by eliminating excessive conservatism in existing probabilistic safety assessment to meet the targeted core damage frequency and conditional core damage probability. By estimating the offsite power restoration time appropriately, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system lies in the acceptable risk against the SBO. In addition, it is concluded that the CDPP is applicable to safety assessment of BDBAs in nuclear power plants without significant erosion of the safety margin.

  16. Seismic stress of plants and equipment in nuclear power station construction

    International Nuclear Information System (INIS)

    Hampe, E.; Schwarz, J.

    1984-01-01

    The applicability of floor spectra for designing components of nuclear power plants taking into account seismic effects is discussed. Methods for the determination of seismic floor excitation and various kinds of floor spectra are presented. As an example the floor spectra method is applied to containment buildings

  17. Characterisation of a pneumatic muscle test station with two dynamic plants in cascade.

    Science.gov (United States)

    Serres, J L; Reynolds, D B; Phillips, C A; Rogers, D B; Repperger, D W

    2010-02-01

    Pneumatic muscle actuators (PMAs) offer significant advantages over more traditional actuators, which make them prime candidates in rehabilitation devices. A dynamic test station (DTS) is modified to demonstrate the use of a PMA for this application. The DTS includes two dynamic systems: a PMA and a DC servomotor. An overall transfer function was developed utilising characterisation data for the PMA and DC servomotor. A Tustin (bilinear) transform was performed on the overall transfer function to obtain a discrete time system. Model parameters were optimised and used to generate input voltage profiles that achieve isokinetic (constant velocity) task specifications. Percent root mean square error values (PRMSE) between the actual and ideal profiles were used to evaluate the accuracy of this method in achieving isokinetic displacement. For PMA pressures (in kPa) of 150, 350 and 550 PRMSE were 7.80, 5.40 and 2.76, respectively.

  18. Monitoring the risk of loss of heat sink during plant shutdowns at Bruce Generating Station 'A'

    International Nuclear Information System (INIS)

    Krishnan, K.S.; Mancuso, F.; Vecchiarelli, D.

    1996-01-01

    A relatively simple loss of shutdown heat sink fault tree model has been developed and used during unit outages at Bruce Nuclear Generation Station 'A' to assess, from a risk and reliability perspective, alternative heat sink strategies and to aid in decisions on allowable outage configurations. The model is adjusted to reflect the various unit configurations planned during a specific outage, and identifies events and event combinations leading to loss of fuel cooling. The calculated failure frequencies are compared to the limits consistent with corporate and international public safety goals. The importance measures generated by the interrogation of the fault tree model for each outage configuration are also used to reschedule configurations with high fuel damage frequency later into the outage and to control the configurations with relatively high probability of fuel damage to short intervals at the most appropriate time into the outage. (author)

  19. Demonstration test of electron beam flue gas treatment pilot plant of a coal fired thermal power station

    International Nuclear Information System (INIS)

    Doi, Yoshitaka; Hayashi, Kazuaki; Izutsu, Masahiro; Watanabe, Shigeharu; Namba, Hideki; Tokunaga, Okihiro; Hashimoto, Shoji; Tanaka, Tadashi; Ogura, Yoshimi.

    1995-01-01

    The Japan Atomic Energy Research Institute, Chubu Electric Power Company and Ebara Corporation jointly constructed a pilot plant for electron beam flue gas treatment (dry process) capable of treating 12,000 m 3 /h (NTP) of flue gas from a coal fired boiler, at Shin-Nagoya Thermal Power Station, Chubu Electric Power Company. Various tests carried out at the plant over a period extending one year verified the followings. By appropriately controlling parameters such as electron beam dosage, flue gas temperature, and ammonia stoichiometric amount, highly efficient simultaneous SO 2 and NOx removal from flue gas was achieved under all gas conditions, equal to or more efficient than that by the highest level conventional treatment. The operation of the pilot plant was stable and trouble-free over a long term, and the operation and the process was easy to operate and control. By-products (ammonium sulfate and ammonium nitrate) produced by the flue gas treatment were proven to have superior quality, equivalent to that of market-available nitrogen fertilizers. These by-products had been registered as by-product nitrogen fertilizers. (author)

  20. Preparation of substituting seaweed field mounds accompanying site preparation for No.3 plant in Ikata Nuclear Power Station

    International Nuclear Information System (INIS)

    Ishihara, Hisashi; Oshima, Teruhiko; Fujisaki, Yuichi; Saeki, Taketoshi

    1987-01-01

    Shikoku Electric Power Co., Inc. is constructing No.3 plant adjacently to No.1 and No.2 plants in operation in Ikata Nuclear Power Station. In the coastal area of Iyo-nada, many seaweed fields are distributed, which are important biologically and for fishery. In the works of site preparation for No.3 plant, a part of the site is created by reclamation of sea area, therefore the natural seaweed fields in the area disappear. From the viewpoint of various circumstances and environment preservation, it was decided to create about 60,000 m 2 of seaweed field mounds on the seabed around the site as the substitute for disappearing natural seaweed fields. The Seaweed Field Study Group composed of the men of learning and experience was organized to obtain the guidance on the possibility of creating artificial seaweed fields, the techniques for creation and the effect on environment accompanying the creation of mounds. The creation works were started in October, 1985, and are in progress smoothly utilizing effectively the stones and rocks cut in the site preparation works. The topographic and geological features, sea conditions, the present state of seaweed fields, the experiment on creating artificial seaweed fields, the design and construction of mounds and others are reported. (Kako, I.)

  1. Trouble found in regular inspection of No.1 plant in Ikata Power Station, Shikoku Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1989-01-01

    Since May 2, 1989, the regular inspection of No.1 plant which is a PWR plant with the rated output of 566 MW in Ikata Power Station, Shikoku Electric Power Co., Inc. has been carried out, and eddy current flaw detection inspection was conducted on the total 6585 heating tubes of steam generators except already plugged tubes. As the result, significant indication was observed in 12 heating tubes at the expanded part of the high temperature side tube plates. As to the cause, similarly to those observed in the same plant in the past, it is considered that the residual stress caused by expanding at the time of the manufacture and the internal pressure stress during the operation were superposed, and stress corrosion cracking occurred. It was decided that these 12 defective tubes are plugged. State of plugging in steam generators. Number of total heating tubes: 6776=3388 tubes x 2 steam generators. Number of plugged tubes: 203 including the increase of 12 this time. Ratio of plugging: 3.0 %. Heating tubes: Inconel 600 tubes of φ22.7 mm x 1.27 mm thickness. (K.I.)

  2. Modification and optimisation measures on the demineralisation plant of the Boxberg Power Station; Umbau und Optimierung der Vollentsalzungsanlage im Kraftwerk Boxberg

    Energy Technology Data Exchange (ETDEWEB)

    Leidich, F.U. [ALSTOM Power Generation AG, Mannheim (Germany); Markert, A. [Vattenfall Europe Generation AG Co KG, E-KT, Cottbus (Germany); Hajdamowicz, S. [Vattenfall Europe Generation AG Co KG, E-GBB, Boxberg (Germany); Kleespies, W. [RoKa GmbH, Butzbach (Germany)

    2006-07-01

    The demineralisation plant at the Boxberg Power Station, Unit AQ (Plant IV), owned by Vattenfall Europe Generation AG and Co KG, officially started its operation in 2000. In the course of the operation, technical shortcomings became apparent that rendered the quality of the deionised water inadequate and did prevent the plant from being operated in a normal, fully-automatic mode. Due to the insolvency of the supplier, it had not been possible to eliminate a series of problems and optimise the processes in such a way that the plant could be operated as planned. Nevertheless, thanks to measures like retrofitting the system with lowering loops, replacing the regenerating stations by frequency-controlled excenter-screw propeller pumps, installing automatic vents, and optimising the control concept of the plant, it finally was possible to solve some of the main problems. Longer intervals between regenerating procedures came as an additional benefit. (orig.)

  3. Power stations

    International Nuclear Information System (INIS)

    Cawte, H.; Philpott, E.F.

    1980-01-01

    The object is to provide a method of operating a dual purpose power station so that the steam supply system is operated at a high load factor. The available steam not required for electricity generation is used to provide process heat and the new feature is that the process plant capacity is determined to make the most economic use of the steam supply system, and not to match the passout capacity of the turbine of the turbogenerator. The product of the process plant should, therefore, be capable of being stored. A dual-purpose power station with a nuclear-powered steam source, turbogenerating means connected to the steam source and steam-powered process plant susceptible to wide variation in its rate of operation is described. (U.K.)

  4. New instrument for the confirmation of declared power histories of central station nuclear power plants

    International Nuclear Information System (INIS)

    Dowdy, E.J.; Robba, A.A.; Hastings, R.D.; France, S.W.

    1979-01-01

    An operationally simple, portable, microprocessor-based, unattended reactor power monitor was developed for International Atomic Energy Agency inspector use in confirming operator records of the power history of nuclear power plants. The monitor is based on the principle that the leakage neutron flux outside the biological shield is proportional to the thermal power level. The leakage flux is detected and compared with the leakage flux from the same reactor for a confirmed calibration period. Several output options are available, and a record of more than three months of hourly measurements of the themal power of the plant can be obtained. The monitor has battery backup power for interruptions of host power of duration up to 18 hours

  5. The main methods of solving the problem of radioactive waste management from nuclear power stations and spent fuel reprocessing plants in the USSR

    International Nuclear Information System (INIS)

    1978-09-01

    The main directions of solving the problem of radioactive waste management from nuclear power stations and radiochemical plants, the aspects of gaseous waste management, liquid HLW storage in vessels and the problems of heat removal during storage of vitrified HLW in surface storages are considered. The main problems arising during fine decontamination of gaseous discharges from nuclear power stations and reprocessing plants are discussed. The migration of fission products in the environment and technical aspects of their capture from gaseous discharges are also considered

  6. Sea-water intake tower works for Hamaoka Nuclear Power Station No. 2 Plant

    International Nuclear Information System (INIS)

    Satake, Norimoto; Sugaya, Yoshinobu; Sugimoto, Tadao

    1976-01-01

    It was determined to adopt tunnel system based on the conclusion of negotiation with local people, specifically fishermen, for the sea water intake arrangement in Hamaoka Nuclear Power Station. The main factors for determining the location of the intake tower included marine conditions such as waves and littoral sand drift, and the sea-bottom topographic features and geology of tunnel route, for which field examination, hydraulic experiments and the research and investigation on the method of construction were carried out. These results in the No.2 tower installation at the point 65 m to the east of the No.1 tower. The construction of the tower is described on the manufacture and conveyance of steel caisson, land works at Omaezaki and temporary assembly works on the sea. Then the details of tower installation and the works on site are reported. Fortunately the difficult sea works have been satisfactorily completed earlier than planned, without any accident. The construction facilities utilizing a pilot tunnel seem to have made the better achievement than expected. In spite of the results, the lifting up, off-shore conveyance, and installation of the intake tower caisson, a superheavy structure of weighting up to total 2900 ton, were critical works. (Wakatsuki, Y.)

  7. Sea-water intake tower works for Hamaoka Nuclear Power Station No. 2 Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sataki, N; Sugaya, Y; Sugimoto, T [Chubu Electric Power Co. Inc., Nagoya (Japan)

    1976-01-01

    It was determined to adopt tunnel system based on the conclusion of negotiation with local people, specifically fishermen, for the sea water intake arrangement in Hamaoka Nuclear Power Station. The main factors for determining the location of the intake tower included marine conditions such as waves and littoral sand drift, and the sea-bottom topographic features and geology of tunnel route, for which field examination, hydraulic experiments and the research and investigation on the method of construction were carried out. These results in the No.2 tower installation at the point 65 m to the east of the No.1 tower. The construction of the tower is described on the manufacture and conveyance of steel caisson, land works at Omaezaki and temporary assembly works on the sea. Then the details of tower installation and the works on site are reported. Fortunately the difficult sea works have been satisfactorily completed earlier than planned, without any accident. The construction facilities utilizing a pilot tunnel seem to have made the better achievement than expected. In spite of the results, the lifting up, off-shore conveyance, and installation of the intake tower caisson, a superheavy structure of weighting up to total 2900 ton, were critical works.

  8. Trouble found during regular inspection of No.1 plant in Takahama Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1990-01-01

    No.1 plant in Takahama Power Station, Kansai Electric Power Co., Inc. is a PWR plant with the rated output of 826 MWe. Its regular inspection has been carried out since August 10, 1989, and eddy current flaw detection inspection was performed on the total number of steam generator heating tubes (9619 tubes except already plugged tubes). As the result, significant indication was observed in 6 tubes in the U-bend part, in 6 tubes in the tube-supporting plate part, in 4 tubes in the crevice part in the tube plate, in 9 tubes in the expanded part in the tube plate and in 11 tubes at the boundary of the expanded part, in total in 36 heating tubes, all of them on high temperature side. Consequently, it was decided to plug these 36 defective heating tubes. The heating tubes are those made of Inconel 600, having 22.2 mm outside diameter and 1.27 mm wall thickness. (K.I.)

  9. Troubles detected during regular inspection of No.1 plant in Oi Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1990-01-01

    No. 1 plant in Oi Power Station, Kansai Electric Power Co., Inc. is a PWR plant with rated output of 1175 MW, and its regular inspection is carried out since August 14, 1989. When eddy current flaw detection inspection was carried out on the total number (11426 except already plugged tubes) of the heating tubes of steam generators, significant indication was observed in tube supporting plate part of 279 tubes, at the boundary of tube plate expanded part of 34 tubes, and in the tube plate expanded part of 99 tubes, 411 heating tubes in total (all on high temperature side). Consequently, it was decided to repair 367 tubes using sleeves, and to plug other 44 tubes. Besides, among the heating tubes plugged in the past, it was decided to remove plugs from 161 tubes, and by repairing them with sleeves, to use them again. Total number of heating tubes 13552 (3388 tubes x 4 steam generators), Number of plugged tubes 2009 (decrease by 117 this time), Ratio of plugging 14.8%. (K.I.)

  10. Trouble found during regular inspection of No.3 plant in Mihama Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1990-01-01

    No.3 plant in Mihama Power Station, Kansai Electric Power Co., Inc. is a PWR type plant with the rated output of 826 MWe. Its regular inspection has been carried out since September 11, 1989, and eddy current flaw detection inspection was carried out on the total number of steam generator heating tubes (9997 tubes except already plugged tubes). As the result, significant indication was observed in 24 tubes in the expanded parts in tube plates, and in 36 tubes at the boundary of the expanded parts (all on high temperature side), in total in 60 tubes. Consequently, it was decided to plug these 60 defective heating tubes. The heating tubes are those made of Inconel 600, having 22.2 mm outside diameter and 1.27 mm wall thickness. The total number of heating tubes in 10164 (3388 tubes x 3 steam generators), the number of plugged tubes is 227, and the ratio of plugging is 2.2 %. (K.I.)

  11. Effects of nearby surface features on wind speed at a nuclear plant meteorological station

    International Nuclear Information System (INIS)

    Nielsen, N.A.; Goodwin, R.J.; Pittman, D.E.

    1984-01-01

    There is a definite cause and effect relationship between the trees in the vicinity of the meteorological tower and the wind speed at the 10-meter level on the meteorological tower. For the affected directions, horizontal wind speed is significantly reduced below what it would be for that level if the trees were not present. This effect is only slightly less for the 10:1 exposure achieved with the 1977 tree clearing, which illustrates that meeting this commonly accepted distance to height ratio does not assure representativeness of 10-meter data collected at a nuclear plant site. The somewhat stronger effect for winds from the south through southwest directions may be partly attributable to the abrupt change in roughness and elevation encountered by air moving at an angle or directly across the reservoir, which is 3.5 to 5.0 kilometers wide at this site. This general reduction in wind speed values below what would be expected at the plant location will result in biased dispersion estimates. Calculated relative concentration values for releases treated as ground-level or building-wake releases would be larger than actual concentrations. While this would provide conservative concentration values, radioactive plume transport calculations would be nonconservative. The calculated, or predicted, transport rate would be slower than the actual transport rate. Such local biases affecting the spatial representativeness of airflow at 10 meters are a primary reason for TVA's decision to use 46-meter wind data for ground-level transport and diffusion modeling in its radiological emergency preparedness program

  12. Islands for nuclear power stations

    International Nuclear Information System (INIS)

    Usher, E.F.F.W.; Fraser, A.P.

    1981-01-01

    The safety principles, design criteria and types of artificial island for an offshore nuclear power station are discussed with particular reference to siting adjacent to an industrial island. The paper concludes that the engineering problems are soluble and that offshore nuclear power stations will eventually be built but that much fundamental work is still required. (author)

  13. Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

    International Nuclear Information System (INIS)

    1983-06-01

    The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  14. Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

    International Nuclear Information System (INIS)

    1983-02-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  15. Air pollution reduction in thermoelectric power stations - case study: Iquitos power plant; Reducao do impacto da poluicao do ar em usinas termeletricas - estudo de caso: usina termeletrica Iquitos

    Energy Technology Data Exchange (ETDEWEB)

    Dondero, Luz [Sao Paulo Univ., SP (Brazil). Inst. de Energia e Eletrotecnica. Programa Interunidades de Pos-graduacao em Energia]. E-mail: luz@iee.usp.br

    2000-07-01

    This work studies the environmental impacts of atmospheric emissions sent out by the Iquito's thermoelectric power station in Peru. Initially, we compute the quantitative flows (in g/s) of major gas pollutants (SO{sub 2}, SO{sub 3}, NOx, CO, CO{sub 2} and MP) emitted by the power plant. Then, we calculate the station's emission rates per kWh generated (in kilogram of pollutant /kWh). Having those inputs, we adopt EPA's SCREEN3.0 dispersion model to simulate the SO{sub 2} and NOx into the local atmosphere. We also forecast the future evolution of SO{sub 2} emissions considering the potential growth of electricity generation in the power plant. Since the Iquito's power station is located within the city's urban area, with gas emissions having direct impacts upon the local population, we study different strategies for emissions reduction from the plant. Firstly, we consider the upgrading of the existing plant with additional equipment for a more strict emission control. Then, we analyze the option of shutting down the most critical machine (in terms of atmospheric emission) in the old plant, and its substitution by a new and more efficient machine. We concluded that, although the addition of more strict control equipment is more efficient on reducing total emission, the strategy of exchanging machines is less costly and should be consider as the preferable option. (author)

  16. Product quality follow-up for the start of an industrial plant, e.g.: The waste station No 3 at La Hague

    International Nuclear Information System (INIS)

    Saas, A.; Vidal, H.; Alvy, J.C.; Boudry, J.C.; Bouin, R.

    1990-01-01

    During the start-up of the plant for waste treatment and mud coating in bitumen (waste station No 3 La Hague), the Characterization and Estimate of Containments and Analyses Service performed several different controls and tests to verify: whether the industrial plant was operating according to the defined procedure, whether the coated products obtained were in line with provisional specifications, whether the operational sector of the plant ensured the final quality of the coated product. The main results of these measurements and tests are presented in this paper. (orig./DG)

  17. Systems analysis of radiation safety during dismantling of power-plant equipment at a nuclear power station

    International Nuclear Information System (INIS)

    Bylkin, B.K.; Shpitser, V.Ya.

    1993-01-01

    A systems analysis of the radiation safety makes possible an ad hoc determination of the elements forming the system, as well as the establishment of the characteristics of their interaction with radiation-effect factors. Here the authors will present part of the hierarchical analysis procedure, consisting in general of four separate procedures. The purpose is to investigate and analyze the mean and stable (on the average) indices of radiation safety, within the framework of alternative mathematical models of dismantling the power-plant equipment of a nuclear power station. The following three of the four procedures are discussed: (1) simulated projection, of the processing of radioactive waste; (2) analysis of the redistribution of radionuclides during the industrial cycle of waste treatment; (3) planning the collective dose load during the dismantling operation. Within the framework of the first of these procedures, the solutions to the problem of simulating a waste-treatment operation of maximum efficiency are analyzed. This analysis is based on the use of a data base for the parameters of the installations, assemblies, and equipment, enabling the integration of these in a simulation of a complex automated facility. The results were visualized in an AUTOCAD-10 medium using a graphical data base containing an explanation of the rooms

  18. Results of 7th regular inspection of No.1 plant in Oi Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1989-01-01

    The 7th regular inspection of No.1 plant in Oi Power Station was carried out from December 25, 1987 to July 15, 1988. The parallel operation was resumed on June 23, 1988, 182 days after the start of the inspection. The facilities to be inspected were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation and emergency power generation system. On these facilities to be inspected, the appearance, disassembling, leak, function, performance and other inspections were carried out, and as the results, a part of the fitting of a water chamber partition cover for a steam generator broke off, significant signals were observed in 936 heating tubes of steam generators, 72 bolts for fixing the blade of a primary coolant pump were damaged, and leak was found in two fuel assemblies. The works related to this regular inspection were accomplished within the range of allowable radiation dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were the use of the fuel containing gadolinia, the removal of a thermometer bypass piping and the repair of defective steam generator tubes. (K.I.)

  19. Comparison of oxide- and metal-core behavior during CRBRP [Clinch River Breeder Reactor Plant] station blackout

    International Nuclear Information System (INIS)

    Polkinghorne, S.T.; Atkinson, S.A.

    1986-01-01

    A resurrected concept that could significantly improve the inherently safe response of Liquid-Metal cooled Reactors (LMRs) during severe undercooling transients is the use of metallic fuel. Analytical studies have been reported on for the transient behavior of metal-fuel cores in innovative, inherently safe LMR designs. This paper reports on an analysis done, instead, for the Clinch River Breeder Reactor Plant (CRBRP) design with the only innovative change being the incorporation of a metal-fuel core. The SSC-L code was used to simulate a protected station blackout accident in the CRBRP with a 943 MWt Integral Fast Reactor (IFR) metal-fuel core. The results, compared with those for the oxide-fueled CRBRP, show that the margin to boiling is greater for the IFR core. However, the cooldown transient is more severe due to the faster thermal response time of metallic fuel. Some additional calculations to assess possible LMR design improvements (reduced primary system pressure losses, extended flow coastdown) are also discussed. 8 refs., 13 figs., 2 tabs

  20. Élimination des micropolluants par les stations d’épuration domestiques Removal of micropollutants by wastewater treatment plants

    Directory of Open Access Journals (Sweden)

    CHOUBERT, Jean-Marc ; POMIES, Maxime ; MARTIN-RUEL, Samuel ; BUDZINSKI, Hélène ; MIEGE, Cécile ; WISNIEWSKI, Christelle ; COQUERY, Marina

    2012-12-01

    Full Text Available Produits industriels, détergents, hydrocarbures, pesticides, médicaments : les stations d'épuration domestiques sont-elles efficaces pour éliminer toutes les substances chimiques issues des activités humaines retrouvées dans les milieux aquatiques? Cet article présente les principales connaissances récemment acquises relatives au comportement et au devenir des micropolluants dans les différentes filières de traitement des eaux ainsi que les perspectives d'amélioration des procédés.Domestic wastewater treatment plants were not designed for micropollutants removal. They perform substantial removal of several micropollutants, mainly by sorption process onto biological sludge and by biodegradation from the liquid phase for some substances. This article presents the main recent advances on the fate of micropollutants through primary, secondary and tertiary treatment processes. It also addresses research in progress for the optimization of micropollutants removal.

  1. Result of 11th regular inspection of No.1 plant in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The 11th regular inspection of No.1 plant in Shimane Nuclear Power Station was carried out from January 9 to July 2, 1986. The parallel operation was resumed on June 19, 1986, 162 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, as the result, any abnormality was not found. The works related to this regular inspection were accomplished within the range of the allowable radiation dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were as follows. Feed water spargers were replaced with those of welded type, the material of the drain pipe for No.3 feed heater was changed to STPA 23, an exhaust compressor, an exhaust gas-water separator and others, which have not been used, were removed, and the connecting pipe for a liquid nitrogen evaporator was installed. (Kako, I.)

  2. Results of 8th regular inspection of No.2 plant in Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1989-01-01

    The 8th regular inspection of No.2 plant in Hamaoka Nuclear Power Station was carried out from January 23 to June 28, 1988. The parallel operation was resumed on June 13, 1988, 143 days after the parallel off. The facilities to be inspected were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation and emergency power generation system. On these facilities to be inspected, the appearance, disassembling, leak, function, performance and other inspections were carried out, and as the result, abnormality was not found. However, during the preparation for running-in after starting up the reactor, the leak from a steam drain piping was found, therefore it was repaired. The works related to this regular inspection were accomplished within the range of allowable radiation dose based on the relevant laws. The maim reconstruction works carried out during the period of this regular inspection were the replacement of the components of cooling seawater pumps, the repair of a steam drain piping in the high pressure injection system and the replacement of LP turbine rotors. (K.I.)

  3. Near-term feasibility of nuclear reactors for seawater desalting. Coupling of standard condensing nuclear power stations to low-grade heat multieffect distillation plants

    International Nuclear Information System (INIS)

    Adar, J.; Manor, S.; Schaal, M.

    1977-01-01

    The paper describes the horizontal aluminium tube, multieffect distillation process developed by Israel Desalination Engineering Ltd., which is very suitable for the use of low-grade heat from standard condensing nuclear turbines operating at increased back-pressure. A special flash-chamber constitutes a positive barrier against any possible contamination being carried over by the steam exhausted from the turbine to the desalination plant. Flow sheets, heat and mass balances have been prepared for two standard sizes of NSSS and turbines, two back-pressures, and corresponding desalination plants. Only standard equipment is being used in the steam and electricity-producing plant. The desalination plant consists of 6 to 12 parallel double lines, each of them similar to a large prototype now being designed and which will be coupled to an old fossil-fuel power station. Total energy requirements of the desalination plant represent only 19 to 50% of the total water cost as against 75% for a single-purpose plant. Costs are based on actual bids for the power plant and actual estimates for the desalination prototype. The operation is designed to be flexible so that the power plant can be operated either in conjunction with the desalination plant, or as a single-purpose plant. (author)

  4. Fixed Point of Generalized Eventual Cyclic Gross in Fuzzy Norm Spaces for Contractive Mappings

    Directory of Open Access Journals (Sweden)

    S. A. M. Mohsenialhosseini

    2015-01-01

    Full Text Available We define generalized eventual cyclic gross contractive mapping in fuzzy norm spaces, which is a generalization of the eventual cyclic gross contractions. Also we prove the existence of a fixed point for this type of contractive mapping on fuzzy norm spaces.

  5. On accumulation of 90Sr and 137Cs by some lower plants in the vicinity of the Beloyarsky atomic power station in the Urals

    International Nuclear Information System (INIS)

    Nifontova, M.G.; Kulikov, N.V.

    1981-01-01

    The data are given on the content of 90 Sr and 137 Cs in thalluses of the foliose epiphytic lichen Hypogymnia physodes (L) and in a number of the most widely distributed in nature edxble fungi that grow in the forests of the sanitary-protective zone of the Beloyarsk nuclear power station in the Middle Urals: russula-Russula cyaxantha (Schw)Fr; brown cap boletus-Leccinum scabrum (Fe)S.F.Gray, milk-agaric-Lactarius resimus Fr., russula-Russula foetens (Fr.)Fr. It has been ascertained that the concentration of 90 Sr and 137 Cs in epiphytic lichens and edible agaric fungi in the vicinity of the Beloyarsk nuclear power station does not exceed the background content of these radionuclides characteristic of analogous plants in other locations outside the range of a possible effect of the nuclear power station [ru

  6. Evaluation of Station Blackout accidents at nuclear power plants. Technical findings related to Unresolved Safety Issue A-44. Draft report for comment

    International Nuclear Information System (INIS)

    Baranowsky, P.W.

    1985-05-01

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

  7. Emission and profile characteristic of volatile organic compounds emitted from coke production, iron smelt, heating station and power plant in Liaoning Province, China.

    Science.gov (United States)

    Shi, Jianwu; Deng, Hao; Bai, Zhipeng; Kong, Shaofei; Wang, Xiuyan; Hao, Jiming; Han, Xinyu; Ning, Ping

    2015-05-15

    107 kinds of C₂-C₁₂ volatile organic compound (VOC) mass concentrations and profiles for four types of coal-fired stationary sources in Liaoning Province were studied by a dilution sampling system and GC-MS analysis method, which are of significant importance with regard to VOC emissions in northeast of China. The results showed that there were some differences among these VOC source profiles. The total mass concentrations of analyzed 107 VOC species varied from 10,917 to 19,652 μg m(-3). Halogenated hydrocarbons exhibited higher mass percentages for the VOC source profiles of iron smelt (48.8%) and coke production plant (37.7%). Aromatic hydrocarbons were the most abundant in heating station plant (69.1%). Ketones, alcohols and acetates held 45.0% of total VOCs in thermal power plant. For non-methane hydrocarbons (NMHCs), which are demanded for photochemical assessment in the USA, toluene and n-hexane were the most abundant species in the iron smelt, coke production and thermal power plant, with the mass percentages of 64.8%, 52.7% and 38.6%, respectively. Trimethylbenzene, n-propylbenzene and o,m-ethyltoluene approximately accounted for 70.0% in heating station plant. NMHCs emitted from coke production, iron smelt, heating station and power plant listed above presented different chemical reactivities. The average OH loss rate of NMHCs from heating station, was 4 to 5.6 times higher than that of NMHCs from iron smelt, coke production and power plant, which implies that VOCs emitted from heating station in northeast of China should be controlled firstly to avoid photochemical ozone pollution and protect human health. There are significant variations in the ratios of benzene/toluene and m, p-xylene/ethylbenzene of these coal-fired source profiles. The representativeness of the coal-fired sources studied and the VOC samples collected should be more closely examined. The accuracy of VOC source profiles related to coal-fired processes is highly dependent on

  8. Quality control of concrete in construction of No.2 and No.5 plants in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Yamashita, Toshio; Nukui, Yasushi; Nojiri, Takaharu.

    1990-01-01

    The construction site and its weather condition are outlined. In the Nuclear Power Station, No.1 plant and No.5 plant with 1100 MWe output each have been already in operation, and No.2 plant with 1100 MWe output is about to start the operation. In this report, the quality control of about 700,000 m 3 of concrete used for No.2 and No.5 plants construction from October, 1983 to November, 1989 is described. The features of the concrete used are shown. The facilities for producing the concrete, which were set up in the construction site, the mixing of the concrete and the quality control are reported. The system for carrying out the quality control of materials and concrete is shown with a flowchart. The material testing on cement, aggregate, water quality, fly ash and chemical additives was carried out. The slump, air quantity, temperature, strength and specific gravity of concrete were tested. (K.I.)

  9. Construction works of large scale impervious wall in construction of No.2 plant in Onagawa Nuclear Power Station, Tohoku Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Ueda, Kozaburo; Sugeno, Yoshisada; Takahashi, Hitoshi

    1991-01-01

    The main buildings for No. 2 plant in Onagawa Nuclear Power Station are constructed on the bedrocks about 14 m below the sea surface. Therefore, for the purpose of executing the works by shutting seawater off and dry work, the large scale impervious wall of about 500 m extension was installed underground. The feature of this impervious wall is the depth of embedment of about 3 m into the hard bedrocks having the uniaxial compressive strength of 2000 kg/cm 2 at maximum, carried out with the newly developed hard rock excavator. The outline of these construction works is reported. No. 2 plant in Onagawa Nuclear Power Station is the BWR plant of 825 MWe output. The construction works of the power station were began in August, 1989, and the rate of progress in civil engineering works as of the end of September, 1990 was 21.3%. The planning of the impervious wall, the geological features at the site, the method of shutting seawater off, the selection of wall materials, the design of the wall body, the investigation of the quantity of spring water, the execution of the construction and execution management, and the confirmation of the effect of the wall are reported. (K.I.)

  10. Integrated-plant-safety assessment Systematic Evaluation program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245

    International Nuclear Information System (INIS)

    1982-11-01

    The Systematic Evaluation Program was initiated in February 1977 to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  11. Greenhouse (III): Gas-Exchange and Seed-to-Seed Experiments on the Russian Space Station MIR and Earth-grown, Ethylene-Treated Wheat Plants

    Science.gov (United States)

    Campbell, William F.; Bingham, Gail; Carman, John; Bubenheim, David; Levinskikh, Margarita; Sytchev, Vladimir N.; Podolsky, Igor B.; Chernova, Lola; Nefodova, Yelena

    2001-01-01

    The Mir Space Station provided an outstanding opportunity to study long-term plant responses when exposed to a microgravity environment. Furthermore, if plants can be grown to maturity in a microgravity environment, they might be used in future bioregenerative life-support systems (BLSS). The primary objective of the Greenhouse experiment onboard Mir was to grow Super Dwarf and Apogee wheat through complete life cycles in microgravity; i.e., from seed-to-seed-to-seed. Additional objectives were to study chemical, biochemical, and structural changes in plant tissues as well as photosynthesis, respiration, and transpiration (evaporation of water from plants). Another major objective was to evaluate the suitability clothe facilities on Mir for advanced research with plants. The Greenhouse experiment was conducted in the Russian/Bulgarian plant growth chamber, the Svet, to which the United States added instrumentation systems to monitor changes in CO2 and water vapor caused by the plants (with four infrared gas analyzers monitoring air entering and leaving two small plastic chambers). In addition, the US instrumentation also monitored O2; air, leaf (IR), cabin pressure; photon flux; and substrate temperature and substrate moisture (16 probes in the root module). Facility modifications were first performed during the summer of 1995 during Mir 19, which began after STS-72 left Mir. Plant development was monitored by daily observations and some photographs.

  12. Duty health physicist program at Byron Nuclear Power Station - a cost-effective way to manage routine plant health physics activities

    International Nuclear Information System (INIS)

    Goldsmith, D.G.; Carey, T.R.

    1987-01-01

    The Duty Health Physicist Program at Byron Station was established to deal with routine health physics tasks and provide an interface between frontline and upper radiation-chemistry management. The program consists of a weekly rotation of selected members of the health physics staff into the duty health physicist position to handle the assigned duty tasks. The tasks include, but are not limited to, daily isotopic and air sample review, effluent release package review, maximum permissible concentration calculations, dose approvals, as-low-as-reasonably-achievable action review of pending jobs, and general availability to answer questions and address problems in health-physics-related areas of plant operation. The daily attendance of the duty health physicist at the radiation-chemistry and station plan-of-the-day meetings has increased the overall presence and visibility of the health physics program to upper station management and other station departments. Since its inception in July of 1985, the Duty Health Physics Program has been a major contributor to the observed 50% reduction in reportable personnel errors in the radiation-chemistry department

  13. An assessment of invasive plant species monitored by the Northern Research Station Forest Inventory and Analysis Program, 2005 through 2010

    Science.gov (United States)

    Cassandra M. Kurtz

    2013-01-01

    Invasive plant species are a worldwide concern due to the high ecological and economic costs associated with their presence. This document describes the plant characteristics and regional distribution of the 50 invasive plant species monitored from 2005 through 2010 on forested Phase 2 (P2) Forest Inventory and Analysis (FIA) plots in the 24 states of the Northern...

  14. Integrated Plant Safety Assessment: Systematic Evaluation Program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245. Final report

    International Nuclear Information System (INIS)

    1983-02-01

    This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in November 1982

  15. Integrated plant safety assessment: Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206): Final report

    International Nuclear Information System (INIS)

    1986-12-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of San Onofre Nuclear Generating Station, Unit 1, operated by Southern California Edison Company. The San Onofre plant is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. This report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the draft report issued in April 1985

  16. Integrated plant safety assessment: systematic evaluation program. Oyster Creek nuclear generating station. GPU Nuclear Corporation and Jersey Central Power and Light Company. Docket No. 50-219

    International Nuclear Information System (INIS)

    1982-09-01

    The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Oyster Creek Nuclear Generating Station (located in Ocean County, New Jersey), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  17. Integrated-plant-safety assessment Systematic Evaluation Program. Dresden Nuclear Power Station, Unit 2, Commonwealth Edison Company, Docket No. 50-237

    International Nuclear Information System (INIS)

    1982-10-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of Dresden Nuclear Generating Station, Unit 2 owned and operated by the Commonwealth Edison Company and located in Grundy County, Illinois. Dresden Unit 2 is one of ten plants reviewed under Phase II of this program, which indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  18. Eventual Suicide in Interrupted and Uninterrupted Attempters: A Challenge to the Cry-for-Help Hypothesis.

    Science.gov (United States)

    Steer, Robert A.; And Others

    1988-01-01

    Followed patients (N=499) hospitalized for suicide attempts (attempters) between 1970 and 1975 until 1982. Found under six percent eventually committed suicide. Found the interrupted attempters were approximately three times more likely to commit suicide than were the uninterrupted attempters. (Author/ABL)

  19. Defending the Counseling Model and Its Eventual Synthesis with the Medical Model.

    Science.gov (United States)

    Farrell, Madison, III

    This paper explores the strengths and weaknesses of the medical model in an effort to promote a counseling perspective that embraces some of the medical models strengths. Through inclusion, rather than exclusion, it is believed that the counseling model will eventually infiltrate the medical model by way of its own documentation system. With its…

  20. Neural Indices of Semantic Processing in Early Childhood Distinguish Eventual Stuttering Persistence and Recovery

    Science.gov (United States)

    Kreidler, Kathryn; Wray, Amanda Hampton; Usler, Evan; Weber, Christine

    2017-01-01

    Purpose: Maturation of neural processes for language may lag in some children who stutter (CWS), and event-related potentials (ERPs) distinguish CWS who have recovered from those who have persisted. The current study explores whether ERPs indexing semantic processing may distinguish children who will eventually persist in stuttering…

  1. An ecophysiological study of plants growing on the fly ash deposits from the "Nikola Tesla-A" thermal power station in Serbia.

    Science.gov (United States)

    Pavlović, Pavle; Mitrović, Miroslava; Djurdjević, Lola

    2004-05-01

    This ecophysiological research on the ash deposits from the "Nikola Tesla-A" thermal power station in Serbia covered 10 plant species (Tamarix gallica, Populus alba, Spiraea van-hauttei, Ambrosia artemisifolia, Amorpha fruticosa, Eupatorium cannabinum, Crepis setosa, Epilobium collinum, Verbascum phlomoides, and Cirsium arvense). This paper presents the results of a water regime analysis, photosynthetic efficiency and trace elements (B, Cu, Mn, Zn, Pb, and Cd) content in vegetative plant parts. Water regime parameters indicate an overall stability in plant-water relations. During the period of summer drought, photosynthetic efficiency (Fv/Fm) was low, ranging from 0.429 to 0.620 for all the species that were analyzed. An analysis of the tissue trace elements content showed a lower trace metal concentration in the plants than in the ash, indicating that heavy metals undergo major concentration during the combustion process and some are not readily taken up by plants. The Zn and Pb concentrations in all of the examined species were normal whereas Cu and Mn concentrations were in the deficiency range. Boron concentrations in plant tissues were high, with some species even showing levels of more than 100 microg/g (Populus sp., Ambrosia sp., Amorpha sp., and Cirsium sp.). The presence of Cd was not detected. In general, it can be concluded from the results of this research that biological recultivation should take into account the existing ecological, vegetation, and floristic potential of an immediate environment that is abundant in life forms and ecological types of plant species that can overgrow the ash deposit relatively quickly. Selected species should be adapted to toxic B concentrations with moderate demands in terms of mineral elements (Cu and Mn).

  2. Near term feasibility of nuclear reactor for sea-water desalting: coupling of standard condensing nuclear power stations to low grade heat multieffect distillation plants

    International Nuclear Information System (INIS)

    Adar, J.; Manor, S.; Schaal, M.

    1977-01-01

    Commercial nuclear power reactors exist only in standard sizes and designs. No large nuclear back-pressure turbines are available today. Therefore, near term large scale nuclear desalination plants must be tailored to the NSSS sizes and available turbines and not the contrary. Standard condensing nuclear turbines could operate continuously with a back-presure of up to 5-7'' Hg (depending on the supplier). It means that they can exhaust huge amounts of steam at 56 0 C - 64 0 C with a loss of electricity production of 6% - 10% when compared to 2 1/2'' Hg normal condensing pressure. The horizontal aluminium tube multi-effect distillation process developed by ''Israel Desalination Engineering'' Ltd. is very suitable for the use of such low-grade heat: 4 to 9 effects can operate within these temperature ranges. A special flash-chamber constitutes a positive barrier against any possible contamination being carried over by the steam exhausted from the turbine to the desalination plant. Flow sheets, heat and mass balances have been prepared for two standard sizes of NSSS and turbines (1882sup(Mwth) and 2785sup(Mwth)), two ''back-pressures'' (5 1/2'' and 7'' Hg), and corresponding desalination plants. Only standard equipment is being used in the steam and electricity producing plant. The desalination plant consists of 6 to 12 parallel double lines, each of them similar to a large prototype now being designed and which is going to be coupled to an old fossil power station. Water production varies between 50 and 123 sup(us MGD) and water cost between 23 and 36 sup(cents)/M 3 . Total energy requirements of the desalination plant represent only 19 to 50% of the total water cost as against 75% for a single purpose plant. Costs are based on actual bids for the power plant and actual estimates for the desalination prototype. The operation is designed to be flexible so that the power plant can be operated either in conjunction with the desalination plant, or as a single purpose

  3. Results of evaluation of periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1994-01-01

    No. 1 plant in Fukushima No. 1 Nuclear Power Station started the commercial power generation in March, 1971, and has continued the operation for more than 23 years. During this period, the countermeasures to troubles, periodic inspections, and the maintenance by the electric power company have been carried out. These states are to be recollected from the viewpoints of the comprehensive evaluation of the operation experiences and the reflection of the latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor was 50.1% on the average of about 23 years, but in the last 10 years, it was improved to 59.7%. In the last five years, the rate of occurrence of unexpected shutdown was 0.4 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, radioactive waste management and the reflection of the experience of troubles and the latest technological knowledge to the improvement of safety have been carried out properly. The work plan for disaster prevention was established. (K.I.)

  4. Comparison of vibrational noise, between thermal power station (T.P.S.) Jamshoro and thermal power plant (T.P.P.) Pakistan Steel Bin Qasim Karachi

    International Nuclear Information System (INIS)

    Zaheer-ud-Din Memon

    2003-01-01

    Vibrational Noise is one of the major environmental problems in Industrial Plants. The Noise study has been under taken in (Japanese Unit) Thermal Power Station (TPS) Jamshoro, which generates 250 MW since Jan: 1990 and Russian Unit Thermal Power Plant (TPP) Pak Steel Bin Qasim Karachi, generates 165 MW since 1984. The prevailing Noise has been recorded in detail; at Basement area feed pumps, Turbines, Boilers F.D.F, I.D.F and Compressor houses. Comparing these two Plants, the Noise Level found more Intensive i.e. 97- 114 dB(A) at TPP Pak Steel Bin Qasim as against 91.4 -96.3 dB(A) at TPS Jamshoro, which was even higher one in the light of ISO and other National Standards. In the light of permissible Occupational Noise exposure limits, as allowed by the ISO and other National Standards, some recommendations have been made to provide safety measures for workers against high level noise health hazards like head ache, hearing problem, irritation, accidents at work, tension, disturbance to work and so many psychological effects, along with guidelines to improve the efficiency of the plants. (author)

  5. Prospects for the utilization of small nuclear plants for civil ships, floating heat and power stations and power seawater desalination complexes

    International Nuclear Information System (INIS)

    Polunichev, V.I.

    2000-01-01

    Small power nuclear reactor plants developed by OKB Mechanical Engineering are widely used as propulsion plants in various civil ships. Russia is the sole country in the world that possesses a powerful icebreaker and transport fleet which offers effective solution for vital socio-economic tasks of Russia's northern regions by maintaining a year-round navigation along the Arctic sea route. In the future, intensification of freighting volumes is expected in Arctic seas and at estuaries of northern rivers. Therefore, further replenishment of nuclear-powered fleet is needed by new generation ice-breakers equipped with advanced reactor plants. Adopted progressive design and technology solutions, reliable equipment and safety systems being continuously perfected on the basis of multi year operation experience feedback, addressing updated safety codes and achievement of science and technology, allow the advanced propulsion reactor plants of this type to be recommended as energy sources for floating heat and power co-generation stations and power-seawater desalination complexes. (author)

  6. Solar thermal power stations for activities implemented jointly. The Theseus 50 MWe solar thermal power plant for the island of Crete, Greece

    Energy Technology Data Exchange (ETDEWEB)

    Brakmann, Georg [Fichtner, Stuttgart (Germany); Aringhoff, Rainer [Pilkington Solar International (United Kingdom); Cobi, Arend [PreussenElektra (Germany)

    1998-09-01

    THESEUS, the proposed commercial 50 MWe (net) Thermal Solar European Power Station for the Island of Crete is a solar hybrid plant with parabolic trough collectors and an advanced high efficiency Rankine reheat steam cycle. At the end of 1996 the DG XVII (Energy) of the European Commission has accepted the THERMIE application of the THESEUS consortium for the design phase. THESEUS reduces the required oil imports by 28 000 t/a, thereby saving the Greek economy every year 4 million ECU in foreign currency. During its 25 years technical lifetime 2.2 million tons of CO{sub 2} emissions will be avoided. Supply, construction, erection and operation of THESEUS creates 2 000 qualified employments (man-years). Because of the high manpower intensity of solar plants and their larger capital income from interest payments in contrast to the high fuel import intensity of fossil plants, THESEUS will generate larger tax revenues for Greece and for the supplier`s countries. The investment cost of THESEUS is some 135 million ECU. Even without any subsidies this would result in electricity generation cost of some 0.085 ECY/kWh, which is lower than the current average cost from the existing power plants of Crete. (author)

  7. Considerations on the role of natural ecosystems in the eventual contamination of man and his environment

    International Nuclear Information System (INIS)

    Desmet, G.; Myttenaere, C.

    1988-01-01

    After the Chernobyl event, the problem of contamination of natural and semi-natural ecosystems has been particularly salient even where these non-agricultural land areas appear to generate only a small fraction of the annual food intakes of certain populations. A concise discussion of some features of natural ecosystems is presented here, with the objective of stimulating a closer inspection of the relative impact of these natural ecosystems on the eventual dose to man. The ability of natural systems to scavenge considerable amounts of contamination is emphasized and it is suggested that there is a need for further work to quantify the importance of these environments, relative to agricultural systems, in terms of producing eventual transfers to man. (author)

  8. Aerial radiological survey of the Three Mile Island Station Nuclear Power Plant (Goldsboro, Pennsylvania). Date of survey: August 1976

    International Nuclear Information System (INIS)

    Fritzsche, A.E.

    1977-03-01

    An airborne radiological survey of an 2143 km 2 area surrounding the Three Mile Island Station was made during August 2 to August 4, 1976. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from the normal background emitters. Areal average exposure rates equivalent to one meter above the ground are presented in the form of an isopleth map. Geological data are presented in an isopleth map of rock and soil types; a brief description of the vegetation and terrain surrounding the site is also included

  9. A qualitative study of medical students in a rural track: views on eventual rural practice.

    Science.gov (United States)

    Roseamelia, Carrie; Greenwald, James L; Bush, Tiffany; Pratte, Morgan; Wilcox, Jessica; Morley, Christopher P

    2014-04-01

    Rural tracks (RTs) exist within medical schools across the United States. These programs often target those students from rural areas and those with primary care career interests, given that these factors are robust predictors of eventual rural practice. However, only 26% to 64% of graduates from RTs enter eventual rural practice. We conducted a qualitative, exploratory study of medical students enrolled in one school's RT, examining their interests in rural training, specialization, and eventual rural practice, via open coding of transcripts from focus groups and in-depth individual interviews, leading to identification of emerging themes. A total of 16 out of 54 eligible first- and second-year preclinical medical students participated in focus group sessions, and a total of seven out of 17 eligible third- and fourth-year medical students participated in individual interviews. Analyses revealed the recognition of a "Rural Identity," typical characteristics, and the importance of "Program Fit" and "Intentions for Practice" that trended toward family medicine specialization and rural practice. However, nuances within the comments reveal incomplete commitment to rural practice. In many cases, student preference for rural practice was driven largely by a disinterest in urban practice. Students with rural and primary care practice interests are often not perfectly committed to rural practice. However, RTs may provide a haven for such students within medical school.

  10. The predictive value of 2-year posttreatment biopsy after prostate cancer radiotherapy for eventual biochemical outcome

    International Nuclear Information System (INIS)

    Vance, Waseet; Tucker, Susan L.; Crevoisier, Renaud de; Kuban, Deborah A.; Cheung, M. Rex

    2007-01-01

    Purpose: To determine the value of a 2-year post-radiotherapy (RT) prostate biopsy for predicting eventual biochemical failure in patients who were treated for localized prostate cancer. Methods and Materials: This study comprised 164 patients who underwent a planned 2-year post-RT prostate biopsy. The independent prognostic value of the biopsy results for forecasting eventual biochemical outcome and overall survival was tested with other factors (the Gleason score, 1992 American Joint Committee on Cancer tumor stage, pretreatment prostate-specific antigen level, risk group, and RT dose) in a multivariate analysis. The current nadir + 2 (CN + 2) definition of biochemical failure was used. Patients with rising prostate-specific antigen (PSA) or suspicious digital rectal examination before the biopsy were excluded. Results: The biopsy results were normal in 78 patients, scant atypical and malignant cells in 30, carcinoma with treatment effect in 43, and carcinoma without treatment effect in 13. Using the CN + 2 definition, we found a significant association between biopsy results and eventual biochemical failure. We also found that the biopsy status provides predictive information independent of the PSA status at the time of biopsy. Conclusion: A 2-year post-RT prostate biopsy may be useful for forecasting CN + 2 biochemical failure. Posttreatment prostate biopsy may be useful for identifying patients for aggressive salvage therapy

  11. Coal-water slurries containing petrochemicals to solve problems of air pollution by coal thermal power stations and boiler plants: An introductory review.

    Science.gov (United States)

    Dmitrienko, Margarita A; Strizhak, Pavel A

    2018-02-01

    This introductory study presents the analysis of the environmental, economic and energy performance indicators of burning high-potential coal water slurries containing petrochemicals (CWSP) instead of coal, fuel oil, and natural gas at typical thermal power stations (TPS) and a boiler plant. We focus on the most hazardous anthropogenic emissions of coal power industry: sulfur and nitrogen oxides. The research findings show that these emissions may be several times lower if coal and oil processing wastes are mixed with water as compared to the combustion of traditional pulverized coal, even of high grades. The study focuses on wastes, such as filter cakes, oil sludge, waste industrial oils, heavy coal-tar products, resins, etc., that are produced and stored in abundance. Their deep conversion is very rare due to low economic benefit. Effective ways are necessary to recover such industrial wastes. We present the cost assessment of the changes to the heat and power generation technologies that are required from typical power plants for switching from coal, fuel oil and natural gas to CWSPs based on coal and oil processing wastes. The corresponding technological changes pay off after a short time, ranging from several months to several years. The most promising components for CWSP production have been identified, which provide payback within a year. Among these are filter cakes (coal processing wastes), which are produced as a ready-made coal-water slurry fuel (a mixture of flocculants, water, and fine coal dust). These fuels have the least impact on the environment in terms of the emissions of sulfur and nitrogen oxides as well as fly ash. An important conclusion of the study is that using CWSPs based on filter cakes is worthwhile both as the main fuel for thermal power stations and boiler plants and as starting fuel. Copyright © 2017 Elsevier B.V. All rights reserved.

  12. Combination of a pyrolysis plant with a hard coal power station firing system; Kombination einer Pyrolyseanlage mit einer Steinkohlekraftwerksfeuerung

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, W.; Hauk, R. [Vereinigte Elektrizitaetswerke Westfalen AG (VEW), Dortmund (Germany)

    1998-09-01

    VEW ENERGIE AG plans and operates power plants and thermal plants for the disposal of residual materials (e.g. household waste, sewage sludge, used wood, residues from paper manufacture). In order to make itself familiar with the market for secondary fuels the company undertook a study to find out what cost-effective techniques are available on the market and how power plants can be used for optimal energy use and with a minimum of disposal costs. Its choice finally fell on pyrolysis because this technology is the most flexible for the thermal and physical utilisation of substitute fuels. Moreover, pyrolysis combines very well with power plants. [Deutsch] VEW ENERGIE AG plant und betreibt Kraftwerke und thermische Anlagen zur Entsorgung von Reststoffen (z.B. Hausmuell, Klaerschlamm, Altholz, Reststoff aus der Papierherstellung). Um sich auf dem Markt der Ersatzbrennstoffe einzustellen, wurde untersucht, welche kostenguenstigen Techniken auf dem Markt verfuegbar sind und wie Kraftwerke zur optimalen Energienutzung und zur Minimierung der Entsorgungskosten eingesetzt werden koennen. Die Pyrolysetechnik wurde ausgewaehlt, weil sie am flexibelsten fuer die thermische und stoffliche Verwertung der Ersatzbrennstoffe ist. Sie laesst sich auch sehr gut mit Kraftwerken kombinieren. (orig.)

  13. United Kingdom. Development plan for the eventual closure of the UK Drigg nuclear surface low level waste disposal facility

    International Nuclear Information System (INIS)

    2001-01-01

    The Drigg site, owned and operated by BNFL, is the UK's principal site for the disposal of low level radioactive waste. The site has operated since 1959 and receives wastes from a wide range of sources including nuclear power stations, nuclear fuel cycle facilities, isotope manufacturing sites, universities, general industry and cleanup of historically contaminated sites. Disposals until the late 1980s were solely by tipping essentially loose wastes into excavated trenches. More recently, trench disposals have been phased out in preference to emplacement of containerised, conditioned wastes in concrete vaults. The standardised wasteform consists of high force compacted (or non-compactable) waste immobilised within 20 m 3 steel overpack containers by the addition of cementitious grout. Larger items of wastes are grouted directly, in situ in the vault. The disposal trenches have been completed with an interim cap, as will the vaults when filled. It is currently estimated that sufficient capacity remains at Drigg for disposals to continue until at least 2050. Post-operations it is planned that the site will enter a phase including shut down of operational facilities, emplacement of long term site closure features including a final closure cap and then to an institutional management phase. Planning has therefore been carried out as to the strategy for eventual closure of the site. This closure strategy is also underpinned by an engineering evaluation studies programme to develop and evaluate appropriate closure measures including assessment of the long term performance of such measures. This appendix summarizes some of this work

  14. Analysis of station blackout accident at the nuclear power plant; Analiza gubitka svih izmjenichnih izvora napajanja u NE

    Energy Technology Data Exchange (ETDEWEB)

    Bencik, V [Elektrotehnichki Inst. Rade Koncar, Zagreb (Yugoslavia); Kozaric, M [Zagreb Univ. (Yugoslavia). Elektrotehnicki Fakultet

    1990-07-01

    In 1986 the US NRC published a proposed rule making to tighten the requirements on nuclear plants with regard to their ability to deal safely with a total loss of all a-c electric power, both from external and internal sources of supply. The proposed rule would require all licensees and applicants to: 1. Assess the capability of their plants to cope with a total loss all a-c power(that is, determine the amount of time the plant could maintain core cooling and containment integrity with a-c power unavailable); 2. Have procedures and training to cope with such an event; 3. Make modification, if necessary, to cope with an acceptable minimum duration loss of all a-c power. A total loss of all a-c electric power has been identified as an 'unresolved safety issue' and subjected to considerably study. The article presents an idea to resolve this issue. (author)

  15. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

    The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station's responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project

  16. Fire Stations

    Data.gov (United States)

    Department of Homeland Security — Fire Stations in the United States Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their...

  17. Tobruk power station

    Energy Technology Data Exchange (ETDEWEB)

    Boergardts, B

    1978-01-01

    In February of 1975, the Electricity Corporation Benghazi (ECB) awarded a contract for the construction of a turnkey power station and seawater desalination plant in Tobruk, Libya to a consortium under the leadership of BBC Mannheim. This power station has an output of 129 MW and supplies about 24,000 m/sup 3/ of drinking water daily. It went into operation in 1977, two and a half years after the contract was awarded.

  18. Process for limiting the effects of operating faults in atomic power stations and plant to carry out the process

    International Nuclear Information System (INIS)

    Kudryavzev, B.K.; Svez, A.J.; Bulynin, V.D.; Butareev, B.A.; Kamsky, N.S.; Kosenko, V.P.; Kapitanov, A.M.; Basilov, V.A.

    1985-01-01

    The reactor plant operated with high temperature water surrounded with an airtight containment and with a multi-loop design includes a condensation device for the steam generated during faults. The condensation device contains an injector, cooling container and condensate collecting container. The injector has a supersonic nozzle, through which the steam/air mixture produced is introduced. (DG) [de

  19. Results of the 6th regular inspection of No. 1 plant in Mihama Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The 6th periodical inspection on Unit 1 in the Mihama Power Station was made for the period of July to December 1984. Inspection was made in the following: reactor proper, reactor cooling system, instrumentation and control system, radiation control facility, etc. By external appearance observation, disassembly, performance test, etc. there were observed no abnormalities. Personnel radiation exposure doses during the inspection were below the permissible level. The following modification etc. works were done in the periodical inspection: replacement of the accumulator safety valve, replacement of the out-reactor nuclear instrumentation panel, installation of accident-time monitors, replacement of the control-rod cluster guide tube support pins, alteration in the fuel enrichment. (Mori, K.)

  20. Results from trialling aqueous NH{sub 3} based post combustion capture in a pilot plant at Munmorah power station. Desorption

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Hai; Morgan, Scott; Allport, Andrew; Cottrell, Aaron; Do, Thong; McGregor, James; Wardhaugh, Leigh; Feron, Paul [CSIRO Energy Centre, Mayfield West, NSW (Australia)

    2013-07-01

    Australia's Commonwealth Scientific and Industrial Research Organization (CSIRO) and Delta Electricity have tested an aqueous ammonia based post combustion capture (PCC) process in a pilot plant at Munmorah black coal fired power station. This paper presents and discusses the experimental results obtained and primarily focuses on the desorption section. A high purity of CO{sub 2} product was obtained at the stripper gas outlet with the CO{sub 2} volumetric concentration generally between 99-100% and the remainder being water and NH{sub 3}. An increase in stripper pressure/temperature can lead to a decrease in NH{sub 3} concentration in the CO{sub 2} product. The NH{sub 3} concentration can be controlled within 200 ppm without wash at a stripper pressure of 850 kPa (the maximum pressure tested) at a stripper gas outlet temperatures of 20-25 C. The solid precipitation occurred in the stripper condenser and reflux lines. Due to the low ammonia content in the solution, CO{sub 2} content in the solution was low and generally more than 50% of regeneration energy was used to heat up the solvent under the pilot plant conditions. The lowest regeneration energy obtained from the pilot plant trials is 4-4.2 MJ/kg CO{sub 2} captured. The effect of various parameters including solvent flow-rate and stripper temperature/pressure in the solvent on the regeneration energy was investigated.

  1. Result of 'clean plant operation tactics' in Onagawa Nuclear Power Station No.1 unit during the first fuel cycle and the first maintenance outage

    International Nuclear Information System (INIS)

    Nukazuka, Hideo; Terada, Hideo; Morikawa, Yoshitake; Tomura, Susumu.

    1986-01-01

    On June 1, 1984, No.1 plant in Onagawa Nuclear Power Station started the commercial operation, and recorded the nonstop operation for 344 days. The parallel off was made on April 3, 1985, and the first regular inspection was carried out. On July 12, 1985, the regular inspection was completed, and thereafter, the second cycle operation has been smoothly continued. Special attention was paid to the measures for reducing radiation exposure, and the attainment of the clean plant was aimed at. As the measures for reducing radiation level, the strengtheining of purifying facilities, the suppression of crud generation, the adoption of low cobalt material and the strengthening of shielding were carried out. For shortening exposure time, the machinery and equipment were improved, paying attention to automation, remote operation and labor saving, and the improvement of reliability, maintainability and inspection. In addition to these design measures, in the construction, operation and regular inspection, the clean plant measures were taken. Very good results were obtained. (Kako, I.)

  2. Accident Analysis of Chinese CPR1000 in Response to Station Blackout

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Juyoul [FNC Technology Co., Yongin (Korea, Republic of); Cilliers, Anthonie [North-West University, Potchefstroom (South Africa)

    2016-10-15

    Stress tests required evaluation of the consequences of loss of safety functions from any initiating event (e.g., earthquake or flooding) causing loss of electrical power, including station blackout (SBO). The SBO scenario involves a loss of offsite power, failure of the redundant emergency diesel generators, failure of alternate current (AC) power restoration and the eventual degradation of the reactor coolant pump (RCP) seals resulting in a long term loss of coolant. Using PCTRAN/CPR1000, this study analyses the station blackout on a Chinese CPR1000 which is the most representative type reactor in terms of number of reactors, operating period, power capacity and geological distance from Korean Peninsula. Both the physical effects of the accidents as well as the releases of radioisotopes are calculated and discussed. Station blackout simulation was conducted in this study. The resulting effects seen are consistent with other stress test station blackout tests used utilizing licensed simulation codes. An exact comparison is however not possible as the plants on which the simulations was done vary greatly and the limitations of availability to Chinese FSAR. PCTRAN/CPR1000 is an extremely useful simulation package that provides engineers and scientists very accurate feedback to how a nuclear power plant would react as a whole under various plant conditions. It is able to do this extremely fast as well. As a training tool PCTRAN/CPR1000 provides hands-on experience with many of the primary plant operations and develops an intuitive understanding of the plant.

  3. Simulation with the MELCOR code of two severe accident sequences, Station Blackout and Small Break LOCA, for the Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    Valle Cepero, Reinaldo

    2004-01-01

    The results of the PSA-I applied to the Atucha I nuclear power plant (CNA I) determine the accidental sequences with the most influence related to the probability of the core reactor damage. Among those sequences are include, the Station Blackout and lost of primary coolant, combine with the failure of the emergency injection systems by pipe breaks of diameters between DN100 - DN25 or equivalent areas, Small LOCA. This paper has the objective to model and analyze the behavior of the primary circuit and the pressure vessel during the evolution of those two accidental sequences. It presented a detailed analysis of the main phenomena that occur from the initial moment of the accident to the failure moment of the pressure vessel and the melt material fall to the reactor cavity. Two sequences were taken into account, considering the main phenomena (core uncover, heating, fuel element oxidation, hydrogen generation, degradation and relocation of the melt material, failure of the support structures, etc.) and the time of occurrence, of those events will be different, if it is considered that both sequences will be developed in different scenarios. One case is an accident with the primary circuit to a high pressure (Station Blackout scenario) and the other with a early primary circuit depressurization due to the lost of primary coolant. For this work the MELCOR 1.8.5 code was used and it allows within a unified framework to modeling an extensive spectrum of phenomenology associated with the severe accidents. (author)

  4. Organic Rankine Cycle for Residual Heat to Power Conversion in Natural Gas Compressor Station. Part II: Plant Simulation and Optimisation Study

    Science.gov (United States)

    Chaczykowski, Maciej

    2016-06-01

    After having described the models for the organic Rankine cycle (ORC) equipment in the first part of this paper, this second part provides an example that demonstrates the performance of different ORC systems in the energy recovery application in a gas compressor station. The application shows certain specific characteristics, i.e. relatively large scale of the system, high exhaust gas temperature, low ambient temperature operation, and incorporation of an air-cooled condenser, as an effect of the localization in a compressor station plant. Screening of 17 organic fluids, mostly alkanes, was carried out and resulted in a selection of best performing fluids for each cycle configuration, among which benzene, acetone and heptane showed highest energy recovery potential in supercritical cycles, while benzene, toluene and cyclohexane in subcritical cycles. Calculation results indicate that a maximum of 10.4 MW of shaft power can be obtained from the exhaust gases of a 25 MW compressor driver by the use of benzene as a working fluid in the supercritical cycle with heat recuperation. In relation to the particular transmission system analysed in the study, it appears that the regenerative subcritical cycle with toluene as a working fluid presents the best thermodynamic characteristics, however, require some attention insofar as operational conditions are concerned.

  5. A study for the establishment of regulatory requirement and evaluation guide for station blackout in nuclear power plants

    International Nuclear Information System (INIS)

    Lim, J. H.; Koo, C. S.; Joo, W. P.; Oh, S. H.; Shin, W. K.

    1999-01-01

    The consequence of SBO event could be a severe accident unless AC power was restored within a proper time, because many safety systems depend upon AC power. Based on the severity, the SBO has been extensively studied since it was identified as Unresolved Safety Issue at USNRC. The resolution of those studies is a rule-making such as 10 CFR 50.63 and Regulatory Guide 1.155. But there is no regulatory requirements of SBO for an operating domestic nuclear power plant up to the present time. This tudy has established SBO rule(regulatory requirements and evaluation guides) for an operating PWR type of the operating nuclear power plants in Korea

  6. Assessing power plant impacts on fish populations at Northeast Utilities sites: winter flounder studies at Millstone Nuclear Power Station

    International Nuclear Information System (INIS)

    Lorda, E.; Danila, D.J.; Miller, J.D.; Bireley, L.E.; Jacobsen, P.M.

    1987-01-01

    An historical view is presented of the various impact assessment approaches used to study the winter flounder, including efforts to identify and quantify compensation and to model its population dynamics. This review illustrates the need for unbiased estimates of basic life history parameters and power plant related mortalities if compensatory mechanisms are to be understood and if impact assessments are to be meaningful. 67 references, 19 figures, 10 tables

  7. Calculations of a station blackout transient in a RBMK type nuclear power plant with the CATHARE code

    International Nuclear Information System (INIS)

    Niklaus, F.; Korteniemi, V.

    1996-01-01

    At the Department of Energy Technology at Lappeenranta University of Technology a CATHARE model of one unit of the St. Petersburg (RBMK) nuclear power plant has been generated. The investigations have been done in order to understand better the thermal-hydraulic behaviour of RBMK type reactors and in order to see how far the French thermal-hydraulic safety code CATHARE can predict the physical phenomena during various RBMK transients. (12 refs.)

  8. Inertial-confinement fusion central-station electric-power-generating plant. Final report, March 1, 1979-September 30, 1980

    International Nuclear Information System (INIS)

    Sucov, E.W.

    1981-01-01

    This report contains a complete description of the subsystems of the power plant including driver, driver power supply, pellet fabrication, pellet injection and aiming, data handling and control, evacuation, tritium and radwaste handling, first wall protection, first wall and structure, heat removal, tritium breeding and neutron shielding, maintenance and repair and balance of plant. In addition, it contains analytic support for the conceptual designs developed for each subsystem. The emphasis of the effort was on designing a viable reactor cavity and on solving the problems of interfacing the driver systems with the reactor cavity. The reactors generate 3500 MWt by irradiating a pellet whose gain is 175 from two opposite sides with a total of 2 MJ driver energy at a 10 Hz repetition rate. Because the nominal laser driver efficiency is 10% and that for the heavy ion driver is 30%, the net electric power outputs are 1207 MWe and 1346 MWe; the net plant conversion efficiencies are 28.1% and 31.3%; and the recirculating fractions are 22.9% and 14.0% respectively. The increased power output is, however, only one of the factors considered by utilities in performing a cost minimization analysis of competing power sources for system expansion. These other factors include: capital costs, cost of construction time, operating costs, environmental and licensing costs and reliability cost

  9. Inertial-confinement fusion central-station electric-power-generating plant. Final report, March 1, 1979-September 30, 1980

    International Nuclear Information System (INIS)

    Sucov, E.W.

    1981-01-01

    This report contains a complete description of the subsystems of the power plant including driver, driver power supply, pellet fabrication, pellet injection and aiming, data handling and control, evacuation, tritium and radwaste handling, first wall protection, first wall and structure, heat removal, tritium breeding and neutron shielding, maintenance and repair and balance of plant. In addition, it contains analytic support for the conceptual designs developed for each subsystem. The emphasis of the effort was on designing a viable reactor cavity and on solving the problems of interfacing the driver systems with the reactor cavity. The reactors generate 3500 NWt by irradiating a pellet whose gain is 175 from two opposite sides with a total of 2 MJ driver energy at a 10 Hz repetition rate. Because the nominal laser driver efficiency is 10% and that for the heavy ion driver is 30%, the net electric power outputs are 1207 MWe and 1346 MWe; the net plant conversion efficiencies are 28.1% and 31.3%; and the recirculating fractions are 22.9% and 14.0% respectively. The increased power output is, however, only one of the factors considered by utilities in performing a cost minimization analysis of competing power sources for system expansion. These other factors include: capital costs, cost of construction time, operating costs, environmental and licensing costs and reliability cost

  10. La Estructura del Dolo Eventual y las Nuevas Fenomenologías de Riesgo

    Directory of Open Access Journals (Sweden)

    Stefano Canestrari

    2004-01-01

    Full Text Available El texto aborda la discusión acerca de la estructura del dolo eventual, a partir de su fenomenología contemporánea, y el tratamiento que la jurisprudencia y doctrina alemana e italiana le han dado, particularmente en relación a supuestos relacionados con la transmisión de enfermedades de carácter sexual y de negativa de transfusión de sangre a menores por padres Testigos de Jehová. Se afirma que la doctrina dominante del consentimiento o aceptación no resuelve adecuadamente la fenomenología analizada y se plantea superar las dificultades que ello acarrea mediante la regulación legal del concepto de dolo eventual que se propone como conclusiónThe article discusses the structure of dolus eventualis (recklessness, considering its contemporary phenomenology, and the contributions of judicial decisions and legal scholarship in Germany and Italy. Especial consideration is given to the cases of sexually transmitted diseases and the refusal of blood transfusions to children by their Jehova's Witnesses parents. It is argued that the dominant doctrine of consent or acceptance does nor adequately resolve the analyzed phenomena, and a proposal is advanced towards a legal definition of the concept of recklessness.

  11. The impact of nuclear power stations and of a fuel reprocessing plant on the Rhone river and its prodelta

    International Nuclear Information System (INIS)

    Foulquier, L.; Garnier-Laplace, J.; Lambrechts, A.; Charmasson, S.; Pally, M.

    1992-01-01

    The Rhone, with its 6 nuclear sites (17 reactors of various types and a fuel reprocessing unit), presents a relevant example for comparing the impact of these various installations on the aquatic ecosystem. Artificial radioactivity (γ emitters, Pu, 3 H, 90 Sr...) and natural radioactivity are monitored in sediments and various living organisms in the river and its prodelta. A summary of the radioecological procedure is given and illustrated with examples selected from results obtained over the last fifteen years (data resulting from about 7500 samples taken up- and downstream of the installations and in the prodelta). The evolution of results obtained during this period by γ spectrometry on fish up- and downstream of the nuclear power station at Bugey and the Marcoule fuel reprocessing unit is presented. The role of aquatic vegetation as indicator of radiocontamination is also illustrated. The evolution in the concentration levels of γ emitting artificial radionuclides in sediments and mussels in the prodelta is commented on in order to show the global radioecological impact of the Rhone in the Mediterranean sea. The analyses presented show that it is possible to quantify the influence of each source term on the total artificial radioactivity of the compartments of the ecosystem. The source terms are atmospheric fallout from early nuclear weapon tests and of the Chernobyl accident, and liquid wastes of various composition from nuclear installations

  12. Operation of TUT Solar PV Power Station Research Plant under Partial Shading Caused by Snow and Buildings

    Directory of Open Access Journals (Sweden)

    Diego Torres Lobera

    2013-01-01

    Full Text Available A grid connected solar photovoltaic (PV research facility equipped with comprehensive climatic and electric measuring systems has been designed and built in the Department of Electrical Engineering of the Tampere University of Technology (TUT. The climatic measuring system is composed of an accurate weather station, solar radiation measurements, and a mesh of irradiance and PV module temperature measurements located throughout the solar PV facility. Furthermore, electrical measurements can be taken from single PV modules and strings of modules synchronized with the climatic data. All measured parameters are sampled continuously at 10 Hz with a data-acquisition system based on swappable I/O card technology and stored in a database for later analysis. The used sampling frequency was defined by thorough analyses of the PV system time dependence. Climatic and electrical measurements of the first operation year of the research facility are analyzed in this paper. Moreover, operation of PV systems under partial shading conditions caused by snow and building structures is studied by means of the measured current and power characteristics of PV modules and strings.

  13. Selective analysis of power plant operation on the Hudson River with emphasis on the Bowline Point Generating Station. Volume 2

    International Nuclear Information System (INIS)

    Barnthouse, L.W.; Cannon, J.B.; Christensen, S.G.

    1977-07-01

    Because of the location of the Bowline, Roseton, and Indian Point power generating facilities in the low-salinity zone of the Hudson estuary, operation of these plants with the present once-through cooling systems will adversely influence the fish populations that use the area for spawning and initial periods of growth and development. Recruitment rates and standing crops of several fish species may be lowered in response to the increased mortality caused by entrainment of nonscreenable eggs and larvae and by impingement of screenable young of the year. Entrainment and impingement data are particularly relevant for assessing which fish species have the greatest potential for being adversely affected by operation of Bowline, Roseton, and Indian Point with once-through cooling. These data from each of these three plants suggest that the six species that merit the greatest consideration are striped bass, white perch, tomcod, alewife, blueback herring, and bay anchovy. Two points of view are available for assessing the relative importance of the fish species in the Hudson River. From the fisheries point of view, the only two species of major importance are striped bass and shad. From the fish-community and ecosystem point of view, the dominant species, as determined by seasonal and regional standing crops (in numbers and biomass per hectare), are the six species most commonly entrained and impinged, namely, striped bass, white perch, tomcod, alewife, blueback herring, and anchovy

  14. Damage of reactor recirculation pump of No.3 plant in Fukushima No.2 Nuclear Power Station, Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1990-01-01

    No.3 plant in Fukushima No.2 Nuclear Power Station is a BWR plant with the rated output of 1100 MW, and as for the damage of its reactor recirculation pump, the investigation of the cause and the examination of countermeasures are advanced by the special committee. It is presumed that the submerged bearing ring of this pump caused the fatigue fracture due to the insufficient penetration in the fillet-welded part. The ring broke into pieces, and the main disk of the impeller was broken by the wear due to the pieces. Further, the damage of washers and the falling-off of bolts occurred. The metallic particles generated by wear were about 30 kg, and it is presumed that several kg of them adhered to fuel. Hereafter, the investigation of the cause will be continued, and the countermeasures for preventing the recurrence are examined. On January 1, 1989, the vibration of the pump increased, and the alarm was issued. However, the operation was continued carefully. On January 6, the vibration increased again, and on January 7, the reactor was stopped. The third regular inspection was begun on the same day, and the damage of the pump was found. (K.I.)

  15. Assessment of Trace Metal Ions on Raw and Treated Water in Dakahlia Drinking water Purification Stations .Behaviour of aluminium in water purification plants

    International Nuclear Information System (INIS)

    El-Defrawy, M.M.; El-Fadaly, H.; El-Zawawy, F.; Makia, D.

    1999-01-01

    The technology of improvement of water quality at water purification plants can be characterised by a large diversity of method and processes employed and by substantial differences in the design and process structure and equipment. The effect of operational parameters as ph, pre-, post- chlorination, coagulant index and mixing intensities on the level of some metal ions concentration in different sources of drinking water plants were studied. Results of the chemical analysis indicated that the dissolved and total AI 3+ concentration in treated water was much higher than raw water and sometimes with values over the international maximum limit. Much of the overall variation in aqua aluminium ion in treated water could be explained on the basis of ph, solubility, and filtration models efficiency, while ions as Fe 3+ and Mn 2+ were found within the acceptable limits. The data obtained indicated that relation between watershed inputs (CI 2 , H CI, alum dose) and output of soluble aluminium was not necessary simple and straightforward. The investigated water samples were collected from main stations and compact units in Dakahlia Governorate

  16. Analyses of occupational radiation exposure received at Gundremmingen nuclear power station, and its implications on the design of current and future power plants

    International Nuclear Information System (INIS)

    Eickelpasch, N.; Pfeiffer, K.W.; Peter, H.

    1977-01-01

    In 1976, the 250 MW Gundremmingen nuclear power station (KRB) completed its first decade of operation. The accumulated activity built-up due to corrosion products in the primary system, the condition of the plant and the methods of radiation work management determine the occupational exposure. The development and the general features of these three parameters are presented in detail. Job related exposure accounting has proven to be an effective means of radiation management. By this means up to 90% of the total radiation exposure could be traced with an accuracy of about 10 mrem. It is shown that up to 40% of the total exposure originate not from primary work but from associating jobs, e.g. work area preparation and testing efforts. Especially in this field a remarkable reduction of the occupational dose rate can be achieved by precise planning. The ten-year radiation protection history of KRB served as a design basis with the objective to reduce occupational radiation exposure. Examples are given how this influenced not only the design of relevant systems but also their accomodation, arrangement and shielding with regard to maintenance and repair work during reactor outage. Physical separation of the components and valves from the associated actuators, controls and instruments was provided to reduce personnel radiation exposure during plant operation. Provisions were also made to avoid contamination of the building atmosphere and to reduce the release of radioactivity via the ventilation systems

  17. Amtrak Stations

    Data.gov (United States)

    Department of Homeland Security — Updated database of the Federal Railroad Administration's (FRA) Amtrak Station database. This database is a geographic data set containing Amtrak intercity railroad...

  18. An examination of qualitative plant modelling as a basis for knowledge-based operator aids in nuclear power stations

    International Nuclear Information System (INIS)

    Herbert, M.; Williams, G.

    1986-01-01

    New qualitative techniques for representing the behaviour of physical systems have recently been developed. These allow a qualitative representation to be formally derived from a quantitative plant model. One such technique, Incremental Qualitative Analysis, is based on manipulating qualitative differential equations, called confluences, using sign algebra. This is described and its potential for reducing the amount of information presented to the reactor operator is discussed. In order to illustrate the technique, a specific example relating to the influence of failures associated with a pressurized water reactor pressuriser is presented. It is shown that, although failures cannot necessarily be diagnosed unambiguously, the number of possible failures inferred is low. Techniques for discriminating between these possible failures are discussed. (author)

  19. Space Station - Risks and vision

    Science.gov (United States)

    Pedersen, K.

    1986-01-01

    In assessing the prospects of the NASA Space Station program, it is important to take account of the long term perspective embodied in the proposal; its international participants are seen as entering a complex web of developmental and operational interdependence of indefinite duration. It is noted to be rather unclear, however, to what extent this is contemplated by such potential partners as the ESA, which has its own program goals. These competing hopes for eventual autonomy in space station operations will have considerable economic, technological, and political consequences extending well into the next century.

  20. PRESCHOOL SPEECH ARTICULATION AND NONWORD REPETITION ABILITIES MAY HELP PREDICT EVENTUAL RECOVERY OR PERSISTENCE OF STUTTERING

    Science.gov (United States)

    Spencer, Caroline; Weber-Fox, Christine

    2014-01-01

    Purpose In preschool children, we investigated whether expressive and receptive language, phonological, articulatory, and/or verbal working memory proficiencies aid in predicting eventual recovery or persistence of stuttering. Methods Participants included 65 children, including 25 children who do not stutter (CWNS) and 40 who stutter (CWS) recruited at age 3;9–5;8. At initial testing, participants were administered the Test of Auditory Comprehension of Language, 3rd edition (TACL-3), Structured Photographic Expressive Language Test, 3rd edition (SPELT-3), Bankson-Bernthal Test of Phonology-Consonant Inventory subtest (BBTOP-CI), Nonword Repetition Test (NRT; Dollaghan & Campbell, 1998), and Test of Auditory Perceptual Skills-Revised (TAPS-R) auditory number memory and auditory word memory subtests. Stuttering behaviors of CWS were assessed in subsequent years, forming groups whose stuttering eventually persisted (CWS-Per; n=19) or recovered (CWS-Rec; n=21). Proficiency scores in morphosyntactic skills, consonant production, verbal working memory for known words, and phonological working memory and speech production for novel nonwords obtained at the initial testing were analyzed for each group. Results CWS-Per were less proficient than CWNS and CWS-Rec in measures of consonant production (BBTOP-CI) and repetition of novel phonological sequences (NRT). In contrast, receptive language, expressive language, and verbal working memory abilities did not distinguish CWS-Rec from CWS-Per. Binary logistic regression analysis indicated that preschool BBTOP-CI scores and overall NRT proficiency significantly predicted future recovery status. Conclusion Results suggest that phonological and speech articulation abilities in the preschool years should be considered with other predictive factors as part of a comprehensive risk assessment for the development of chronic stuttering. PMID:25173455

  1. The nuclear power station

    International Nuclear Information System (INIS)

    Plettner, B.

    1987-04-01

    The processes taking place in a nuclear power plant and the dangers arising from a nuclear power station are described. The means and methods of controlling, monitoring, and protecting the plant and things that can go wrong are presented. There is also a short discourse on the research carried out in the USA and Germany, aimed at assessing the risks of utilising nuclear energy by means of the incident tree analysis and probability calculations. (DG) [de

  2. Shippingport station communications program

    International Nuclear Information System (INIS)

    Stote, J.J.

    1988-01-01

    The author discusses how the communications program for the Shippingport Atomic Power Station has a long history. It can be traced as far back as 1953, when the U.S. Atomic Energy Commission (AEC) awarded a contract to Westinghouse Electric to design the nuclear portion of a power plant for electric utility use. During May of the next year, President Eisenhower initiated groundbreaking ceremonies for the construction of the commercial atomic power plant at Shippingport, Pennsylvania

  3. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    1989-01-01

    This Topical Report is a synopsis of the decontamination of plant components and structures at the Shippingport Station Decommissioning Project (SSDP). The information is provided as a part of the Technology Transfer Program to document the preparation activities in support of the shipment of radioactive wastes and the unconditional release of the site and structural materials. 1 ref., 16 figs., 4 tabs

  4. The design of a real-time software system for the distributed control of power station plant

    International Nuclear Information System (INIS)

    Maples, G.C.

    1980-01-01

    As the application of computers to the control of generating plants widens, the problems of resourcing several individual projects over their life cycle can become formidable. This paper indicates the factors relevant to containing the resource requirements associated with software, and outlines the benefits of adopting a standard machine-independent software system which enables engineers rather than computer specialists to develop programs for specific projects. The design objectives which have led to the current development within C.E.G.B. of CUTLASS (Computer Users Technical Languages and Applications Software System) are then considered. CUTLASS is intended to be a standard software system applicable to the majority of future on-line computing projects in the area of generation and is appropriate to stand alone schemes or distributed schemes having a host/target configuration. The CUTLASS system software provides the necessary environment in which to develop, test, and run the applications software, the latter being created by the user by means of a set of engineer-orientated languages. The paper describes the various facilities within CUTALSS, i.e. those considered essential to meet the requirements of future process control applications. Concentrating on the system software relating to the executive functions, and the organisation of global data and communications within distributed systems. The salient features of the engineer-orientated language sets are also discussed. (auth)

  5. Systematic evaluation program review of NRC safety topic VII-2 associated with the electrical, instrumentation and control portions of the ESF system control logic and design for the Dresden Station, Unit II nuclear power plant

    International Nuclear Information System (INIS)

    St Leger-Barter, G.

    1980-11-01

    This report documents the technical evaluation and review of NRC Safety Topic VII-2, associated with the electrical, instrumentation, and control portions of the ESF system control logic and design for the Dresden Station Unit II nuclear power plant, using current licensing criteria

  6. Assessing the Eventual Publication of Clinical Trial Abstracts Submitted to a Large Annual Oncology Meeting.

    Science.gov (United States)

    Massey, Paul R; Wang, Ruibin; Prasad, Vinay; Bates, Susan E; Fojo, Tito

    2016-03-01

    Despite the ethical imperative to publish clinical trials when human subjects are involved, such data frequently remain unpublished. The objectives were to tabulate the rate and ascertain factors associated with eventual publication of clinical trial results reported as abstracts in the Proceedings of the American Society of Clinical Oncology (American Society of Clinical Oncology). Abstracts describing clinical trials for patients with breast, lung, colorectal, ovarian, and prostate cancer from 2009 to 2011 were identified by using a comprehensive online database (http://meetinglibrary.asco.org/abstracts). Abstracts included reported results of a treatment or intervention assessed in a discrete, prospective clinical trial. Publication status at 4-6 years was determined by using a standardized search of PubMed. Primary outcomes were the rate of publication for abstracts of randomized and nonrandomized clinical trials. Secondary outcomes included factors influencing the publication of results. A total of 1,075 abstracts describing 378 randomized and 697 nonrandomized clinical trials were evaluated. Across all years, 75% of randomized and 54% of nonrandomized trials were published, with an overall publication rate of 61%. Sample size was a statistically significant predictor of publication for both randomized and nonrandomized trials (odds ratio [OR] per increase of 100 participants = 1.23 [1.11-1.36], p publication (OR 2.37, p = .013; and 2.21, p = .01, respectively). Among nonrandomized studies, phase II trials were more likely to be published than phase I (p publication in randomized (OR 0.76 [0.38-1.52]; p = .441) or nonrandomized trials (OR 0.89 [0.61-1.29]; p = .532). This is the largest reported study examining why oncology trials are not published. The data show that 4-6 years after appearing as abstracts, 39% of oncology clinical trials remain unpublished. Larger sample size and advanced trial phase were associated with eventual publication; among randomized

  7. Preschool speech articulation and nonword repetition abilities may help predict eventual recovery or persistence of stuttering.

    Science.gov (United States)

    Spencer, Caroline; Weber-Fox, Christine

    2014-09-01

    In preschool children, we investigated whether expressive and receptive language, phonological, articulatory, and/or verbal working memory proficiencies aid in predicting eventual recovery or persistence of stuttering. Participants included 65 children, including 25 children who do not stutter (CWNS) and 40 who stutter (CWS) recruited at age 3;9-5;8. At initial testing, participants were administered the Test of Auditory Comprehension of Language, 3rd edition (TACL-3), Structured Photographic Expressive Language Test, 3rd edition (SPELT-3), Bankson-Bernthal Test of Phonology-Consonant Inventory subtest (BBTOP-CI), Nonword Repetition Test (NRT; Dollaghan & Campbell, 1998), and Test of Auditory Perceptual Skills-Revised (TAPS-R) auditory number memory and auditory word memory subtests. Stuttering behaviors of CWS were assessed in subsequent years, forming groups whose stuttering eventually persisted (CWS-Per; n=19) or recovered (CWS-Rec; n=21). Proficiency scores in morphosyntactic skills, consonant production, verbal working memory for known words, and phonological working memory and speech production for novel nonwords obtained at the initial testing were analyzed for each group. CWS-Per were less proficient than CWNS and CWS-Rec in measures of consonant production (BBTOP-CI) and repetition of novel phonological sequences (NRT). In contrast, receptive language, expressive language, and verbal working memory abilities did not distinguish CWS-Rec from CWS-Per. Binary logistic regression analysis indicated that preschool BBTOP-CI scores and overall NRT proficiency significantly predicted future recovery status. Results suggest that phonological and speech articulation abilities in the preschool years should be considered with other predictive factors as part of a comprehensive risk assessment for the development of chronic stuttering. At the end of this activity the reader will be able to: (1) describe the current status of nonlinguistic and linguistic predictors for

  8. Diagnosis, Surgical Treatment, Recovery, and Eventual Necropsy of a Leopard (Panthera pardus with Thyroid Carcinoma

    Directory of Open Access Journals (Sweden)

    Ashley Malmlov

    2014-01-01

    Full Text Available An 18-year-old, male, castrated, captive-born leopard (Panthera pardus presented to Colorado State University’s Veterinary Teaching Hospital with a two-week history of regurgitation. Thoracic radiographs and ultrasound revealed a well-differentiated cranioventral mediastinal mass measuring 7.5 × 10 × 5.5 cm, impinging the esophagus. A sternotomy followed by mass excision was performed. The mass was diagnosed as an ectopic thyroid carcinoma. The leopard recovered from surgery with minimal complications and returned to near-normal activity levels for just under 6 months before rapidly declining. He had an acute onset of severe dyspnea and lethargy and was euthanized. On postmortem examination the tumor was found to involve the lung, liver, thyroid, parietal pleura, bronchial lymph nodes, and the internal intercostal muscles. This case report describes the history, diagnosis, surgical treatment, postoperative care, and recovery as well as the eventual decline, euthanasia, and necropsy of a leopard with thyroid carcinoma. When compared to thyroid carcinomas of domestic animals, the leopard’s disease process more closely resembles the disease process seen in domestic canines compared to domestic cats.

  9. K. Schmitt’s Theory of Partisan: Socio - Political Eventuality of Partisan

    Directory of Open Access Journals (Sweden)

    Mihail Petrovich Ostromenskij

    2016-01-01

    Full Text Available Eventual socio-political conditions of the appearance of a partisan are considered. It is shown that the appearance of the partisan becomes possible when the socio-political uncertainty in the state and social anomie in society caused serious set into question the legitimacy of the sovereign. In such circumstances, falling value of public institutions, the rule of law and the rules of the routine, but the role of the individual and adopt independent decisions, in each case, increases. And increasing the area of independent ad hoc decisions. Such conditions arise in the occupied territory, especially in a situation of the continuing war. Besides, here indigenous people without taking any illegal actions, from the point of view of both clashing sovereigns, it is struck in the rights. All this makes a real opportunity to show the political subjectivity of the citizen, even with low social status. The behavior of the occupied population can follow three models: expectations of the solution of the conflict between sovereigns and the subsequent acceptance of its results as due - absolute majority population, the active help to the occupying sovereign for the purpose of the statement new political - the collaborator, active opposition of the occupying authority for the purpose of return former political - the partisan.

  10. Verification experiment on the downblending of high enriched uranium (HEU) at the Portsmouth Gaseous Diffusion Plant. Digital video surveillance of the HEU feed stations

    International Nuclear Information System (INIS)

    Martinez, R.L.; Tolk, K.; Whiting, N.; Castleberry, K.; Lenarduzzi, R.

    1998-01-01

    As part of a Safeguards Agreement between the US and the International Atomic Energy Agency (IAEA), the Portsmouth Gaseous Diffusion Plant, Piketon, Ohio, was added to the list of facilities eligible for the application of IAEA safeguards. Currently, the facility is in the process of downblending excess inventory of HEU to low enriched uranium (LEU) from US defense related programs for commercial use. An agreement was reached between the US and the IAEA that would allow the IAEA to conduct an independent verification experiment at the Portsmouth facility, resulting in the confirmation that the HEU was in fact downblended. The experiment provided an opportunity for the DOE laboratories to recommend solutions/measures for new IAEA safeguards applications. One of the measures recommended by Sandia National Laboratories (SNL), and selected by the IAEA, was a digital video surveillance system for monitoring activity at the HEU feed stations. This paper describes the SNL implementation of the digital video system and its integration with the Load Cell Based Weighing System (LCBWS) from Oak Ridge National Laboratory (ORNL). The implementation was based on commercially available technology that also satisfied IAEA criteria for tamper protection and data authentication. The core of the Portsmouth digital video surveillance system was based on two Digital Camera Modules (DMC-14) from Neumann Consultants, Germany

  11. Geodatabase of environmental information for Air Force Plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas, 1990-2004

    Science.gov (United States)

    Shah, Sachin D.; Quigley, Sean M.

    2005-01-01

    Air Force Plant 4 (AFP4) and adjacent Naval Air Station-Joint Reserve Base (NAS-JRB) at Fort Worth, Tex., constitute a government-owned, contractor-operated (GOCO) facility that has been in operation since 1942. Contaminants from the facility, primarily volatile organic compounds (VOCs) and metals, have entered the groundwater-flow system through leakage from waste-disposal sites (landfills and pits) and from manufacturing processes (U.S. Air Force, Aeronautical Systems Center, 1995). The U.S. Geological Survey (USGS), in cooperation with the U.S. Air Force (USAF), Aeronautical Systems Center, Environmental Management Directorate (ASC/ENVR), developed a comprehensive database (or geodatabase) of temporal and spatial environmental information associated with the geology, hydrology, and water quality at AFP4 and NAS-JRB. The database of this report provides information about the AFP4 and NAS-JRB study area including sample location names, identification numbers, locations, historical dates, and various measured hydrologic data. This database does not include every sample location at the site, but is limited to an aggregation of selected digital and hardcopy data of the USAF, USGS, and various consultants who have previously or are currently working at the site.

  12. Radioactive effluents from nuclear power stations and nuclear fuel reprocessing plants in the European Community. Discharge data 1972-1976 radiological aspects

    International Nuclear Information System (INIS)

    Luykx, F.; Fraser, G.

    1978-04-01

    The report presents the available data on radioactive gaseous and liquid effluents discharged by nuclear power stations and nuclear fuel reprocessing plants in the European Community from 1972 to 1976. Discharges are expressed both in absolute terms and relative to the net production of electricity from the fuel. On the basis of the discharges recorded for 1976 the resulting maximum exposure of members of the population is quantified and compared with the dose limits prescribed by Euratom radiological protection standards and with the exposure resulting from natural radioactivity. It is concluded that there is no case in which a discharge could have given rise to an exposure exceeding the relevant prescribed limit. Not only did the possible maximum exposures incurred by individuals leave an appreciable safety margin relative to that limit but, for the vast majority of installations, they were comparable with or were considerably lower than the geographical and temporal variations in exposures resulting from natural radioactivity. Where environmental levels have been detectable the measured results have of course been used but, with few exceptions, the levels have remained less than the very low limits of detection currently possible. In general, where theoretical models are used to evaluate exposure, they are designed to give conservative results and hence it is likely that the true exposures are even less than those calculated

  13. Power station instrumentation

    International Nuclear Information System (INIS)

    Jervis, M.W.

    1993-01-01

    Power stations are characterized by a wide variety of mechanical and electrical plant operating with structures, liquids and gases working at high pressures and temperatures and with large mass flows. The voltages and currents are also the highest that occur in most industries. In order to achieve maximum economy, the plant is operated with relatively small margins from conditions that can cause rapid plant damage, safety implications, and very high financial penalties. In common with other process industries, power stations depend heavily on control and instrumentation. These systems have become particularly significant, in the cost-conscious privatized environment, for providing the means to implement the automation implicit in maintaining safety standards, improving generation efficiency and reducing operating manpower costs. This book is for professional instrumentation engineers who need to known about their use in power stations and power station engineers requiring information about the principles and choice of instrumentation available. There are 8 chapters; chapter 4 on instrumentation for nuclear steam supply systems is indexed separately. (Author)

  14. Patient and family physician preferences for care and communication in the eventuality of anthrax terrorism.

    Science.gov (United States)

    Kahan, Ernesto; Fogelman, Yacov; Kitai, Eliezer; Vinker, Shlomo

    2003-08-01

    The threat of bioterrorism consequent to the September 11, 2001 attack in the USA generated suggestions for improved medical response mainly through hospital preparedness. The aim of the present study was to investigate the impact of this period of tension on patients' first choice for care and for receiving relevant information, and on primary care doctors' feelings of responsibility in the eventuality of an anthrax attack. During October 11-31, 2001, 500 patients from 30 clinics throughout Israel were asked to complete a questionnaire on their awareness of the anthrax threat, measures taken to prepare for it, and preferred sources of care and information. Their 30 physicians, and an additional 20, completed a questionnaire on knowledge about anthrax and anthrax-related patient behaviours and clinic visits. The outstanding finding was the low rate (30%) of patients who chose the hospital emergency department as their first choice for care or information if they were worried about an anthrax attack or the media communicated that an attack was in progress. The other two-thirds preferred their family doctor or the health authorities. Most of the physicians (89%) felt it was their responsibility to treat anthrax-infected patients and that they should therefore be supplied with appropriate guidelines. This study suggests that in Israel, a country with a high degree of awareness of civil defence aspects, both patients and primary care doctors believe that family physicians should have a major role in the case of bioterrorist attacks. This must be seriously considered during formulation of relevant health services programmes.

  15. The evolution, etiology and eventualities of the global health security regime.

    Science.gov (United States)

    Hoffman, Steven J

    2010-11-01

    Attention to global health security governance is more important now than ever before. Scientists predict that a possible influenza pandemic could affect 1.5 billion people, cause up to 150 million deaths and leave US$3 trillion in economic damages. A public health emergency in one country is now only hours away from affecting many others. Using regime analysis from political science, the principles, norms, rules and decision-making procedures by which states govern health security are examined in the historical context of their punctuated evolution. This methodology illuminates the catalytic agents of change, distributional consequences and possible future orders that can help to better inform progress in this area. Four periods of global health security governance are identified. The first is characterized by unilateral quarantine regulations (1377-1851), the second by multiple sanitary conferences (1851-92), the third by several international sanitary conventions and international health organizations (1892-1946) and the fourth by the hegemonic leadership of the World Health Organization (1946-????). This final regime, like others before it, is challenged by globalization (e.g. limitations of the new International Health Regulations), changing diplomacy (e.g. proliferation of global health security organizations), new tools (e.g. global health law, human rights and health diplomacy) and shock-activated vulnerabilities (e.g. bioterrorism and avian/swine influenza). This understanding, in turn, allows us to appreciate the impact of this evolving regime on class, race and gender, as well as to consider four possible future configurations of power, including greater authority for the World Health Organization, a concert of powers, developing countries and civil society organizations. This regime analysis allows us to understand the evolution, etiology and eventualities of the global health security regime, which is essential for national and international health

  16. Technical evaluation report on the adequacy of station electric distribution system voltages for the Point Beach Nuclear Plant, Units 1 and 2. (Docket Nos. 50-266, 50-301)

    International Nuclear Information System (INIS)

    White, R.L.

    1983-01-01

    This report documents the technical evaluation of the adequacy of the station electric distribution system voltages for the Point Beach Nuclear Plant, Units 1 and 2. The evaluation is to determine if the onsite distribution system, in conjunction with the offsite power sources, has sufficient capacity to automatically start and operate all Class 1E loads within the equipment voltage ratings under certain conditions established by the Nuclear Regulatory Commission. For the worst case conditions study submitted by the licensee, it was shown that the station electric distribution system voltages would be adequate to start and operate 4160-volt and 480-volt Class 1E loads and their associated low voltage controls

  17. Daya Bay Nuclear Power Station operation and management indicators system

    International Nuclear Information System (INIS)

    Fang Chunfa

    2000-01-01

    Ever since the commercial operation of Daya Bay Nuclear Power Station (GNPS), dynamic objective management concept that features modern enterprises has been adopted by the station to manage all operational activities with the guidance of business plan. And some quantitative indicators have been employed in order to measure effectively the progress status of these operational activities. After several years' evolvement, a hierarchical and standard performance indicators system has been developed and is playing an active part in the plant's efforts towards top quartile of world nuclear power industry. Structured hierarchically with higher levels resolving into lower levels and lower levels committing to higher levels, the indicator system represents the corporate vision, WANO (World Association of Nuclear Operators) performance indicators, plant integrated indicators and departmental key indicators, covering such areas as safety, production, environment, human resource and cost control. The indicator system not only reflects performance-centered management concept, but also shows the controllability of the whole operational process of the station. Indicators of a certain level serve as both early warnings to superior indicators (lagging indicators in this case) and effects to inferior indicators (leading indicators in this case). The dynamic status of these indicators, numbered more than 230, will eventually be fed back to the business plan and realized through daily work of every branch, and even every member of the workforce. With the indicator system as a quantitative management tool, and an effective tracking system, GNPS has achieved great success in self-assessment, objective definition, improvement follow up, resource re-allocation, and management-staff communication. Periodic plant performance assessment is performed through spider chart and other pictorial diagrams. Indicators are displayed at the plant entrance, offices, Main Control Room and SIS network

  18. Station Capacity

    DEFF Research Database (Denmark)

    Landex, Alex

    2011-01-01

    the probability of conflicts and the minimum headway times into account. The last method analyzes how optimal platform tracks are used by examining the arrival and departure pattern of the trains. The developed methods can either be used separately to analyze specific characteristics of the capacity of a station......Stations are often limiting the capacity of railway networks. This is due to extra need of tracks when trains stand still, trains turning around, and conflicting train routes. Although stations are often the capacity bottlenecks, most capacity analysis methods focus on open line capacity. Therefore...... for platform tracks and the probability that arriving trains will not get a platform track immediately at arrival. The third method is a scalable method that analyzes the conflicts in the switch zone(s). In its simplest stage, the method just analyzes the track layout while the more advanced stages also take...

  19. UMTS Network Stations

    Science.gov (United States)

    Hernandez, C.

    2010-09-01

    The weakness of small island electrical grids implies a handicap for the electrical generation with renewable energy sources. With the intention of maximizing the installation of photovoltaic generators in the Canary Islands, arises the need to develop a solar forecasting system that allows knowing in advance the amount of PV generated electricity that will be going into the grid, from the installed PV power plants installed in the island. The forecasting tools need to get feedback from real weather data in "real time" from remote weather stations. Nevertheless, the transference of this data to the calculation computer servers is very complicated with the old point to point telecommunication systems that, neither allow the transfer of data from several remote weather stations simultaneously nor high frequency of sampling of weather parameters due to slowness of the connection. This one project has developed a telecommunications infrastructure that allows sensorizadas remote stations, to send data of its sensors, once every minute and simultaneously, to the calculation server running the solar forecasting numerical models. For it, the Canary Islands Institute of Technology has added a sophisticated communications network to its 30 weather stations measuring irradiation at strategic sites, areas with high penetration of photovoltaic generation or that have potential to host in the future photovoltaic power plants connected to the grid. In each one of the stations, irradiance and temperature measurement instruments have been installed, over inclined silicon cell, global radiation on horizontal surface and room temperature. Mobile telephone devices have been installed and programmed in each one of the weather stations, which allow the transfer of their data taking advantage of the UMTS service offered by the local telephone operator. Every minute the computer server running the numerical weather forecasting models receives data inputs from 120 instruments distributed

  20. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement

    Science.gov (United States)

    Wasko, Frank

    Traditionally, electric utilities have been slow to change and very bureaucratic in nature. This culture, in and of itself, has now contributed to a high percentage of United States electric utilities operating uneconomical nuclear plants (Crooks, 2014). The economic picture behind owning and operating United States nuclear plants is less than favorable for many reasons including rising fuel, capital and operating costs (EUCG, 2012). This doctoral dissertation is specifically focused on life without nuclear power. The purpose of this dissertation is to create a model and guide that will provide electric utilities who currently operate or will operate uneconomical nuclear plants the opportunity to economically assess whether or not their nuclear plant should be retired. This economic assessment and stakeholder analysis will provide local government, academia and communities the opportunity to understand how Southern California Edison (SCE) embraced system upgrade import and "voltage support" opportunities to replace "base load" generation from San Onofre Nuclear Generating Station (SONGS) versus building new replacement generation facilities. This model and guide will help eliminate the need to build large replacement generation units as demonstrated in the SONGS case analysis. The application of The Nuclear Power Retirement Model and Guide will provide electric utilities with economic assessment parameters and an evaluation assessment progression needed to better evaluate when an uneconomical nuclear plant should be retired. It will provide electric utilities the opportunity to utilize sound policy, planning and development skill sets when making this difficult decision. There are currently 62 nuclear power plants (with 100 nuclear reactors) operating in the United States (EIA, 2014). From this group, 38 are at risk of early retirement based on the work of Cooper (2013). As demonstrated in my model, 35 of the 38 nuclear power plants qualify to move to the economic

  1. Development of the stationary state and simulation of an accident severe stage type station blackout with the MELCOR code version 1.8.6 for the nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Mugica R, C. A.; Godinez S, V.

    2011-11-01

    Considering the events happened since the 11 March of 2011, in Japan, where an earthquake of 9.1 grades Ritcher of intensity and a later tsunami impacted in an important way the operation of a nuclear power plant located in the Fukushima, Japan; damaging and disabling their cooling systems and injection of emergency water due to the total loss of electric power (commonly denominated Station Blackout), is eminent the analysis of this stage type that took to the nuclear power plant to conditions of damage to the core and explosions generation by hydrogen concentrations in the reactor building. In this work an analysis of a stage type station blackout is presented, using the model of the nuclear power plant of Laguna Verde starting of the stationary state. The analysis is carried out using the MELCOR code (Methods for Estimation of Leakages and Consequences of Releases) version 1.8.6 whose purpose is to model the accidents progression for light water reactors. The obtained results are qualitatively similar to the events observed in the Fukushima nuclear power plant even though limitations exist to achieve a precise simulation of the events happened in Japan, such as the information flow of the chronology of the operator actions, as well as of the characteristic design of the power plant, volumes in cavities and rooms, water/cooling inventories, interconnected systems and their own emergency procedures or guides for the administration of severe accidents among others. (Author)

  2. Alternative cooling water flow path for RHR heat exchanger and its effect on containment response during extended station blackout for Chinshan BWR-4 plant

    Energy Technology Data Exchange (ETDEWEB)

    Yuann, Yng-Ruey, E-mail: ryyuann@iner.gov.tw

    2016-04-15

    Highlights: • Motivating alternative RHR heat exchanger tube-side flow path and determining required capacity. • Calculate NSSS and containment response during 24-h SBO for Chinshan BWR-4 plant. • RETRAN and GOTHIC models are developed for NSSS and containment, respectively. • Safety relief valve blowdown flow and energy to drywell are generated by RETRAN. • Analyses are performed with and without reactor depressurization, respectively. - Abstract: The extended Station Blackout (SBO) of 24 h has been analyzed with respect to the containment response, in particular the suppression pool temperature response, for the Chinshan BWR-4 plant of MARK-I containment. The Chinshan plant, owned by Taiwan Power Company, has twin units with rated core thermal power of 1840 MW each. The analysis is aimed at determining the required alternative cooling water flow capacity for the residual heat removal (RHR) heat exchanger when its tube-side sea water cooling flow path is blocked, due to some reason such as earthquake or tsunami, and is switched to the alternative raw water source. Energy will be dissipated to the suppression pool through safety relief valves (SRVs) of the main steam lines during SBO. The RETRAN model is used to calculate the Nuclear Steam Supply System (NSSS) response and generate the SRV blowdown conditions, including SRV pressure, enthalpy, and mass flow rate. These conditions are then used as the time-dependent boundary conditions for the GOTHIC code to calculate the containment pressure and temperature response. The shaft seals of the two recirculation pumps are conservatively assumed to fail due to loss of seal cooling and a total leakage flow rate of 36 gpm to the drywell is included in the GOTHIC model. Based on the given SRV blowdown conditions, the GOTHIC containment calculation is performed several times, through the adjustment of the heat transfer rate of the RHR heat exchanger, until the criterion that the maximum suppression pool temperature

  3. Correlation of Admission Metrics with Eventual Success in Mathematics Academic Performance of Freshmen in AMAIUB's Business Curricula

    Science.gov (United States)

    Calucag, Lina S.; Talisic, Geraldo C.; Caday, Aileen B.

    2016-01-01

    This is a correlational study research design, which aimed to determine the correlation of admission metrics with eventual success in mathematics academic performance of the admitted 177 first year students of Bachelor of Science in Business Informatics and 59 first year students of Bachelor of Science in International Studies. Using Pearson's…

  4. Torness: proposed nuclear power station

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

  5. Comparison of wastewater plant of Nova Pampulha, with an UASB reactor, with another ten brazilian stations; Comparacion de la EDAR de Nova Pampulha, dotada de reactor UASB, con otras diez plantas brasilenas

    Energy Technology Data Exchange (ETDEWEB)

    Barrosa Correa, S. M. B.; Ruiz, E.; Romero, F.

    2004-07-01

    This work is based on data of the wastewater plant of Nova Pampulha with an UASB reactor. The objective of this research was focussed in the comparison of this plant with another ten brazilian stations provided with different depuration techniques. Firstly the graphical comparison of average operational data suggest analogies between influents (less suspended solids in the Nova Pampulha), effluent (more suspended solids and bacteria in the same station) and alimentation's (smaller for suspended solids and bacteria in Nova Pampulha, where there is also an increase in alkalinity). Cluster analysis, made with percentages of elimination of constituents in the eleven stations and shown as dendrograms, was chosen as the second comparative method. A third comparison was affected by multiple linear regression for obtaiming mathematical models from the eliminations of constituents, with statistical significance at level of the 95% confidence, using as possible independent variables the flows and the concentrations of influents. The explanations of the variances of data by the calculated equations is in the range 46 to 91%. As a general conclusion, it can be said that a well operated UASB reactor may be a satisfactory technique for wastewater treatment and well adapted to climatological Brazilian conditions. (Author) 14 refs.

  6. Shippingport Station decommissioning project overview

    International Nuclear Information System (INIS)

    Schreiber, J.J.

    1985-01-01

    The U.S. Department of Energy is in the process of decommissioning the Shippingport Atomic Power Station located on the Ohio River, 30 miles northwest of Pittsburgh, Pennsylvania. The Shippingport Station is the first commercial size nuclear power plant to undergo decommissioning in the United Staes. The plant is located on approximately 7 acres of land owned by the Duquesne Light Company (DLC) and leased to the U.S. Government. DLC operates two nuclear power plants, Beaver Valley 1 and 2, located immediately adjacent to the site and the Bruce Mansfield coal-fired power plant is also within the immediate area. The Station was shutdown in October, 1982. Defueling operations began in 1983 and were completed by September, 1984. The Shippingport Station consists of a 275' x 60' fuel handling building containing the reactor containment chamber, the service building, the turbine building, the radioactive waste processing building, the administration building and other smaller support buildings. The Station has four coolant loops and most of the containment structures are located below grade. Structures owned by the U.S. Government including the fuel handling building, service building, contaminated equipment room, the boiler chambers, the radioactive waste processing building and the decontamination and laydown buildings will be dismantled and removed to 3 feet below grade. The area will then be filled with clean soil and graded. The turbine building, testing and training building and the administration building are owned by DLC and will remain

  7. Innovations in PHWR design, integration of nuclear power stations into power systems and role of small size nuclear power plants in a developing country

    International Nuclear Information System (INIS)

    Mehta, S.K.; Kakodkar, A.; Balakrishnan, M.R.; Ray, R.N.; Murthy, L.G.K.; Chamany, B.F.; Kati, S.L.

    1977-01-01

    PHWR concept of thermal reactors has been considered with a view to exploiting the limited resources of natural uranium and keeping in mind the projected nuclear power programme covering fast breeder reactors. Experience in engineering of current PHWR units in India, gradual build up of necessary infrastructure and operational experience with one unit, have helped in building up design and technological capability in the country. The R and D facilities have been so planned that additional data required for the design of bigger reactor units (i.e.500/600 MWe) could be generated with minimal augmentation. Satisfactory operation of a nuclear power station demands certain prerequisites from the connected power system. The grid should have load patterns suitable for base load operation of these stations, should be stiff so far as voltage and frequency fluctuations are concerned and should have high reliability. A typical power grid in this country is characterised by heavy loads during peak hours and very light loads during night. Regional grids are of small size and the few interconnections existing between the regional grids consist of weak tie lines. Amongst all types of the power stations, it is the nuclear system which undergoes maximum strain and economic penalty while operating when connected to such a power system. Consistent with the above, phase installation of small-size power reactor units of about 200 MWe capacity may facilitate setting up of larger unit sizes at a later date. The effect of any possible reduction in the capital cost of a larger unit power station will enable the power station to partially meet the demand of the more productive types of loads. This paper deals with some of the major design changes that are being incorporated in the PHWR type power reactors currently being set up and the research and development back-up required for the purpose. Since the unit sizes of the power reactors presently contemplated are small compared to nuclear

  8. MELCOR simulation of long-term station blackout at Peach Bottom

    International Nuclear Information System (INIS)

    Madni, I.K.

    1990-01-01

    This paper presents the results from MELCOR (Version 1.8BC) calculations of the Long-Term Station Blackout Accident Sequence, with failure to depressurize the reactor vessel, at the Peach Bottom (BWR Mark I) plant, and presents comparisons with Source Term Code Package (STCP) calculations of the same sequence. This sequence assumes that batteries are available for six hours following loss of all power to the plant. Following battery failure, the reactor coolant system (RCS) inventory is boiled off through the relief valves by continued decay heat generation. This leads to core uncovery, heatup, clad oxidation, core degradation, relocation, and, eventually, vessel failure at high pressure. STCP has calculated the transient out to 13.5 hours after core uncovery. The results include the timing of key events, pressure and temperature response in the reactor vessel and containment, hydrogen production, and the release of source terms to the environment. 12 refs., 23 figs., 3 tabs

  9. On results of measurement and method of behavior analysis for land slide protection wall in excavation works for main building foundation of No.2 plant in Kashiwazaki-Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Otsuki, Hideo; Tsuchi, Hiroyuki; Nishioka, Toshimichi

    1987-01-01

    Tokyo Electric Power Co. has been constructing the nuclear power station having 8 million kW capacity of seven BWR plants in the site of about 4.2 million m 2 in Niigata Prefecture. No.1 BWR plant of 1100 MWe output started the operation in September, 1985. As a rule, the important structures in nuclear power stations such as a reactor building and a turbine building are to be directly supported on bedrocks, and in this case, on the mudstone of Nishiyama strata. As this Nishiyama strata exists in large depth, the excavation works for the foundations of buildings are to be carried out by installing large scale land slide protection walls. In this report, among the excavation works for the main building foundation of No.2 plant, the results of examining the behavior of the land slide protection wall installed in soft rock ground based on the results of measurement of vertical excavation by land slide protection method and the techniques of its analysis are described. The geological features, the design of land slide protection walls, the measurement of the land slide protection walls and surrounding ground and the results, and the examination of the analysis methods by a beam model and FEM are reported. (Kako, I.)

  10. Machine Learning Algorithms Utilizing Quantitative CT Features May Predict Eventual Onset of Bronchiolitis Obliterans Syndrome After Lung Transplantation.

    Science.gov (United States)

    Barbosa, Eduardo J Mortani; Lanclus, Maarten; Vos, Wim; Van Holsbeke, Cedric; De Backer, William; De Backer, Jan; Lee, James

    2018-02-19

    Long-term survival after lung transplantation (LTx) is limited by bronchiolitis obliterans syndrome (BOS), defined as a sustained decline in forced expiratory volume in the first second (FEV 1 ) not explained by other causes. We assessed whether machine learning (ML) utilizing quantitative computed tomography (qCT) metrics can predict eventual development of BOS. Paired inspiratory-expiratory CT scans of 71 patients who underwent LTx were analyzed retrospectively (BOS [n = 41] versus non-BOS [n = 30]), using at least two different time points. The BOS cohort experienced a reduction in FEV 1 of >10% compared to baseline FEV 1 post LTx. Multifactor analysis correlated declining FEV 1 with qCT features linked to acute inflammation or BOS onset. Student t test and ML were applied on baseline qCT features to identify lung transplant patients at baseline that eventually developed BOS. The FEV 1 decline in the BOS cohort correlated with an increase in the lung volume (P = .027) and in the central airway volume at functional residual capacity (P = .018), not observed in non-BOS patients, whereas the non-BOS cohort experienced a decrease in the central airway volume at total lung capacity with declining FEV 1 (P = .039). Twenty-three baseline qCT parameters could significantly distinguish between non-BOS patients and eventual BOS developers (P machine), we could identify BOS developers at baseline with an accuracy of 85%, using only three qCT parameters. ML utilizing qCT could discern distinct mechanisms driving FEV 1 decline in BOS and non-BOS LTx patients and predict eventual onset of BOS. This approach may become useful to optimize management of LTx patients. Copyright © 2018 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

  11. Characterizing toxic emissions from a coal-fired power plant demonstrating the AFGD ICCT Project and a plant utilizing a dry scrubber/baghouse system: Bailly Station Units 7 and 8 and AFGD ICCT Project. Final report. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Dismukes, E.B.

    1994-10-20

    This report describes results of assessment of the risk of emissions of hazardous air pollutants at one of the electric power stations, Bailly Station, which is also the site of a Clean Coal Technology project demonstrating the Pure Air Advanced Flue Gas Desulfurization process (wet limestone). This station represents the configuration of no NO{sub x} reduction, particulate control with electrostatic precipitators, and SO{sub 2} control with a wet scrubber. The test was conducted September 3--6, 1993. Sixteen trace metals were determined along with 5 major metals. Other inorganic substances and organic compounds were also determined.

  12. Thermodynamic effects when utilizing waste heat from condensation in cases of a reduced vacuum in steam turbine plants of thermal power stations, to provide heat at low temperatures

    Energy Technology Data Exchange (ETDEWEB)

    Vasiljevic, N.; Savic, B.; Stojakovic, M.

    1986-01-01

    There is an interesting variant of cogeneration in the steam turbine system of a thermal power plant, i.e. the utilisation of the waste heat of condensation with a reduced vacuum without reconstruction of the thermal power plant. The thermodynamic effect in cogeneration was calculated in consideration of the dynamics of heat consumption. This cogeneration process has the advantage of saving primary energy without reconstruction of the thermal power plant.

  13. Local control stations

    International Nuclear Information System (INIS)

    Brown, W.S.; Higgins, J.C.; Wachtel, J.A.

    1993-01-01

    This paper describes research concerning the effects of human engineering design at local control stations (i.e., operator interfaces located outside the control room) on human performance and plant safety. The research considered both multifunction panels (e.g. remote shutdown panels) as well as single-function interfaces (e.g., valves, breakers, gauges, etc.). Changes in performance shaping factors associated with variations in human engineering at LCSs were estimated based on expert opinion. By means of a scaling procedure, these estimates were used to modify the human error probabilities in a PRA model, which was then employed to generate estimates of plant risk and scoping-level value/impact ratios for various human engineering upgrades. Recent documentation of human engineering deficiencies at single-function LCSs was also reviewed, and an assessment of the current status of LCSs with respect to human engineering was conducted

  14. The study of specific activity and effect of gamma ray from natural radionuclide to the environment outside Sultan Abdul Aziz Plant Station, Kapar, Klang, Selangor

    International Nuclear Information System (INIS)

    Wan Amar Fikri Wan Ali

    2012-01-01

    Waste resulting from coal combustion process can result in increasing the specific activity of natural radionuclide such as 238 U, 232 Th , 226 Ra and 40 K. Following combustion, radionuclide focused on fly ash, some escape the filtration system in the chimney that causes the gamma ray exposure dose increases. The objective of this study was to calculate the specific activity of natural radionuclide and identifying the gamma ray exposure dose outside the Stesen Janakuasa Elektric Station of Sultan Abdul Aziz further examine the risk of gamma ray exposure dose and specific activity of natural radionuclide to the ecosystem because the station is located close to residential areas and local residents migratory bird stopover. The samples studied are soil, water and sediment that are outside the station. Samples taken with the correct procedures then treated and stored about a month before counting. Gamma ray exposure dose for the seven stations studied are between 0.330 μSv/ h - 1.20 μSv/ h. While the range of specific activities obtained for the 40 K, 238 U, 232 Th and 226 Ra were 201 Bq/ kg - 468 Bq/ kg, 0.480 Bq/ kg - 2.57 Bq/ kg, 12.9 Bq/ kg - 74.5 Bq/ kg and 6.64 Bq/ kg - 11.7 Bq/ kg. While the sediment samples were 216 Bq/ kg - 465 Bq/ kg, 18.1 Bq/ kg - 4.43 Bq/ kg, 24.8 Bq/ kg - 65.3 Bq/ kg, 8.53 Bq/ kg - 11.2 Bq/ kg. For water samples, the specific range of their specific activities are 10.5 Bq/ L - 12.1 Bq/ L, 1.40 Bq/ L - 1.63 Bq/ L, 1.57 Bq/ L - 1.65 Bq/ L and 0 Bq/ L - 1.14 Bq/ L. (author)

  15. NRC's object-oriented simulator instructor station

    International Nuclear Information System (INIS)

    Griffin, J.I.; Griffin, J.P.

    1995-06-01

    As part of a comprehensive simulator upgrade program, the simulator computer systems associated with the Nuclear Regulatory Commission's (NRC) nuclear power plant simulators were replaced. Because the original instructor stations for two of the simulators were dependent on the original computer equipment, it was necessary to develop and implement new instructor stations. This report describes the Macintosh-based Instructor Stations developed by NRC engineers for the General Electric (GE) and Babcock and Wilcox (B and W) simulators

  16. Controversial power station

    International Nuclear Information System (INIS)

    Marcan, P.

    2008-01-01

    When information on plans to build a power station in Trebisov first appeared reactions differed. A 40-billion investment in a town with more than 20% unemployment seemed attractive. But some people did not like the idea of having a power plant located in the town. Around one year after the investment was officially announced TREND returned to Trebisov. In the meantime the investor has managed to overcome one of the biggest obstacles on its way to building a new power plant. The ministry responsible gave the environmental study a positive rating. But objectors are still not sure that everything is fine. They claim that the study misinterprets data and that the ministry did not show expertise when evaluating it. 'Is it possible that a coal power plant located in a town would have twice as many positive effects on peoples' health than negative ones? Why don't we build them everywhere?'asked the chairman of the civic society, Trebisov nahlas, Gejza Gore. The developer of the project, Ceskoslovenska energeticka spolocnost (CES), Kosice is fighting back and claims that their counterpart lacks professional arguments. In the meantime it is preparing for area management proceedings. Trebisov is also involved in the discussion and claims that the town planning scheme does not include such a project. The Ministry of Construction has a different opinion. In the opinion of the Ministry the town planning scheme allows a 885-megawatt power plant to be built only a few hundred meters away from housing estates. (author)

  17. Shippingport station communications program

    International Nuclear Information System (INIS)

    Stote, J.J.

    1988-01-01

    At the Shippingport Station Decommissioning Project, the central idea of the communications program that was developed for use was purposely designed to be as uncomplicated as possible. The central theme, that was developed and communicated, is that all nuclear plants will someday need to be retired and also decommissioned. The Shippingport Plant, originally constructed as a demonstration nuclear power plant, was now being decommissioned as a demonstration to the world-wide nuclear industry that this evolution can be done in a safe and cost-effective manner. Furthermore, the technology currently exists to complete this process. The new phase of the communications program was initiated even before the responsibility for the plant was transferred from Duquesne Light to GE. With such a change forthcoming, it was necessary to inform local officials of these plans, and the reasons for them. Equally important was the need to inform a variety of agencies and offices in the three-state area of the changes, and the continuing need to involve them in the Site Emergency Plan. This document was also revised in recognition of changing site conditions, as well as the changes in responsibility. 1 ref

  18. Smithsonian Marine Station (SMS) at Fort Pierce

    Science.gov (United States)

    share current Smithsonian research on the plants and animals of the Indian River Lagoon and marine Smithsonian Marine Station at Fort Pierce Website Search Box Search Field: SMS Website Search Twitter SMS Home › Welcome to the Smithsonian Marine Station Homepage slideshow Who We Are... The

  19. The decommissioning of commercial magnox gas cooled reactor power stations in the United Kingdom

    International Nuclear Information System (INIS)

    Holt, G.

    1998-01-01

    There are nine commercial Magnox gas-cooled reactor power stations in the United Kingdom. Three of these stations have been shutdown and are being decommissioning, and plans have also been prepared for the eventual decommissioning of the remaining operational stations. The preferred strategy for the decommissioning of the Magnox power stations has been identified as 'Safestore' in which the decommissioning activities are carried out in a number of steps separated by quiescent periods of care and maintenance. The final clearance of the site could be deferred for up to 135 years following station shutdown so as to obtain maximum benefit from radioactive decay. The first step in the decommissioning strategy is to defuel the reactors and transport all spent and new fuel off the site. This work has been completed at all three shutdown stations. Decommissioning work is continuing on the three sites and has involved activities such as dismantling, decontamination, recycling and disposal of some plant and structures, and the preparation of others for retention on the site for a period of care and maintenance. Significant experience has been gained in the practical application of decommissioning, with successful technologies and processes being identified for a wide range of activities. For example, large and small metallic and concrete structures, some with complex geometries, have been successfully decontaminated. Also, the reactors have been prepared for a long period of care and maintenance, with instrumentation and sampling systems having been installed to monitor their continuing integrity. All of this work has been done under careful safety, technical, and financial control. (author)

  20. The annal of british RPV steel plates for first nuclear power station in Japan (1). Unforseen accidents araised before nuclear power plant open

    International Nuclear Information System (INIS)

    Miyoshi, Shigeru

    2011-01-01

    This article described the author's experiences of reactor vessel steel plates for the first nuclear power station, Tokai-mura reactor. The station is an advanced Calder Hall type. The electrical output is 166 MWe. The reactor vessel was spherical with internal diameter of 189 cm and wall thickness of 83 mm. Material was a fine-grain, aluminum-killed steel. Each part of pressure vessel, bottom cap, belt 1, 2, 3, 4 and top cap, were prefabricated with welding of plates, then lifted into the reactor building and assembled with welding. Steel plates were imported from UK, press formed to spherical segments in Japan and transferred to the site. Ultrasonic testing, magnetic particle testing of groove face (crack detection), sizing of groove and sulfur print tests were performed as an on-site acceptance testing. Inclusions and lamination openings were observed at groove faces due to gas flame cutting. White spot was observed at rupture face of tensile test specimen. At the liquid penetration testing after back gauging of extra seam, a crack-like indication with length of less than 3 mm was observed. Reexamination of groove face by magnetic particles testing showed indications of inclusion cloud or alumina cloud. These would be cracks caused by hydrogen embrittlement. (T. Tanaka)

  1. Model-based monitoring, optimisation and cogeneration plant billing in heating power stations; Modellgestuetzte Ueberwachung, Optimierung und KWK Abrechnung in Heizkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Deeskow, P. [STEAG KETEK IT GmbH, Oberhausen (Germany); Pawellek, R. [Sofbid GmbH, Zwingenberg (Germany)

    2005-07-01

    On the basis of thermodynamic modelling, efficient online systems can be constructed which provide multiple commercial uses for plant operation. Incipient failures are recognized earlier, so that countermeasures can be taken at an early stage and long-term maintenance measures can be planned. Performance can be optimised, and - last but not least - the multitude of processed data enables workflow analysis, e.g. for simplifying billing processes in secondary relational databases. Performance data are presented of two coal power plants with 350 MWel/250MWth and 450MWel/50MWth in which systems of this type have been in use for several years now. (orig.)

  2. The Trencin water power station

    International Nuclear Information System (INIS)

    2005-01-01

    of the impeller wheel 3800 mm. Its water absorption maximum flow is 90 m 3 .s -1 and operational extension of the head between 13.85 and 10,35 m. Maximum power output of the generator is 11.5 MVA, a nominal voltage 10.5 kV and the power factor cos φ = 0.7. The power station has a block arrangement with its output led out through the 22 kV switchgear that is connected to the 110 kV switchgear. The big inner cubicle-type switchgear of 22 kV provides power supplies for many industrial plants in Trencin and for the city of Trencin itself, as well as interconnection with neighbouring water power stations

  3. Effect of pruning height on the architecture of plants of camu camu (Myrciaria dubia HBK Mc Vaugh in the experimental station of IIAP, Ucayali, Peru.

    Directory of Open Access Journals (Sweden)

    Carlos Abanto

    2011-06-01

    Full Text Available In order to evaluate the response camu camu’s plants in plantations initial undergoing training pruning, an experiment was installed in EE - IIAP-Ucayali, under a design randomized complete block, with 3 replications, making use of 20 plants per experimental unit. The pruning treatments were performing at different heights from the base of the stem, it was considered T0 [witness without pruning], T1 [pruning to 10 cm from the base], T2 [pruning to 20 cm from the base] and T3 [pruning to 40 cm from the base] in plants of known provenance. The investigation was directed to evaluate the number of shoots, shoot growth, plant height, basal diameter, crown diameter and number of branches. After of 9 months of evaluation was found significant differences between the variables except in top diameter. In the variable Height, treatment T0 [witness without pruning] outstanding because they were not pruned, among the remaining treatments has similarly behaved, surpassing the control treatment by 267 %. In addition to this, the basal diameter was found that T1 [pruning to 10 cm from the base] has a better performed with an average value of 1.96 cm compared with the control (1.7cm. The pruning had a positive influence in the number of branches, with an average of 13.4 branches compared with T0 that get 3.1 branches on average, its shows that the pruning can increased up the production of branches to 432.3%.

  4. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    International Nuclear Information System (INIS)

    Baker, J.W.

    1982-11-01

    The case for Sizewell B in terms of the CEGB's overall duties, policies and objectives is presented. The discussion concentrates on the rationale of the CEGB's wish to proceed with Sizewell B and the implications which an eventual decision to proceed with a Pressurised Water Reactor at Sizewell could have for future power station orders. (U.K.)

  5. Bradwell Nuclear Power Station

    International Nuclear Information System (INIS)

    1987-01-01

    When built, the Magnox reactors were expected to have operating lifetimes of 20-25 years. In order to satisfy the licensing authorities of their continued safety, long term safety reviews (LTSRs) are being carried out as the reactors reach 20 years of operation. This is the Nuclear Installations Inspectorate's (NII) summary report on Bradwell nuclear power station. The objectives of the LTSR are stated. A description of the plant is followed by an explanation of the statutory position on licensing. The responsibilities of the Central Electricity Generating Board (CEGB) and the NII are defined. From the examination of the CEGB's LTSR it is concluded that this generally confirms the validity of the existing safety case for present operation. However, some recommendations are made as to work required for reactor operation up to 1992. A summary of the NII findings is presented. This includes the reactor pressure circuit integrity, effects of ageing and in-service wear and radiation doses. (U.K.)

  6. Experiences with a new technology of the water treatment at the reverse osmosis plant in the power station Schkopau; Betriebserfahrungen mit einer neuen Art der Wasserbehandlung an der Umkehrosmose-Anlage im Kraftwerk Schkopau

    Energy Technology Data Exchange (ETDEWEB)

    Geissler, K.P. [E.ON Kraftwerke, Schkopau (Germany); Nebauer, G.; Schallert, B. [E.ON Engineering, Gelsenkirchen (Germany); Koerner, J.; Koppe, J. [MOL Katalysatorentechnik GmbH, Schkopau (Germany)

    2003-07-01

    Similar to any river, the water of the river Saale shows strong fluctuations in the composition as a result of the local rain events and the climatic conditions. In the year 1992, when the planning started for the power station building the fluctuations of filtered substances, the acid capacity, the organic load of the water and the colony forming unities as a summary recording of bacteria etc. were not striking in comparison with former years. With the complete processing technique upstream of the reverse osmosis plant it became almost quantitatively to remove and to tie bacteria and higher microbiology and to eliminate diluted organic components (DOC), feast substances, and to reduce the carbonate hardness. The company MOL Katalysatortechnik GmbH offered power station operators already in 1999 a method with which biological growth can be limited in cooling circuits. (orig.) [German] Der Ueberschuss von Desinfektionsmitteln wie Chlor, Chlorbleichlauge oder Chlordioxid muss zwingend vor der UO-Anlage durch Zugabe von Reduktionsmitteln beseitigt sein, weil die UO-Membranen auf Polyamidbasis durch Oxidationsvorgaenge selbst nach kurzer Einwirkung Leistungsabnahmen aufweisen. Als Nachteil dieser Vorgehensweise bestehen bereits hinter der Dosierstelle des Reduktionsmittels, d.h. am Kerzenfilter und auch an der UO-Anlage, Bedingungen, die biologisches Wachstum kaum einschraenken und deshalb in hohem Masse zeitaufwaendige Reinigungsvorgaenge erfordern. (orig.)

  7. Reviewing nuclear power station achievement

    International Nuclear Information System (INIS)

    Howles, L.R.

    1976-01-01

    For measurement of nuclear power station achievement against original purchase the usual gross output figures are of little value since the term loosely covers many different definitions. An authentically designed output figure has been established which relates to net design output plus house load at full load. Based on these figures both cumulative and moving annual load factors are measured, the latter measuring the achievement over the last year, thus showing trends with time. Calculations have been carried out for all nuclear stations in the Western World with 150 MW(e) gross design output and above. From these are shown: moving annual load factor indicating relative station achievements for all the plants; cumulative load factors from which return of investment can be calculated; average moving annual load factors for the four types of system Magnox, PWR, HWR, and BWR; and a relative comparison of achievement by country in a few cases. (U.K.)

  8. Interactive firing and control station simulation of a waste incineration plant with grate firing; Interaktive Feuerungsbetriebs- und Leitstandssimulation einer Abfallverbrennungsanlage mit Rostfeuerung

    Energy Technology Data Exchange (ETDEWEB)

    Boller, M.; Urban, A.I. [Kassel Univ. (Gesamthochschule) (Germany). Fachgebiet Abfalltechnik

    1998-09-01

    In the course of several years` work in the area of waste engineering a model was developed which maps the dynamic behaviour of the plant from waste delivery to deslagging, crude gas output, and steam generation, thus providing a unique solution in terms of function and scope. This was made possible by the use of the semi-empirical approach of ``System Dynamics``. The approach presupposes that the model has already been adapted to reality by means of comparative studies. Expensive as it is, this procedure is necessary for waste incineration plants because theoretical analyses can never model the behaviour of the plant as a whole but only individual stages. [Deutsch] Durch mehrjaehrige Arbeiten ist im Fachgebiet Abfalltechnik ein Modell einer Abfallverbrennungsanlage enstanden, welches das dynamische Verhalten der Anlage von der Abfallaufgabe bis zur Entschlackung, dem Rohgasausgang und der Dampfproduktion abbildet und damit vom Umfang und der Funktion einmalig ist. Dies war moeglich, da der halbempirische Ansatz `System Dynamics` gewaehlt wurde, der das Anpassen des Modells an die Realitaet durch vergleichende Untersuchungen voraussetzt. Eine solche Vorgehensweise ist zwar aufwendig, im Bereich der MVA aber notwendig, da sich mit theoretischen Analysen nie das gesamte Anlagenverhalten erfassen laesst, sondern immer nur einzelne Ausschnitte. (orig.)

  9. Guidelines for Learning Stations.

    Science.gov (United States)

    Fehrle, Carl C.; Schulz, Jolene

    Guidelines for designing and planning learning stations for pupils at the elementary grade level include suggestions on how to develop a station that will be successful in meeting the learners' needs. Instructions for the use of tapes at a station and matching pupils with stations are given, as are guidelines on classroom arrangement and record…

  10. Lifetime risk of developing impaired glucose metabolism and eventual progression from prediabetes to type 2 diabetes: a prospective cohort study.

    Science.gov (United States)

    Ligthart, Symen; van Herpt, Thijs T W; Leening, Maarten J G; Kavousi, Maryam; Hofman, Albert; Stricker, Bruno H C; van Hoek, Mandy; Sijbrands, Eric J G; Franco, Oscar H; Dehghan, Abbas

    2016-01-01

    Data are scarce for the lifetime risk of developing impaired glucose metabolism, including prediabetes, as are data for the risk of eventual progression from prediabetes to diabetes and for initiation of insulin treatment in previously untreated patients with diabetes. We aimed to calculate the lifetime risk of the full range of glucose impairments, from normoglycaemia to prediabetes, type 2 diabetes, and eventual insulin use. In this prospective population-based cohort analysis, we used data from the population-based Rotterdam Study. We identified diagnostic events by use of general practitioners' records, hospital discharge letters, pharmacy dispensing data, and serum fasting glucose measurements taken at the study centre (Rotterdam, Netherlands) visits. Normoglycaemia, prediabetes, and diabetes were defined on the basis of WHO criteria for fasting glucose (normoglycaemia: ≤6·0 mmol/L; prediabetes: >6·0 mmol/L and prediabetes to overt diabetes and from diabetes free of insulin treatment to insulin use. Additionally, we calculated years lived with healthy glucose metabolism. We used data from 10 050 participants from the Rotterdam Study. During a follow-up of up to 14·7 years (between April 1, 1997, and Jan 1, 2012), 1148 participants developed prediabetes, 828 developed diabetes, and 237 started insulin treatment. At age 45 years, the remaining lifetime risk was 48·7% (95% CI 46·2-51·3) for prediabetes, 31·3% (29·3-33·3) for diabetes, and 9·1% (7·8-10·3) for insulin use. In individuals aged 45 years, the lifetime risk to progress from prediabetes to diabetes was 74·0% (95% CI 67·6-80·5), and 49·1% (38·2-60·0) of the individuals with overt diabetes at this age started insulin treatment. The lifetime risks attenuated with advancing age, but increased with increasing BMI and waist circumference. On average, individuals with severe obesity lived 10 fewer years without glucose impairment compared with normal-weight individuals. Impaired glucose

  11. Decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Gregory, A.R.

    1988-01-01

    In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

  12. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    International Nuclear Information System (INIS)

    Wilson, A.

    1982-11-01

    The methods of establishing construction time, capital cost, availability and lifetime of different types of generating plant are described. In volume one assessments are presented for a new coal fired station, for a new AGR station and for a new PWR station - Sizewell B. Volume two, contains all diagrams, tables and appendices presented as evidence. (U.K.)

  13. The incident guidelines for nuclear power stations of the FRG - an example illustrating the degradation of safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1984-01-01

    The 'Guidelines for the Assessment of the Design of Nuclear Power Plants Against Incidents', i.e. the Federal German Incident Guidelines, have been the subject of an official hearing of experts before the Committee of Internal Affairs of the German Bundestag on February 22, 1984. The report in hand presents the official invitation to the meeting, the list of questions posed, written statements given by critics, and an appendix with the full text of the Incident Guidelines, as of August 12, 1983. (orig./HP) [de

  14. Transcriptome patterns from primary cutaneous Leishmania braziliensis infections associate with eventual development of mucosal disease in humans.

    Directory of Open Access Journals (Sweden)

    Ana Claudia Maretti-Mira

    Full Text Available INTRODUCTION: Localized Cutaneous Leishmaniasis (LCL and Mucosal Leishmaniasis (ML are two extreme clinical forms of American Tegumentary Leishmaniasis that usually begin as solitary primary cutaneous lesions. Host and parasite factors that influence the progression of LCL to ML are not completely understood. In this manuscript, we compare the gene expression profiles of primary cutaneous lesions from patients who eventually developed ML to those that did not. METHODS: Using RNA-seq, we analyzed both the human and Leishmania transcriptomes in primary cutaneous lesions. RESULTS: Limited number of reads mapping to Leishmania transcripts were obtained. For human transcripts, compared to ML patients, lesions from LCL patients displayed a general multi-polarization of the adaptive immune response and showed up-regulation of genes involved in chemoattraction of innate immune cells and in antigen presentation. We also identified a potential transcriptional signature in the primary lesions that may predict long-term disease outcome. CONCLUSIONS: We were able to simultaneously sequence both human and Leishmania mRNA transcripts in primary cutaneous leishmaniasis lesions. Our results suggest an intrinsic difference in the immune capacity of LCL and ML patients. The findings correlate the complete cure of L. braziliensis infection with a controlled inflammatory response and a balanced activation of innate and adaptive immunity.

  15. Eventual sport performance level: What about the role of type of sport, perception of critical life events, and practice quality?

    Science.gov (United States)

    Toering, Tynke

    2017-01-01

    The target article describes an interesting study, which provides some challenging findings regarding athletes' pathway to excellence. The suggested links between critical life events, need for success, personal characteristics, and eventual performance level make sense from a psychodynamic perspective. This commentary will discuss some critical points related to the application of the findings in talent identification and -development programs. These are (1) the possible effect of the selection of participants on the results (including the impact of dependence on others for team sport athletes and the opportunity for multiple medal attainment), (2) a lack of detail in the description of how the athletes approached the critical life events (the perception of an event may contribute more to development than the event itself), and (3) a lack of detail in the description of the practice process throughout development. Some interesting differences were found in the motivation for and approach to practice, but little detail was given about what the athletes exactly were doing at the time. The concept of self-regulated learning may be useful in explaining how super-elite athletes action their goals through quality practice. © 2017 Elsevier B.V. All rights reserved.

  16. OpenStack Swift as Multi-Region Eventual Consistency Storage for ownCloud Primary Storage

    CERN Multimedia

    CERN. Geneva

    2014-01-01

    As more users adopt AARNet’s CloudStor Plus offering within Australia, interim solutions deployed to overcome failures of various distributed replicated storage technologies haven’t kept pace with the growth in data volume. AARNet’s original design goal of user proximal data storage, combined with national and even international data replication for redundancy reasons continues to be a key driver for design choices. AARNet’s national network is over 90ms from end to end, and accommodating this has been a key issue with numerous software solutions, hindering attempts to provide both original design goals in a reliable real-time manner. With the addition of features to the ownCloud software allowing primary data storage on OpenStack Swift, AARNet has chosen to deploy Swift in a nation spanning multi-region ring to take advantage of Swift’s eventual consistency capabilities and the local region quorum functionality for fast writes. The scaling capability of Swift resolves the twin problems of geogr...

  17. A study of design features of civil works of nuclear installations facilitating their eventual refurbishing, renewal, dismantling or demolition

    International Nuclear Information System (INIS)

    Paton, A.A.; Benwell, P.; Irwin, T.F.; Hunter, I.

    1984-03-01

    This report describes a study that has been carried out to identify civil engineering features which could be incorporated in future gas cooled and light water cooled nuclear power plants to facilitate their decommissioning. The report reviews the problems likely to be met in decommissioning present day nuclear power plants and concludes that there is a number of such features which could be introduced in future designs to overcome or eliminate the problems. The report identifies and describes these features and recommends that further work be carried out to confirm their feasibility. The study briefly considered the possibility of refurbishing nuclear plants and concluded that this is not a realistic option in present circumstances. (author)

  18. Swedish encapsulation station review

    International Nuclear Information System (INIS)

    Andersson, Sven Olof; Brunzell, P.; Heibel, R.; McCarthy, J.; Pennington, C.; Rusch, C.; Varley, G.

    1998-06-01

    In the Encapsulation Station (ES) Review performed by NAC International, a number of different areas have been studied. The main objectives with the review have been to: Perform an independent review of the cost estimates for the ES presented in SKB's document 'Plan 1996'. This has been made through comparisons between the ES and BNFL's Waste Encapsulation Plant (WEP) at Sellafield as well as with the CLAB facility. Review the location of the ES (at the CLAB site or at the final repository) and its interaction with other parts of the Swedish system for spent fuel management. Review the logistics and plant capacity of the ES. Identify important safety aspects of the ES as a basis for future licensing activities. Based on NAC International's experience of casks for transport and storage of spent fuel, review the basic design of the copper/steel canister and the transport cask. This review insides design, manufacturing, handling and licensing aspects. Perform an overall comparison between the ES project and the CLAB project with the objective to identify major project risks and discuss their mitigation

  19. Swedish encapsulation station review

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Sven Olof; Brunzell, P.; Heibel, R.; McCarthy, J.; Pennington, C.; Rusch, C.; Varley, G. [NAC International, Zuerich (Switzerland)

    1998-06-01

    In the Encapsulation Station (ES) Review performed by NAC International, a number of different areas have been studied. The main objectives with the review have been to: Perform an independent review of the cost estimates for the ES presented in SKB`s document `Plan 1996`. This has been made through comparisons between the ES and BNFL`s Waste Encapsulation Plant (WEP) at Sellafield as well as with the CLAB facility. Review the location of the ES (at the CLAB site or at the final repository) and its interaction with other parts of the Swedish system for spent fuel management. Review the logistics and plant capacity of the ES. Identify important safety aspects of the ES as a basis for future licensing activities. Based on NAC International`s experience of casks for transport and storage of spent fuel, review the basic design of the copper/steel canister and the transport cask. This review insides design, manufacturing, handling and licensing aspects. Perform an overall comparison between the ES project and the CLAB project with the objective to identify major project risks and discuss their mitigation 19 refs, 9 figs, 35 tabs

  20. Design of earth slide prevention structure and results of analyzing its behavior in excavation work for main building foundation for No.4 plant in Kashiwazaki-Kariwa Nuclear Power Station

    International Nuclear Information System (INIS)

    Kuroda, Teruo; Shimazu, Masaomi; Terada, Kenji

    1990-01-01

    In the construction works for No.4 plant in Kashiwazaki-Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc., the excavation work using ground anchor type earth slide prevention structure of about 30 m height intended for soft rocks was carried out. In this report, the outline of the design of the earth slide prevention structure is described, and based on the results of measurement of the earth slide prevention structure and surrounding ground during the period of the excavation work, the effect that the underground continuous wall normally intersecting with the back of the earth slide prevention wall and structurally separated from it exerted to the deformation behavior of the earth slide prevention wall was examined, and the results are reported. The geological features of the site are explained. The excavation work is to excavate the site of +5 m level down to -26 m for the turbine building and to -38.15 m for the reactor building, and the quantity of earth to be excavated is 1.39 million m 3 . These valuable experiences are utilized for the design and construction of the following plants. (K.I.)

  1. Utilities respond to nuclear station blackout rule

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  2. BAR-CODE BASED WEIGHT MEASUREMENT STATION FOR PHYSICAL INVENTORY TAKING OF PLUTONIUM OXIDE CONTAINERS AT THE MINING AND CHEMICAL COMBINE RADIOCHEMICAL REPROCESSING PLANT NEAR KRASNOYARSK, SIBERIA

    International Nuclear Information System (INIS)

    SUDA, S.

    1999-01-01

    This paper describes the technical tasks being implemented to computerize the physical inventory taking (PIT) at the Mining and Chemical Combine (Gorno-Khimichesky Kombinat, GKhK) radiochemical plant under the US/Russian cooperative nuclear material protection, control, and accounting (MPC and A) program. Under the MPC and A program, Lab-to-Lab task agreements with GKhK were negotiated that involved computerized equipment for item verification and confirmatory measurement of the Pu containers. Tasks under Phase I cover the work for demonstrating the plan and procedures for carrying out the comparison of the Pu container identification on the container with the computerized inventory records. In addition to the records validation, the verification procedures include the application of bar codes and bar coded TIDs to the Pu containers. Phase II involves the verification of the Pu content. A plan and procedures are being written for carrying out confirmatory measurements on the Pu containers

  3. On alteration of reactor installation (additional installation of No.3 and No.4 plants in the Genkai Nuclear Power Station, Kyushu Electric Power Co., Inc.)

    International Nuclear Information System (INIS)

    1985-01-01

    The Nuclear Safty Commission sent the reply to the Minister of International Trade and Industry on October 4, 1984, on this matter after having received the report from the Committee on Examination of Nuclear Reactor Safety and carried out the deliberation. It was judged that the applicant has the technical capability required for installing and operating these reactor facilities. Also it was judged that on the safety after these reactor plants are installed, there is no obstacle in the prevention of disaster due to contaminated substances and reactors. The policy of the investigation and deliberation is reported. The contents of the investigation and deliberation are the condition of location such as site, geological features and ground, earthquake, weather, hydraulic problem and social environments, the safety design of reactor facilities, the evaluation of radiation exposure dose in normal operation, the analysis of abnormal transient change in operation, accident analysis and the evaluation of location. (Kako, I.)

  4. Oil use of the effluent plant ETEO (Effluent Station of Oil Treatment) as combustible for generation of energy in the power plant UG-50Hz; Utulizacao de oleo da ETEO (Estacao de Tratamento de Efluentes Oleosos) para geracao de energia na UG-50Hz

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Jose Francisco de; Nascimento, Jose Maria do; Silva, Luiz Antonio da; Salazar, Marcos Vinicios; Baptista, Reinaldo Lopes; Barros, Sueli Aguiar [Companhia Siderurgica Nacional (CSN), Volta Redonda, RJ (Brazil)

    2009-11-01

    The areas of finishing products of CSN Steel Plant generate contaminated effluents with oil and grease , that are treated in ETEO (Effluent Station of Oil Treatment). In this plant, the oil is processed to be sold for the consuming market. However, some seasons of the year, the market does not absorb the oil, and CSN is obliged to defray the burning of this oil, to not interrupt the productive process and cause an environmental impact. Because of this situation, we search alternatives for the viable use of this oil inside CSN steel plant, taking care for the security of the processes and the impact to the environment. This paper describes the details of the work and the implantation of the burning of this oil of the ETEO with BPF oil (type of petrochemical oil) as combustible in the boiler 7 of the power plant UG 50 Hz. For the implantation of this project, operational contingencies of security for equipment was prepared . Moreover, the work included chemical analyses of the oil and the conditions of the boiler using this mixing of oils. The reached results demonstrate the total viability of this project and it was proved another alternative of the use of this residue, with reduction of the fuel costs , steam costs and the electric energy generated in the power plant of CSN. (author)

  5. Clinical medical education in rural and underserved areas and eventual practice outcomes: A systematic review and meta-analysis.

    Science.gov (United States)

    Raymond Guilbault, Ryan William; Vinson, Joseph Alexander

    2017-01-01

    Undergraduate medical students are enrolled in clinical education programs in rural and underserved urban areas to increase the likelihood that they will eventually practice in those areas and train in a primary care specialty to best serve those patient populations. MEDLINE and Cochrane Library online databases were searched to identify articles that provide a detailed description of the exposure and outcome of interest. A qualitative review of articles reporting outcome data without comparison or control groups was completed using the Medical Education Research Study Quality Instrument (MERSQI). A meta-analysis of articles reporting outcome data with comparison or control groups was completed with statistical and graphical summary estimates. Seven hundred and nine articles were retrieved from the initial search and reviewed based on inclusion and exclusion criteria. Of those, ten articles were identified for qualitative analysis and five articles included control groups and thus were included in the quantitative analysis. Results indicated that medical students with clinical training in underserved areas are almost three times as likely to practice in underserved areas than students who do not train in those areas (relative risk [RR] = 2.94; 95% confidence interval [CI]: 2.17, 4.00). Furthermore, medical students training in underserved areas are about four times as likely to practice primary care in underserved areas than students who do not train in those locations (RR = 4.35; 95% CI: 1.56, 12.10). These estimates may help guide medical school administrators and policymakers to expand underserved clinical training programs to help relieve some of the problems associated with access to medical care among underserved populations.

  6. Investigation of the mixed beta-photon radiation field in plant areas of the heat steam generator of the Obrigheim nuclear power station

    International Nuclear Information System (INIS)

    Burgkhardt, B.; Piesch, E.

    1988-10-01

    The investigations of the beta-photon radiation field in parts of the plant in the primary circuit were performed by irradiation experiments in different distances of exhausted disks of the heat steam generator using LiF-TLDs. The depth dose distribution for a detector free of mass is found on the basis of the measurement results by using a standardized extrapolation procedure. The measurement results show that the depth dose distribution is more or less independent of the detector-to-source distance if the absorption in air and the detector is taken into account. Thus low energy beta-photon fields can be analyzed, in general, using the results found in one distance of about 5 cm from the source. For the purpose of radiation protection at working places transmission factors for protective clothes and detectors of different thicknesses were determined. The estimation of the dose equivalents H'(0.07) and H'(10) and the dose equivalents in the lens of the eye and the testes shows that the low energy beta radiation component contributes only to the partial dose equivalent H'(0.07) and will be absorbed by a protective layer of 100 mg.cm -2 . (orig.) [de

  7. Reference Climatological Stations

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Reference Climatological Stations (RCS) network represents the first effort by NOAA to create and maintain a nationwide network of stations located only in areas...

  8. Streamflow Gaging Stations

    Data.gov (United States)

    Department of Homeland Security — This map layer shows selected streamflow gaging stations of the United States, Puerto Rico, and the U.S. Virgin Islands, in 2013. Gaging stations, or gages, measure...

  9. Fire Stations - 2007

    Data.gov (United States)

    Kansas Data Access and Support Center — Fire Station Locations in Kansas Any location where fire fighters are stationed at or based out of, or where equipment that such personnel use in carrying out their...

  10. Hammond Bay Biological Station

    Data.gov (United States)

    Federal Laboratory Consortium — Hammond Bay Biological Station (HBBS), located near Millersburg, Michigan, is a field station of the USGS Great Lakes Science Center (GLSC). HBBS was established by...

  11. Water Level Station History

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Images contain station history information for 175 stations in the National Water Level Observation Network (NWLON). The NWLON is a network of long-term,...

  12. Weather Radar Stations

    Data.gov (United States)

    Department of Homeland Security — These data represent Next-Generation Radar (NEXRAD) and Terminal Doppler Weather Radar (TDWR) weather radar stations within the US. The NEXRAD radar stations are...

  13. Big Game Reporting Stations

    Data.gov (United States)

    Vermont Center for Geographic Information — Point locations of big game reporting stations. Big game reporting stations are places where hunters can legally report harvested deer, bear, or turkey. These are...

  14. Ocean Station Vessel

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Ocean Station Vessels (OSV) or Weather Ships captured atmospheric conditions while being stationed continuously in a single location. While While most of the...

  15. Fire Stations - 2009

    Data.gov (United States)

    Kansas Data Access and Support Center — Fire Stations in Kansas Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their jobs is...

  16. Newport Research Station

    Data.gov (United States)

    Federal Laboratory Consortium — The Newport Research Station is the Center's only ocean-port research facility. This station is located at Oregon State University's Hatfield Marine Science Center,...

  17. Solidifying power station resins and sludges

    International Nuclear Information System (INIS)

    Willis, A.S.D.; Haigh, C.P.

    1984-01-01

    Radioactive ion exchange resins and sludges arise at nuclear power stations from various operations associated with effluent treatment and liquid waste management. As the result of an intensive development programme, the Central Electricity Generating Board (CEGB) has designed a process to convert power station resins and sludges into a shielded, packaged solid monolithic form suitable for final disposal. Research and development, the generic CEGB sludge/resin conditioning plant and the CEGB Active Waste Project are described. (U.K.)

  18. Pumps for nuclear power stations

    International Nuclear Information System (INIS)

    Ogura, Shiro

    1979-01-01

    16 nuclear power plants are in commercial operation in Japan, and nuclear power generation holds the most important position among various substitute energies. Hereafter also, it is expected that the construction of nuclear power stations will continue because other advantageous energy sources are not found. In this paper, the outline of the pumps used for BWR plants is described. Nuclear power stations tend to be large scale to reduce the construction cost per unit power output, therefore the pumps used are those of large capacity. The conditions to be taken in consideration are high temperature, high pressure, radioactive fluids, high reliability, hydrodynamic performances, aseismatic design, relevant laws and regulations, and quality assurance. Pumps are used for reactor recirculation system, control rod driving hydraulic system, boric acid solution injecting system, reactor coolant purifying system, fuel pool cooling and purifying system, residual heat removing system, low pressure and high pressure core spraying systems, and reactor isolation cooling system, for condensate, feed water, drain and circulating water systems of turbines, for fresh water, sea water, make-up water and fire fighting services, and for radioactive waste treating system. The problems of the pumps used for nuclear power stations are described, for example, the requirement of high reliability, the measures to radioactivity and the aseismatic design. (Kako, I.)

  19. Managing nuclear power stations for success

    International Nuclear Information System (INIS)

    Smith, G.

    2006-01-01

    Ontario Power Generation's (OPG) top operational priority is to manage its nuclear assets to ensure they operate as safely, efficiently and cost effectively as possible. In meeting these objectives, the company is focused on continuously improving its nuclear performance and benchmarking that performance against the best in North America. This presentation explores how OPG is improving its nuclear performance and the steps it is taking to sustain performance success going forward. Topics to be discussed include the measures OPG is taking to enhance human performance and station reliability as well as the company's preparations to determine if a business case exists for extending the lives of the Pickering B and eventually the Darlington nuclear stations. (author)

  20. How to handle station black outs

    International Nuclear Information System (INIS)

    Reisch, Frigyes

    1986-01-01

    Station black out is defined as the loss of ail high voltage alternating current at a nuclear power site. An international study was made to survey the practices in the different countries. The best way to handle station black out is to avoid it therefore briefly the normal off site and emergency on site power supplies are discussed. The ways in use to enhance nuclear power plants using Boiling Water Reactors or Pressurized Water Reactors to cope with a station black out are discussed in some detail. (author)

  1. How to handle station black outs

    Energy Technology Data Exchange (ETDEWEB)

    Reisch, Frigyes [Swedish Nuclear Power Inspectorate, S-10252 Stockholm (Sweden)

    1986-02-15

    Station black out is defined as the loss of ail high voltage alternating current at a nuclear power site. An international study was made to survey the practices in the different countries. The best way to handle station black out is to avoid it therefore briefly the normal off site and emergency on site power supplies are discussed. The ways in use to enhance nuclear power plants using Boiling Water Reactors or Pressurized Water Reactors to cope with a station black out are discussed in some detail. (author)

  2. CDIP Station Data Collection - All Stations

    Data.gov (United States)

    Scripps Institution of Oceanography, UC San Diego — The Coastal Data Information Program's station data collection consists of all publicly-released coastal environment measurements taken over the program's history, a...

  3. Construction work management for nuclear power stations

    International Nuclear Information System (INIS)

    Yoshikawa, Yuichiro

    1982-01-01

    Nuclear power generation is positioned as the nucleus of petroleum substitution. In the Kansai Electric Power Co., efforts have been made constantly to operate its nuclear power plants in high stability and safety. At present, Kansai Electric Power Co. is constructing Units 3 and 4 in the Takahama Nuclear Power Station in Fukui Prefecture. Under the application of the management of construction works described here, both the nuclear power plants will start operation in 1985. The activities of Kansai Electric Power Co. in the area of this management are described: an outline of the construction works for nuclear power stations, the management of the construction works in nuclear power stations (the stages of design, manufacturing, installation and test operation, respectively), quality assurance activities for the construction works of nuclear power plants, important points in the construction work management (including the aspects of quality control). (J.P.N.)

  4. Single-Station Sigma for the Iranian Strong Motion Stations

    Science.gov (United States)

    Zafarani, H.; Soghrat, M. R.

    2017-11-01

    In development of ground motion prediction equations (GMPEs), the residuals are assumed to have a log-normal distribution with a zero mean and a standard deviation, designated as sigma. Sigma has significant effect on evaluation of seismic hazard for designing important infrastructures such as nuclear power plants and dams. Both aleatory and epistemic uncertainties are involved in the sigma parameter. However, ground-motion observations over long time periods are not available at specific sites and the GMPEs have been derived using observed data from multiple sites for a small number of well-recorded earthquakes. Therefore, sigma is dominantly related to the statistics of the spatial variability of ground motion instead of temporal variability at a single point (ergodic assumption). The main purpose of this study is to reduce the variability of the residuals so as to handle it as epistemic uncertainty. In this regard, it is tried to partially apply the non-ergodic assumption by removing repeatable site effects from total variability of six GMPEs driven from the local, Europe-Middle East and worldwide data. For this purpose, we used 1837 acceleration time histories from 374 shallow earthquakes with moment magnitudes ranging from M w 4.0 to 7.3 recorded at 370 stations with at least two recordings per station. According to estimated single-station sigma for the Iranian strong motion stations, the ratio of event-corrected single-station standard deviation ( Φ ss) to within-event standard deviation ( Φ) is about 0.75. In other words, removing the ergodic assumption on site response resulted in 25% reduction of the within-event standard deviation that reduced the total standard deviation by about 15%.

  5. Overview--Development of a geodatabase and conceptual model of the hydrogeologic units beneath Air Force Plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas

    Science.gov (United States)

    Shah, Sachin D.

    2004-01-01

    Air Force Plant 4 (AFP4) and adjacent Naval Air Station-Joint Reserve Base Carswell Field (NAS–JRB) at Fort Worth, Tex., constitute a contractor-owned, government-operated facility that has been in operation since 1942. Contaminants from the 3,600-acre facility, primarily volatile organic compounds (VOCs) and metals, have entered the ground-water-flow system through leakage from waste-disposal sites and from manufacturing processes. Environmental data collected at AFP4 and NAS–JRB during 1993–2002 created the need for consolidation of the data into a comprehensive temporal and spatial geodatabase. The U.S. Geological Survey (USGS), in cooperation with the U.S. Air Force Aeronautical Systems Center Environmental Management Directorate, developed a comprehensive geodatabase of temporal and spatial environmental data associated with the hydrogeologic units beneath the facility. A three-dimensional conceptual model of the hydrogeologic units integrally linked to the geodatabase was designed concurrently. Three hydrogeologic units—from land surface downward, the alluvial aquifer, the GoodlandWalnut confining unit, and the Paluxy aquifer—compose the subsurface of interest at AFP4 and NAS–JRB. The alluvial aquifer consists primarily of clay and silt with sand and gravel channel deposits that might be interconnected or interfingered. The Goodland-Walnut confining unit directly underlies the alluvial aquifer and consists of limestone, marl, shale, and clay. The Paluxy aquifer is composed of dense mudstone and fine- to coarse-grained sandstone

  6. Analyses and estimates of hydraulic conductivity from slug tests in alluvial aquifer underlying Air Force Plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas

    Science.gov (United States)

    Houston, Natalie A.; Braun, Christopher L.

    2004-01-01

    This report describes the collection, analyses, and distribution of hydraulic-conductivity data obtained from slug tests completed in the alluvial aquifer underlying Air Force Plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas, during October 2002 and August 2003 and summarizes previously available hydraulic-conductivity data. The U.S. Geological Survey, in cooperation with the U.S. Air Force, completed 30 slug tests in October 2002 and August 2003 to obtain estimates of horizontal hydraulic conductivity to use as initial values in a ground-water-flow model for the site. The tests were done by placing a polyvinyl-chloride slug of known volume beneath the water level in selected wells, removing the slug, and measuring the resulting water-level recovery over time. The water levels were measured with a pressure transducer and recorded with a data logger. Hydraulic-conductivity values were estimated from an analytical relation between the instantaneous displacement of water in a well bore and the resulting rate of head change. Although nearly two-thirds of the tested wells recovered 90 percent of their slug-induced head change in less than 2 minutes, 90-percent recovery times ranged from 3 seconds to 35 minutes. The estimates of hydraulic conductivity range from 0.2 to 200 feet per day. Eighty-three percent of the estimates are between 1 and 100 feet per day.

  7. 1100 MW BWR power station

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    Now, the start-up test of No. 2 plant in Fukushima No. 2 Nuclear Power Station is smoothly in progress, and the start of its commercial operation is scheduled at the beginning of 1984. Here, the main features of No. 2 plant including piping design are explained. For No. 2 plant, many improving measures were adopted as the base plant of the improvement and standardization project of the Ministry of International Trade and Industry, such as the adoption of Mark-2 improved PCV, the adoption of an intermediate loop in the auxiliary cooling system, one-body forging of the lower end cover of the reactor pressure vessel, the adoption of many curved pipes, the adoption of large one-body structural components in reactor recirculation system piping and so on, which are related to the reduction of radiation exposure and the improvement of plant reliability in operation and regular inspection. Also, in order to do general adjustment in the arrangement of equipment and piping and in route design, and to establish the rational construction work plan, model engineering was adopted. In No. 2 plant, a remote-controlled automatic and semiautomatic ultrasonic flaw detection system was adopted to reduce radiation exposure in in-service inspection. Automatic welding was adopted to improve the quality. (Kako, I.)

  8. Principles of nuclear power station control

    International Nuclear Information System (INIS)

    Knowles, J.B.

    1975-12-01

    This memorandum represents lecture notes first distributed as part of a UKAEA introductory course on Reactor Technology held during November 1975. A nuclear power station is only one element of a dispersed interconnected arrangement of other nuclear and fossil-fired units which together constitute the national 'grid'. Thus the control of any one station must relate to the objectives of the grid network as a whole. A precise control of the supply frequency of the grid is achieved by regulating the output power of individual stations, and it is necessary for each station to be stable when operating in isolation with a variable load. As regards individual stations, several special control problems concerned with individual plant items are discussed, such as: controlled reactivity insertions, temperature reactivity time constants and flow instability. A simplified analysis establishes a fundamental relationship between the stored thermal energy of a boiler unit (a function of mechanical construction) and the flexibility of the heat source (nuclear or fossil-fired) if the station is to cope satisfactorily with demands arising from unscheduled losses of other generating sets or transmission capacity. Two basic control schemes for power station operation are described known as 'coupled' and 'decoupled control'. Each of the control modes has its own merits, which depend on the proposed station operating strategy (base load or load following) and the nature of the heat source. (U.K.)

  9. Gravitational biology on the space station

    Science.gov (United States)

    Keefe, J. R.; Krikorian, A. D.

    1983-01-01

    The current status of gravitational biology is summarized, future areas of required basic research in earth-based and spaceflight projects are presented, and potential applications of gravitational biology on a space station are demonstrated. Topics covered include vertebrate reproduction, prenatal/postnatal development, a review of plant space experiments, the facilities needed for growing plants, gravimorphogenesis, thigmomorphogenesis, centrifuges, maintaining a vivarium, tissue culture, and artificial human organ generation. It is proposed that space stations carrying out these types of long-term research be called the National Space Research Facility.

  10. Selective analysis of power plant operation on the Hudson River with emphasis on the Bowline Point Generating Station. Volume 2. [Multiple impact of power plant once-through cooling systems on fish populations

    Energy Technology Data Exchange (ETDEWEB)

    Barnthouse, L. W.; Cannon, J. B.; Christensen, S. G.

    1977-07-01

    Because of the location of the Bowline, Roseton, and Indian Point power generating facilities in the low-salinity zone of the Hudson estuary, operation of these plants with the present once-through cooling systems will adversely influence the fish populations that use the area for spawning and initial periods of growth and development. Recruitment rates and standing crops of several fish species may be lowered in response to the increased mortality caused by entrainment of nonscreenable eggs and larvae and by impingement of screenable young of the year. Entrainment and impingement data are particularly relevant for assessing which fish species have the greatest potential for being adversely affected by operation of Bowline, Roseton, and Indian Point with once-through cooling. These data from each of these three plants suggest that the six species that merit the greatest consideration are striped bass, white perch, tomcod, alewife, blueback herring, and bay anchovy. Two points of view are available for assessing the relative importance of the fish species in the Hudson River. From the fisheries point of view, the only two species of major importance are striped bass and shad. From the fish-community and ecosystem point of view, the dominant species, as determined by seasonal and regional standing crops (in numbers and biomass per hectare), are the six species most commonly entrained and impinged, namely, striped bass, white perch, tomcod, alewife, blueback herring, and anchovy.

  11. Non-Coop Station History

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Station history documentation for stations outside the US Cooperative Observer network. Primarily National Weather Service stations assigned WBAN station IDs. Other...

  12. Nuclear Station Facilities Improvement Planning

    International Nuclear Information System (INIS)

    Hooks, R. W.; Lunardini, A. L.; Zaben, O.

    1991-01-01

    An effective facilities improvement program will include a plan for the temporary relocation of personnel during the construction of an adjoining service building addition. Since the smooth continuation of plant operation is of paramount importance, the phasing plan is established to minimize the disruptions in day-to-day station operation and administration. This plan should consider the final occupancy arrangements and the transition to the new structure; for example, computer hookup and phase-in should be considered. The nuclear industry is placing more emphasis on safety and reliability of nuclear power plants. In order to do this, more emphasis is placed on operations and maintenance. This results in increased size of managerial, technical and maintenance staffs. This in turn requires improved office and service facilities. The facilities that require improvement may include training areas, rad waste processing and storage facilities, and maintenance facilities. This paper discusses an approach for developing an effective program to plan and implement these projects. These improvement projects can range in magnitude from modifying a simple system to building a new structure to allocating space for a future project. This paper addresses the planning required for the new structures with emphasis on site location, space allocation, and internal layout. Since facility planning has recently been completed by Sargent and Leyden at six U. S. nuclear stations, specific examples from some of those plants are presented. Site planning and the establishment of long-range goals are of the utmost importance when undertaking a facilities improvement program for a nuclear station. A plan that considers the total site usage will enhance the value of both the new and existing facilities. Proper planning at the beginning of the program can minimize costs and maximize the benefits of the program

  13. Base Station Performance Model

    OpenAIRE

    Walsh, Barbara; Farrell, Ronan

    2005-01-01

    At present the testing of power amplifiers within base station transmitters is limited to testing at component level as opposed to testing at the system level. While the detection of catastrophic failure is possible, that of performance degradation is not. This paper proposes a base station model with respect to transmitter output power with the aim of introducing system level monitoring of the power amplifier behaviour within the base station. Our model reflects the expe...

  14. Environment and ecology in the design and construction of a nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Lebreton, J C [Electricite de France, 75 - Paris. Dept. Etudes Generales Programmes-Sites Environnement

    1975-01-01

    The purpose of the studies on the environment of nuclear stations is to reduce changes to the surroundings as much as possible in order not to interfere with ecosystems and consequently impede human activities. A nuclear power station implies heat discharges, radioactive effluent, and wastes and produces a certain sound level and creates aesthetic problems of space occupation. The main questions dealt with are those of heat discharge and noise, together with architectural and aesthetic problems. In the first two cases the intention is to define as accurately as possible the levels reached by the temperature or noise parameter. Where noise is concerned it is enough to know these levels in order to define an eventual hindrance to the target in question, the human being in this case. For heat fluxes man is not directly involved and further research is planned to identify the sensitivity of plants and animals. Since the environment also covers aesthetics, an effort is made to safeguard and improve the quality of the landscape.

  15. Environment and ecology in the design and construction of a nuclear power station

    International Nuclear Information System (INIS)

    Lebreton, J.-C.

    1975-01-01

    The purpose of the studies on the environment of nuclear stations is to reduce changes to the surroundings as much as possible in order not to interfere with ecosystems and consequently impede human activities. A nuclear power station implies heat discharges, radioactive effluent and wastes, produces a certain sound level and creates aesthetic problems of space occupation. The main questions dealt with are those of heat discharge and noise, together with architectural and aesthetic problems. In the first two cases the intention is to define as accurately as possible the levels reached by the temperature or noise parameter. Where noise is concerned it is enough to know these levels in order to define an eventual hindrance to the target in question, the human being in this case. For heat fluxes man is not directly involved and further research is planned to identify the sensitivity of plants and animals. Since the environment also covers aesthetics, an effort is made to safeguard and improve the quality of the landscape [fr

  16. Shadow play for travellers. One of Europe's biggest integrated solar plants is in the roof of Turin central station; Schattenspiel fuer Reisende. Im Dach des Turiner Bahnhofs befindet sich eine der groessten integrierten Solaranlagen Europas

    Energy Technology Data Exchange (ETDEWEB)

    Korn, Stefan

    2012-08-15

    The new central station building in the Italian city of turin shows how photovoltaic technology can combine 21st century aesthetics with the requirements on a modern railway station. The architects combined elements of historical railway station architecture with a modern energy concepts. Thousands of solar cells integrated in the glass roof produce electric power and also regulate lighting and shading in a sophisticated manner.

  17. Amtrak Rail Stations (National)

    Data.gov (United States)

    Department of Transportation — Updated database of the Federal Railroad Administration's (FRA) Amtrak Station database. This database is a geographic data set containing Amtrak intercity railroad...

  18. Cooperative Station History Forms

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Various forms, photographs and correspondence documenting the history of Cooperative station instrumentation, location changes, inspections, and...

  19. Tokai earthquakes and Hamaoka Nuclear Power Station

    International Nuclear Information System (INIS)

    Komura, Hiroo

    1981-01-01

    Kanto district and Shizuoka Prefecture are designated as ''Observation strengthening districts'', where the possibility of earthquake occurrence is high. Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., is at the center of this district. Nuclear power stations are vulnerable to earthquakes, and if damages are caused by earthquakes in nuclear power plants, the most dreadful accidents may occur. The Chubu Electric Power Co. underestimates the possibility and scale of earthquakes and the estimate of damages, and has kept on talking that the rock bed of the power station site is strong, and there is not the fear of accidents. However the actual situation is totally different from this. The description about earthquakes and the rock bed in the application of the installation of No.3 plant was totally rewritten after two years safety examination, and the Ministry of International Trade and Industry approved the application in less than two weeks thereafter. The rock bed is geologically evaluated in this paper, and many doubtful points in the application are pointed out. In addition, there are eight active faults near the power station site. The aseismatic design of the Hamaoka Nuclear Power Station assumes the acceleration up to 400 gal, but it may not be enough. The Hamaoka Nuclear Power Station is intentionally neglected in the estimate of damages in Shizuoka Prefecture. (Kako, I.)

  20. Extension of life of nuclear power stations

    International Nuclear Information System (INIS)

    Takahashi, Hideaki

    1991-01-01

    At the time of designing nuclear power stations, as their service life, generally 40 years are taken, and the basic design specifications of machinery and equipment are determined. In USA where atomic energy has been developed, the new construction of nuclear power stations is cased for a while, however, if this situation continues as it is, since old power stations reach the service life of 40 years and are retired in near future, it is feared that the circumstance of the total amount of power generation becoming short will occur. As one of the countermeasures to this, the research on the extension of life of nuclear power stations has been carried out in many fields in USA, and it is expected that the application for extending the life for the power stations constructed in the initial period of development is submitted in 1991. The researches that have been carried out for solving the technical problems in this extension of life and the situation in Japan are reported. The NEC of USA decided that the operation period of nuclear power stations in USA, which is considered to be 40 years so far, can be extended up to the limit of 20 years. The background and circumstances of this problem in USA, Nuclear Plant Aging Research Program, Plant Life Extension Program and so on are reported. (K.I.)

  1. Technological development of Guangdong nuclear power station

    International Nuclear Information System (INIS)

    Huang Shiqiang

    2000-01-01

    After over 5 years of operations, the Guangdong Nuclear Power Station (GNPS) has achieved good results both economically and in operational safety performance. The main attributes to the success of the plant operational performances include the equipment reliability, the technical capability and management efficiency. To that the key strategy has been to adopt know-how and technological transfer and encourage self-innovation, aiming to strive for the long-term self-reliance in design, manufacturing and operating the plant. (author)

  2. Periodical inspection in nuclear power stations

    International Nuclear Information System (INIS)

    1986-01-01

    Periodical inspection is presently being made of eight nuclear power plants in nuclear power stations. Up to the present time, in three of them, failures as follows have been observed. (1) Unit 3 (PWR) of the Mihama Power Station in The Kansai Electric Power Co., Inc. Nineteen heat-transfer tubes of the steam generators were plugged up due to failure. A fuel assembly with a failed spring fixture and in another the control-rod cluster with a failed control rod fixture were replaced. (2) Unit 2 (PWR) of the Oi Power Station in The Kansai Electric Power Co., Inc. Eight heat-transfer tubes of the heat exchangers were plugged up due to failure. (3) Unit 6 (BWR) of the Fukushima Nuclear Power Station I in The Tokyo Electric Power Co., Inc. A fuel assembly with leakage was replaced. (Mori, K.)

  3. STRUVE arc and EUPOS® stations

    Science.gov (United States)

    Lasmane, Ieva; Kaminskis, Janis; Balodis, Janis; Haritonova, Diana

    2013-04-01

    inspection deformation of leveling networks within the European framework of ground based GNSS European positioning augmentation system EUPOS®. The GNSS observation RTCM corrections produced by the EUPOS® system can be used for high precision position determination in various navigation and land surveying applications. Using EUPOS® network together with data from European Combined Geodetic Network (ECGN) and applying Bernese v.5.0 Software it is possible to compare situation of the solid Earth tide caused vertical displacements at the EUPOS® (EUREF) stations which are close to Struve arc within region from Artic Ocean till Black Sea. Scientific staff of LU GGI is looking forward for eventual participation in cooperation and science projects. Supported by ERAF Project 010/0202/2DP/2.1.1.2.0/10/APIA/VIAA/013

  4. 76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations

    Science.gov (United States)

    2011-12-30

    ... guidelines in identifying suitable candidate sites for nuclear power stations. The decision that a station... combination and a cost-benefit analysis comparing it with alternative site-plant combinations, as discussed in...

  5. Studying dynamics of indicators of nuclear power stations exploitation (the case of US nuclear power stations)

    OpenAIRE

    Varshavsky, Leonid

    2013-01-01

    Analysis of external and internal factors influencing significant improvement of economic indicators of US nuclear power stations in the 1990s is carried out. Approaches to modeling dynamics of capacity factors of nuclear power stations are proposed. Comparative analysis of dynamics of capacity factors and occupational radiation exposure for various generations of US nuclear power plants is carried out. Dynamical characteristics of «learning by doing» effects for analyzed indicators are measu...

  6. Secure base stations

    NARCIS (Netherlands)

    Bosch, Peter; Brusilovsky, Alec; McLellan, Rae; Mullender, Sape J.; Polakos, Paul

    2009-01-01

    With the introduction of the third generation (3G) Universal Mobile Telecommunications System (UMTS) base station router (BSR) and fourth generation (4G) base stations, such as the 3rd Generation Partnership Project (3GPP) Long Term Evolution (LTE) Evolved Node B (eNB), it has become important to

  7. INTERACT Station Catalogue - 2015

    DEFF Research Database (Denmark)

    INTERACT stations are located in all major environmental envelopes of the Arctic providing an ideal platform for studying climate change and its impact on the environment and local communities. Since alpine environments face similar changes and challenges as the Arctic, the INTERACT network also ...... catalogue includes descriptions of 73 research stations included in the network at the time of printing....

  8. Meyrin Petrol Station

    CERN Multimedia

    2006-01-01

    Please note that the Meyrin petrol station will be closed for maintenance work on Tuesday 19 and Wednesday 20 December 2006. If you require petrol during this period we invite you to use the Prévessin petrol station, which will remain open. TS-IC-LO Section Tel.: 77039 - 73793

  9. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    Solito, J.

    1978-04-01

    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt

  10. SPS rectifier stations

    CERN Multimedia

    CERN PhotoLab

    1974-01-01

    The first of the twelves SPS rectifier stations for the bending magnets arrived at CERN at the end of the year. The photograph shows a station with the rectifiers on the left and in the other three cubicles the chokes, capacitors and resistor of the passive filter.

  11. Ondergronds Station Blijdorp, Rotterdam

    NARCIS (Netherlands)

    Hijma, M.P.|info:eu-repo/dai/nl/266562426; Cohen, K.M.|info:eu-repo/dai/nl/185633374

    2014-01-01

    Het is in de herfst van 2005. Een lief meisje, Marieke, rijdt op haar vouwfiets door Rotterdam. Bij het Centraal Station is het al tijden een grote bouwplaats. Onder de nieuwe hal komt een veel groter metrostation en ook onder de Statenweg in Blijdorp is een grote bouwput voor een nieuw station.

  12. [STEM on Station Education

    Science.gov (United States)

    Lundebjerg, Kristen

    2016-01-01

    The STEM on Station team is part of Education which is part of the External Relations organization (ERO). ERO has traditional goals based around BHAG (Big Hairy Audacious Goal). The BHAG model is simplified to a saying: Everything we do stimulates actions by others to advance human space exploration. The STEM on Station education initiate is a project focused on bringing off the earth research and learning into classrooms. Educational resources such as lesson plans, activities to connect with the space station and STEM related contests are available and hosted by the STEM on Station team along with their partners such as Texas Instruments. These educational activities engage teachers and students in the current happenings aboard the international space station, inspiring the next generation of space explorers.

  13. Central Station Design Options

    DEFF Research Database (Denmark)

    2011-01-01

    . The work identifies the architecture, sizing and siting of prospective Central Stations in Denmark, which can be located at shopping centers, large car parking lots or gas stations. Central Stations are planned to be integrated in the Danish distribution grid. The Danish island of Bornholm, where a high...... overloading, more reference points might be necessary to represent various transformer loading levels. The subject of safety in Central Station is also addressed. A number of safety rules based on European standards apply to AC charging equipment up to 44 kW. The connection interlock and the automatic de......-energization are identified as fundamental requirements for safety in such a charging station. The connection interlock is a solution which ensures that no power is applied to the DC cable when the EV connector is not connected. The automatic de-energization device ensures that whenever a strain on the cable is detected, e...

  14. Space station operations management

    Science.gov (United States)

    Cannon, Kathleen V.

    1989-01-01

    Space Station Freedom operations management concepts must be responsive to the unique challenges presented by the permanently manned international laboratory. Space Station Freedom will be assembled over a three year period where the operational environment will change as significant capability plateaus are reached. First Element Launch, Man-Tended Capability, and Permanent Manned Capability, represent milestones in operational capability that is increasing toward mature operations capability. Operations management concepts are being developed to accomodate the varying operational capabilities during assembly, as well as the mature operational environment. This paper describes operations management concepts designed to accomodate the uniqueness of Space Station Freedoom, utilizing tools and processes that seek to control operations costs.

  15. Waste Transfer Stations

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund

    2011-01-01

    tion and transport is usually the most costly part of any waste management system; and when waste is transported over a considerable distance or for a long time, transferring the waste from the collection vehicles to more efficient transportation may be economically beneficial. This involves...... a transfer station where the transfer takes place. These stations may also be accessible by private people, offering flexibility to the waste system, including facilities for bulky waste, household hazardous waste and recyclables. Waste transfer may also take place on the collection route from small...... describes the main features of waste transfer stations, including some considerations about the economical aspects on when transfer is advisable....

  16. Lifetime management of Magnox power stations

    International Nuclear Information System (INIS)

    Smitton, C.

    1998-01-01

    Magnox Electric, which is, a subsidiary of BNFL, operates six nuclear power plants that have an average age of about 33 years. The procedures developed to maintain the plants and ensure nuclear safety in longer-term operation are reviewed. The technical limit on station lifetimes is expected to be determined by the effect of ageing on major reactor structures where replacement is impractical. Examination of the effect of ageing confirms that the stations are capable of operating to a life of at least 40 years. The economic factors affecting operation are reviewed, recognising the need to sell electricity in a competitive market. Recently Magnox Electric and BNFL have merged and all plant supporting Magnox operations are now within a single integrated company that will provide further opportunities for improved efficiency. (author)

  17. Dynamics and control in nuclear power stations

    International Nuclear Information System (INIS)

    Butterfield, M.H.

    1992-01-01

    This volume presents a wide view of aspects of control of nuclear power stations by taking into consideration the plant as a whole and the protection systems employed therein. Authors with worldwide experience consider all aspects of dynamics and control in the context of both fast and thermal power stations. The topics discussed include the methods of development and applications within the analysis of plant behaviour, the validation of mathematical models, plant testing, and the design and implementation of controls. There are 27 papers all of which are indexed separately; steady states and model evolution (5 papers), control and protection systems (5 papers), transients (7 papers), testing and data (3 papers), model validation (6 papers) and commissioning and operation (1 paper). (author)

  18. "Central Station" Londonis

    Index Scriptorium Estoniae

    2000-01-01

    Londoni galeriis Milch seitsme läti, leedu ja eesti kunstniku projekt "Central Station". Kuraatorid Lisa Panting, Sally Tallant. Eestist osalevad Hanno Soans (Catarina Campinoga koostöös valminud video), Kiwa, Kai Kaljo

  19. Materials Test Station

    Data.gov (United States)

    Federal Laboratory Consortium — When completed, the Materials Test Station at the Los Alamos Neutron Science Center will meet mission need. MTS will provide the only fast-reactor-like irradiation...

  20. Active Marine Station Metadata

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Active Marine Station Metadata is a daily metadata report for active marine bouy and C-MAN (Coastal Marine Automated Network) platforms from the National Data...

  1. Electrostatic pickup station

    CERN Multimedia

    CERN PhotoLab

    1982-01-01

    Electrostatic pickup station, with 4 interleaved electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TT70, TTL2). See also 7904075.

  2. Public Transit Stations

    Data.gov (United States)

    Department of Homeland Security — fixed rail transit stations within the Continental United States, Alaska, Hawaii, the District of Columbia, and Puerto Rico. The modes of transit that are serviced...

  3. Mukilteo Research Station

    Data.gov (United States)

    Federal Laboratory Consortium — Research at the Mukilteo Research Station focuses on understanding the life cycle of marine species and the impacts of ecosystem stressors on anadromous and marine...

  4. Maine Field Station

    Data.gov (United States)

    Federal Laboratory Consortium — In 2000 NOAA's National Marine Fisheries Service established the Maine Field Station in Orono, ME to have more direct involvement in the conservation of the living...

  5. FEMA DFIRM Station Start

    Data.gov (United States)

    Minnesota Department of Natural Resources — This table contains information about station starting locations. These locations indicate the reference point that was used as the origin for distance measurements...

  6. Natural Weathering Exposure Station

    Data.gov (United States)

    Federal Laboratory Consortium — The Corps of Engineers' Treat Island Natural Weathering Exposure Station is a long-term natural weathering facility used to study concrete durability. Located on the...

  7. Routes and Stations

    Data.gov (United States)

    Department of Homeland Security — he Routes_Stations table is composed of fixed rail transit systems within the Continental United States, Alaska, Hawaii, the District of Columbia, and Puerto Rico....

  8. USRCRN Station Information

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Documentation of United States Regional Climate Reference Network (USRCRN) installations in 2009. Installations documented are for USRCRN pilot project stations in...

  9. Nuclear safeguards control in nuclear power stations

    International Nuclear Information System (INIS)

    Boedege, R.; Braatz, U.; Heger, H.

    1976-01-01

    The execution of the Non-Proliferation Treaty (NPT) has initiated a third phase in the efforts taken to ensure peace by limiting the number of atomic powers. In this phase it is important, above all, to turn into workable systems the conditions imposed upon technology by the different provisions of the Verification Agreement of the NPT. This is achieved mainly by elaborating annexes to the Agreement specifically geared to certain model plants, typical representatives selected for LWR power stations being the plants at Garigliano, Italy (BWR), and Stade, Federal Republic of Germany (PWR). The surveillance measures taken to prevent any diversion of special nuclear material for purposes of nuclear weapons manufacture must be effective in achieving their specific objective and must not impede the circumspect management of operations of the plants concerned. A VDEW working party has studied the technical details of the planned surveillance measures in nuclear power stations in the Federal Republic of Germany and now presents a concept of material balancing by units which meets the conditions imposed by the inspection authority and could also be accepted by the operators of nuclear power stations. The concept provides for uninterrupted control of the material balance areas of the nuclear power stations concerned, allows continuous control of the whole nuclear fuel cycle, is based exclusively on existing methods and facilities, and can be implemented at low cost. (orig.) [de

  10. Gas Stations, US, 2010, NAVTEQ

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Gas_Stations dataset is derived from the Navteq 'AUTOSVC' SDC layer (FAC_TYPE=5540) and contains gas stations and petrol stations. This NAVTEQ dataset is...

  11. Enhanced Master Station History Report

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Enhanced Master Station History Report (EMSHR) is a compiled list of basic, historical information for every station in the station history database, beginning...

  12. Space Station galley design

    Science.gov (United States)

    Trabanino, Rudy; Murphy, George L.; Yakut, M. M.

    1986-01-01

    An Advanced Food Hardware System galley for the initial operating capability (IOC) Space Station is discussed. Space Station will employ food hardware items that have never been flown in space, such as a dishwasher, microwave oven, blender/mixer, bulk food and beverage dispensers, automated food inventory management, a trash compactor, and an advanced technology refrigerator/freezer. These new technologies and designs are described and the trades, design, development, and testing associated with each are summarized.

  13. Leadership at Antarctic Stations.

    Science.gov (United States)

    1987-03-01

    Claseification 6. No. Pegees LEADERSHIP AT ANTARTIC STATIONS hxIs i4 5, C =r~eta(C), 17 Rfs~W (R, Udusiied U)J 7. No Refs 8. Author(s) Edocumesnt I...whether there is a "best" approach to leadership at an Antartic Station and what leadership style may have the most to offer. 3~~ __ ___ Tipesis to be

  14. National Seismic Station

    International Nuclear Information System (INIS)

    Stokes, P.A.

    1982-06-01

    The National Seismic Station was developed to meet the needs of regional or worldwide seismic monitoring of underground nuclear explosions to verify compliance with a nuclear test ban treaty. The Station acquires broadband seismic data and transmits it via satellite to a data center. It is capable of unattended operation for periods of at least a year, and will detect any tampering that could result in the transmission of unauthentic seismic data

  15. Spent fuel canister docking station

    International Nuclear Information System (INIS)

    Suikki, M.

    2006-01-01

    The working report for the spent fuel canister docking station presents a design for the operation and structure of the docking equipment located in the fuel handling cell for the spent fuel in the encapsulation plant. The report contains a description of the basic requirements for the docking station equipment and their implementation, the operation of the equipment, maintenance and a cost estimate. In the designing of the equipment all the problems related with the operation have been solved at the level of principle, nevertheless, detailed designing and the selection of final components have not yet been carried out. In case of defects and failures, solutions have been considered for postulated problems, and furthermore, the entire equipment was gone through by the means of systematic risk analysis (PFMEA). During the docking station designing we came across with needs to influence the structure of the actual disposal canister for spent nuclear fuel, too. Proposed changes for the structure of the steel lid fastening screw were included in the report. The report also contains a description of installation with the fuel handling cell structures. The purpose of the docking station for the fuel handling cell is to position and to seal the disposal canister for spent nuclear fuel into a penetration located on the cell floor and to provide suitable means for executing the loading of the disposal canister and the changing of atmosphere. The designed docking station consists of a docking ring, a covering hatch, a protective cone and an atmosphere-changing cap as well as the vacuum technology pertaining to the changing of atmosphere and the inert gas system. As far as the solutions are concerned, we have arrived at rather simple structures and most of the actuators of the system are situated outside of the actual fuel handling cell. When necessary, the equipment can also be used for the dismantling of a faulty disposal canister, cut from its upper end by machining. The

  16. The Princess Elisabeth Station

    Science.gov (United States)

    Berte, Johan

    2012-01-01

    Aware of the increasing impact of human activities on the Earth system, Belgian Science Policy Office (Belspo) launched in 1997 a research programme in support of a sustainable development policy. This umbrella programme included the Belgian Scientific Programme on Antarctic Research. The International Polar Foundation, an organization led by the civil engineer and explorer Alain Hubert, was commissioned by the Belgian Federal government in 2004 to design, construct and operate a new Belgian Antarctic Research Station as an element under this umbrella programme. The station was to be designed as a central location for investigating the characteristic sequence of Antarctic geographical regions (polynia, coast, ice shelf, ice sheet, marginal mountain area and dry valleys, inland plateau) within a radius of 200 kilometers (approx.124 miles) of a selected site. The station was also to be designed as "state of the art" with respect to sustainable development, energy consumption, and waste disposal, with a minimum lifetime of 25 years. The goal of the project was to build a station and enable science. So first we needed some basic requirements, which I have listed here; plus we had to finance the station ourselves. Our most important requirement was that we decided to make it a zero emissions station. This was both a philosophical choice as we thought it more consistent with Antarctic Treaty obligations and it was also a logistical advantage. If you are using renewable energy sources, you do not have to bring in all the fuel.

  17. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    Pasquini, L.A.

    1986-01-01

    The purpose of the Shippingport Station Decommissioning Project (SSDP) is to place the Shippingport Atomic Power Station in a long-term radiologically safe condition following defueling of the reactor, to perform decommissioning in such a manner as to demonstrate to the nuclear industry the application of decommissioning procedures to a large scale nuclear power plant, and to provide useful planning data for future decommissioning projects. This paper describes the Technology Transfer Program for collecting and archiving the decommissioning data base and its availability to the nuclear industry

  18. Small hydroelectric power stations and their reality

    International Nuclear Information System (INIS)

    Kamenski, Miroslav

    1999-01-01

    Construction of a small hydroelectric power station provides additional amounts of electric energy, engages a private capital, revives investment activities and promotes the use of renewable energy sources. Transmission losses are reduced, a voltage of higher quality is achieved and idle power is compensated by the generation of electricity in the small hydroelectric power stations and at the place of consumption. Legislation and technical regulations, however, require a multidisciplinary approach, defining of complex spaces and environmental protection. Unfortunately, complete documents should be prepared for small,hydroelectric plants just as for big ones what is a long procedure and many of those papers are unnecessary or even superfluous. (Author)

  19. Development of a geodatabase and conceptual model of the hydrogeologic units beneath air force plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas

    Science.gov (United States)

    Shah, Sachin D.

    2004-01-01

    Air Force Plant 4 and adjacent Naval Air Station-Joint Reserve Base Carswell Field at Fort Worth, Texas, constitute a government-owned, contractor-operated facility that has been in operation since 1942. Contaminants from AFP4, primarily volatile organic compounds and metals, have entered the ground-water-flow system through leakage from waste-disposal sites and from manufacturing processes. The U.S. Geological Survey developed a comprehensive geodatabase of temporal and spatial environmental information associated with the hydrogeologic units (alluvial aquifer, Goodland-Walnut confining unit, and Paluxy aquifer) beneath the facility and a three-dimensional conceptual model of the hydrogeologic units integrally linked to the geodatabase. The geodatabase design uses a thematic layer approach to create layers of feature data using a geographic information system. The various features are separated into relational tables in the geodatabase on the basis of how they interact and correspond to one another. Using the geodatabase, geographic data at the site are manipulated to produce maps, allow interactive queries, and perform spatial analyses. The conceptual model for the study area comprises computer-generated, three-dimensional block diagrams of the hydrogeologic units. The conceptual model provides a platform for visualization of hydrogeologic-unit sections and surfaces and for subsurface environmental analyses. The conceptual model is based on three structural surfaces and two thickness configurations of the study area. The three structural surfaces depict the altitudes of the tops of the three hydrogeologic units. The two thickness configurations are those of the alluvial aquifer and the Goodland-Walnut confining unit. The surface of the alluvial aquifer was created using a U.S. Geological Survey 10-meter digital elevation model. The 2,130 point altitudes of the top of the Goodland-Walnut unit were compiled from lithologic logs from existing wells, available soil

  20. Drought Tip: Keeping Plants Alive under Drought or Water Restrictions

    OpenAIRE

    Hartin, Janet; Oki, Loren; Fujino, Dave; Faber, Ben

    2015-01-01

    Plants that don't receive enough water eventually show signs of water stress. During a drought or under water restrictions aimed at water conservation, keeping plants alive can be particularly difficult.

  1. Shippingport Atomic Power Station. Quarterly operating report, third quarter 1978

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1978-01-01

    A loss of ac power to the station occurred on July 28, 1978 caused by an interaction between Beaver Valley Power Station and Shippingport Atomic Power Station when the main transformer of Unit No. 1 of the Beaver Valley Power Station developed an internal failure and tripped the BVPS. Two environmental studies were continued this quarter. The first involves reduction of main unit condenser chlorination and the second, river intake screen fish impingement sampling. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. During the third quarter of 1978, 874 cubic feet of radioactive solid waste was shipped out of state for burial. At the end of the quarter, the Fall shutdown continued with the plant heated up, the main turbine on turning gear and plant testing in progress prior to Station startup.

  2. Catawba nuclear station preoperational ALARA review

    International Nuclear Information System (INIS)

    Deal, W.P.

    1985-01-01

    This paper describes the particular emphasis placed on preoperational as los as reasonably achievable (ALARA) considerations at Duke Power's Catawba Nuclear Station. A strong station commitment to the ALARA philosophy, and review of existing capabilities, led to development of an aggressive two-part ALARA program. Capabilities consisted of sufficient numbers of available personnel, lengthy lead time during construction, a very detailed plastic model, and a sister plant of similar design. The program, as developed, consisted of a preoperational program, which looked at design and construction aspects of ALARA, and the operational program, dealing with the ALARA committee and operational problems. MAnagement's philosophy of holding everyone responsible for ALARA provided the motivation to organize the preoperational program to use that resource. The Health Physics group accepted responsibility for development, coordination, and reviewer training. The problem provided a base to build on as station personnel gained experience in their own crafts and radiation protection in general

  3. Balakovo nuclear power station

    International Nuclear Information System (INIS)

    1996-01-01

    A key means of improving the safety and reliability of nuclear power plants is through effective training of plant personnel. The goal of this paper is to show the progress of the training at the Balakovo Nuclear Power Plant, and the important role that international cooperation programs have played in that progress

  4. Hydrogen Fuelling Stations

    DEFF Research Database (Denmark)

    Rothuizen, Erasmus Damgaard

    . A system consisting of one high pressure storage tank is used to investigate the thermodynamics of fuelling a hydrogen vehicle. The results show that the decisive parameter for how the fuelling proceeds is the pressure loss in the vehicle. The single tank fuelling system is compared to a cascade fuelling......This thesis concerns hydrogen fuelling stations from an overall system perspective. The study investigates thermodynamics and energy consumption of hydrogen fuelling stations for fuelling vehicles for personal transportation. For the study a library concerning the components in a hydrogen fuelling...... station has been developed in Dymola. The models include the fuelling protocol (J2601) for hydrogen vehicles made by Society of Automotive Engineers (SAE) and the thermodynamic property library CoolProp is used for retrieving state point. The components in the hydrogen fuelling library are building up...

  5. Hydrogen vehicle fueling station

    Energy Technology Data Exchange (ETDEWEB)

    Daney, D.E.; Edeskuty, F.J.; Daugherty, M.A. [Los Alamos National Lab., NM (United States)] [and others

    1995-09-01

    Hydrogen fueling stations are an essential element in the practical application of hydrogen as a vehicle fuel, and a number of issues such as safety, efficiency, design, and operating procedures can only be accurately addressed by a practical demonstration. Regardless of whether the vehicle is powered by an internal combustion engine or fuel cell, or whether the vehicle has a liquid or gaseous fuel tank, the fueling station is a critical technology which is the link between the local storage facility and the vehicle. Because most merchant hydrogen delivered in the US today (and in the near future) is in liquid form due to the overall economics of production and delivery, we believe a practical refueling station should be designed to receive liquid. Systems studies confirm this assumption for stations fueling up to about 300 vehicles. Our fueling station, aimed at refueling fleet vehicles, will receive hydrogen as a liquid and dispense it as either liquid, high pressure gas, or low pressure gas. Thus, it can refuel any of the three types of tanks proposed for hydrogen-powered vehicles -- liquid, gaseous, or hydride. The paper discusses the fueling station design. Results of a numerical model of liquid hydrogen vehicle tank filling, with emphasis on no vent filling, are presented to illustrate the usefulness of the model as a design tool. Results of our vehicle performance model illustrate our thesis that it is too early to judge what the preferred method of on-board vehicle fuel storage will be in practice -- thus our decision to accommodate all three methods.

  6. Space Station Habitability Research

    Science.gov (United States)

    Clearwater, Yvonne A.

    1988-01-01

    The purpose and scope of the Habitability Research Group within the Space Human Factors Office at the NASA/Ames Research Center is described. Both near-term and long-term research objectives in the space human factors program pertaining to the U.S. manned Space Station are introduced. The concept of habitability and its relevancy to the U.S. space program is defined within a historical context. The relationship of habitability research to the optimization of environmental and operational determinants of productivity is discussed. Ongoing habitability research efforts pertaining to living and working on the Space Station are described.

  7. Process instrumentation for nuclear power station

    International Nuclear Information System (INIS)

    Yanai, Katsuya; Shinohara, Katsuhiko

    1978-01-01

    Nuclear power stations are the large scale compound system composed of many process systems. Accordingly, for the safe and high reliability operation of the plants, it is necessary to grasp the conditions of respective processes exactly and control the operation correctly. For this purpose, the process instrumentation undertakes the important function to monitor the plant operation. Hitachi Ltd. has exerted ceaseless efforts since long before to establish the basic technology for the process instrumentation in nuclear power stations, to develop and improve hardwares of high reliability, and to establish the quality control system. As for the features of the process instrumentation in nuclear power stations, the enormous quantity of measurement, the diversity of measured variables, the remote measurement and monitoring method, and the ensuring of high reliability are enumerated. Also the hardwares must withstand earthquakes, loss of coolant accidents, radiations, leaks and fires. Hitachi Unitrol Sigma Series is the measurement system which is suitable to the general process instrumentation in nuclear power stations, and satisfies sufficiently the basic requirements described above. It has various features as the nuclear energy system, such as high reliability by the use of ICs, the methods of calculation and transmission considering signal linkage, loop controller system and small size. HIACS-1000 Series is the analog controller of high reliability for water control. (Kako, I.)

  8. TEPCO plans to construct Higashidori Nuclear Power Station

    International Nuclear Information System (INIS)

    Tsuruta, Atsushi

    2008-01-01

    In 2006, TEPCO submitted to the government plans for the construction of Higashidori Nuclear Power Station. The application was filed 41 years after the project approved by the Higashidori Village Assembly. This nuclear power station will be the first new nuclear power plant constructed by TEPCO since the construction of Units No.6 and 7 at the Kashiwazaki Kariwa Nuclear Power Station 18 years ago. Higashidori Nuclear Power Station is to be constructed at a completely new site, which will become the fourth TEPCO nuclear power station. Higashidori Nuclear Power Station Unit No.1 will be TEPCO's 18th nuclear reactor. Unit No.1 will be an advanced boiling water reactor (ABWR), a reactor-type with a proven track record. It will be TEPCO's third ABWR. Alongside incorporating the latest technology, in Higashidori Nuclear Power Station Unit No.1, the most important requirement is for TEPCO to reflect in the new unit information and experience acquired from the operation of other reactors (information and experience acquired through the experience of operating TEPCO's 17 units at Fukushima Daiichi Nuclear Power Station, Fukushima Daini Nuclear Power Station and Kashiwazaki Kashiwa Nuclear Power Station in addition to information on non-conformities at nuclear power stations in Japan and around the world). Higashidori Nuclear Power Station is located in Higashidori-Village (Aomori Prefecture) and the selected site includes a rich natural environment. From an environmental perspective, we will implement the construction with due consideration for the land and sea environment, aiming to ensure that the plant can co-exist with its natural surroundings. The construction plans are currently being reviewed by the Nuclear and Industrial Safety Agency. We are committed to making progress in the project for the start of construction and subsequent commercial operation. (author)

  9. Wolf Creek Generating Station containment model

    International Nuclear Information System (INIS)

    Nguyen, D.H.; Neises, G.J.; Howard, M.L.

    1995-01-01

    This paper presents a CONTEMPT-LT/28 containment model that has been developed by Wolf Creek Nuclear Operating Corporation (WCNOC) to predict containment pressure and temperature behavior during the postulated events at Wolf Creek Generating Station (WCGS). The model has been validated using data provided in the WCGS Updated Safety Analysis Report (USAR). CONTEMPT-LT/28 model has been used extensively at WCGS to support plant operations, and recently, to support its 4.5% thermal power uprate project

  10. Physical degradation assessment of generator station cables

    International Nuclear Information System (INIS)

    Stonkus, D.J.

    1988-01-01

    Preliminary studies of fossil-fired and nuclear generator station cables indicate that the low voltage PVC insulated cables are in relatively good condition. The insulation is flexible and in the case of nuclear cables can withstand a design basis event after nearly 15 years of service. Cables insulated with styrene butadiene rubber have been found embrittled and cables insulated with SBR should be closely inspected in any plant assurance program. Thermal analysis using oxidative induction technique shows promise to indicate cable insulation degradation. Long term reliability assurance and plant life extension studies are being actively pursued at Ontario Hydro. A major study is currently underway to extend the life of the oldest operating fossil-fuel station, the 8-unit, 2400 MW Lakeview TGS in operation since the 1960s. Plant life assurance programs have been initiated at the 2000 MW Lambton TGS in operation since 1969, and for the oldest operating nuclear plant, Pickering NGS A in operation since the early 1970s. As cables are considered one of the critical components in a generator station due to the extreme difficulty and cost of cable replacement, test programs have been initiated to evaluate the physical degradation of the cables and relate the results to electrical diagnostic tests and to chemical changes. The decommissioning of two small nuclear stations, the 20 MW Nuclear Power Demonstration (NPD) and the 200 MW Douglas Point NGS, which were placed in service in 1962 and 1967 respectively, will provide an opportunity to perform destructive electrical and physical evaluation on field aged cables

  11. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1988-01-01

    US Department of Energy (DOE) Shippingport Station Decommissioning Project (SSDP) decommissioned, decontaminated, and dismantled the world's first, nuclear fueled, commercial size, electric power plant. SSDP programmatic goal direction for technology transfer is documentation of project management and operations experience. Objective is to provide future nuclear facility decommissioning projects with pertinent SSDP performance data for project assessment, planning, and operational implementation. This paper presents a working definition for technology transfer. Direction is provided for access and availability for SSDP technology acquisition

  12. Galileo Station Keeping Strategy

    Science.gov (United States)

    Perez-Cambriles, Antonio; Bejar-Romero, Juan Antonio; Aguilar-Taboada, Daniel; Perez-Lopez, Fernando; Navarro, Daniel

    2007-01-01

    This paper presents analyses done for the design and implementation of the Maneuver Planning software of the Galileo Flight Dynamics Facility. The station keeping requirements of the constellation have been analyzed in order to identify the key parameters to be taken into account in the design and implementation of the software.

  13. Designing a Weather Station

    Science.gov (United States)

    Roman, Harry T.

    2012-01-01

    The collection and analysis of weather data is crucial to the location of alternate energy systems like solar and wind. This article presents a design challenge that gives students a chance to design a weather station to collect data in advance of a large wind turbine installation. Data analysis is a crucial part of any science or engineering…

  14. Avoiding Service Station Fraud.

    Science.gov (United States)

    Burton, Grace M.; Burton, John R.

    1982-01-01

    High school students are warned against service station fraud. A problem-solving section is designed to help students calculate consumer costs for various fraudulent transactions. Several ways of reducing fraud or of lessening the chances of problems are noted. (MP)

  15. The Service Station.

    Science.gov (United States)

    Ohio State Univ., Columbus. Center for Vocational and Technical Education.

    The purpose of the teacher's guide is to encourage the primary student to expand his or her awareness of jobs within the community. The role of the service station worker is examined, with emphasis on the goods and services provided. Subject areas for which the materials in this guide have potential are social studies, art, and language. Each set…

  16. Electrostatic pickup station

    CERN Multimedia

    CERN PhotoLab

    1979-01-01

    Electrostatic pickup station, with 4 electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TTL2, TT70). See also 8206063, where the electrode shapes are clearly visible.

  17. Point Lepreau generating station

    International Nuclear Information System (INIS)

    Ganong, G.H.D.; Strang, A.E.; Gunter, G.E.; Thompson, T.S.

    Point Lepreau-1 reactor is a 600 MWe generating station expected to be in service by October 1979. New Brunswick is suffering a 'catch up' phenomenon in load growth and needs to decrease dependence on foreign oil. The site is on salt water and extensive study has gone into corrosion control. Project management, financing and scheduling have unique aspects. (E.C.B.)

  18. Mojave Base Station Implementation

    Science.gov (United States)

    Koscielski, C. G.

    1984-01-01

    A 12.2 meter diameter X-Y mount antenna was reconditioned for use by the crustal dynamic project as a fixed base station. System capabilities and characteristics and key performance parameters for subsystems are presented. The implementation is completed.

  19. Naturalization of landscaped parkland at Ontario Hydro's Nanticoke generating station

    International Nuclear Information System (INIS)

    McKenna, G.R.

    1998-01-01

    The implementation of a program for the naturalization of Nanticoke Park, a 30 hectare area located on the property of Ontario Hydro's Nanticoke Generating Station was discussed. The station, which is located in southern Ontario very near to noted wildlife areas, is the largest coal-fired generating station in North America. Naturalization of Nanticoke Park began with passive naturalization of interior areas. An active naturalization program involving four to five hectare size areas annually was begun in 1997, to be completed over a five -year period. This presentation described the site preparation, planting methods, post-planting tending methods, survival assessment of planted areas, and scientific research initiatives including mulch trials with zebra mussel shells to increase soil moisture. The lessons learned from the two year experiment in determining the optimum planting strategy and methods were described. 7 refs., 1 tab

  20. Hydrogen Filling Station

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-02-24

    Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. The Freedom CAR and Freedom FUEL initiatives emphasize the importance of hydrogen as a future transportation fuel. Presently, Las Vegas has one hydrogen fueling station powered by natural gas. However, the use of traditional sources of energy to produce hydrogen does not maximize the benefit. The hydrogen fueling station developed under this grant used electrolysis units and solar energy to produce hydrogen fuel. Water and electricity are furnished to the unit and the output is hydrogen and oxygen. Three vehicles were converted to utilize the hydrogen produced at the station. The vehicles were all equipped with different types of technologies. The vehicles were used in the day-to-day operation of the Las Vegas Valley Water District and monitoring was performed on efficiency, reliability and maintenance requirements. The research and demonstration utilized for the reconfiguration of these vehicles could lead to new technologies in vehicle development that could make hydrogen-fueled vehicles more cost effective, economical, efficient and more widely used. In order to advance the development of a hydrogen future in Southern Nevada, project partners recognized a need to bring various entities involved in hydrogen development and deployment together as a means of sharing knowledge and eliminating duplication of efforts. A road-mapping session was held in Las Vegas in June 2006. The Nevada State Energy Office, representatives from DOE, DOE contractors and LANL, NETL, NREL were present. Leadership from the National hydrogen Association Board of Directors also attended. As a result of this session, a roadmap for hydrogen development was created. This roadmap has the ability to become a tool for use by other road-mapping efforts in the hydrogen community. It could also become a standard template for other states or even countries to approach planning for a hydrogen

  1. Water Pumping Stations, File name = UTILITIES - PARTIAL Data is incomplete. Contains electric trans lines, electric substations, sewer plants, sewer pumpstations, water plants, water tanks http://www.harfordcountymd.gov/gis/Index.cfm, Published in 2011, 1:1200 (1in=100ft) scale, Harford County Government.

    Data.gov (United States)

    NSGIC Local Govt | GIS Inventory — Water Pumping Stations dataset current as of 2011. File name = UTILITIES - PARTIAL Data is incomplete. Contains electric trans lines, electric substations, sewer...

  2. Sewerage Pumping Stations, File name = UTILITIES - PARTIAL Data is incomplete. Contains electric trans lines, electric substations, sewer plants, sewer pumpstations, water plants, water tanks http://www.harfordcountymd.gov/gis/Index.cfm, Published in 2011, 1:600 (1in=50ft) scale, Harford County Government.

    Data.gov (United States)

    NSGIC Local Govt | GIS Inventory — Sewerage Pumping Stations dataset current as of 2011. File name = UTILITIES - PARTIAL Data is incomplete. Contains electric trans lines, electric substations, sewer...

  3. Mobile environmental radiation monitoring station

    International Nuclear Information System (INIS)

    Assido, H.; Shemesh, Y.; Mazor, T.; Tal, N.; Barak, D.

    1997-01-01

    A mobile environmental radiation monitoring station has been developed and established for the Israeli Ministry of Environment. The radiation monitoring station is ready for immediate placing in any required location, or can be operated from a vehicle. The station collects data Tom the detector and transfers it via cellular communication network to a Computerized Control Center for data storage, processing, and display . The mobile station is fully controlled from the. Routinely, the mobile station responses to the data request accumulated since the last communication session. In case of fault or alarm condition in the mobile station, a local claim is activated and immediately initiates communication with the via cellular communication network. (authors)

  4. Battery charging stations

    Energy Technology Data Exchange (ETDEWEB)

    Bergey, M.

    1997-12-01

    This paper discusses the concept of battery charging stations (BCSs), designed to service rural owners of battery power sources. Many such power sources now are transported to urban areas for recharging. A BCS provides the opportunity to locate these facilities closer to the user, is often powered by renewable sources, or hybrid systems, takes advantage of economies of scale, and has the potential to provide lower cost of service, better service, and better cost recovery than other rural electrification programs. Typical systems discussed can service 200 to 1200 people, and consist of stations powered by photovoltaics, wind/PV, wind/diesel, or diesel only. Examples of installed systems are presented, followed by cost figures, economic analysis, and typical system design and performance numbers.

  5. Corrective action baseline report for underground storage tanks 0439-U, 0440-U, 2073-U, 2074-U, and 2075-U at the East End Fuel Station, Buildings 9754 and 9754-2, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Facility ID No. 0-010117

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tanks (USTs) 0439-U, 0440-U, 2073-U, 2074-U, and 2075-U at the East End Fuel Station, Buildings 9754 and 9754-2 at the Oak Ridge Y-12 Plant. Progress in support of corrective action at the East End Fuel Station has included monitoring well installation, tank removal, and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the East End Fuel Station and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes a summary of additional monitoring well installation activities, the results of baseline groundwater sampling, a summary of tank removal activities, and the results of confirmatory soil sampling performed during tank removal. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

  6. MÉXICO EN UN EVENTUAL ACUERDO DE LIBRE COMERCIO DE LAS AMÉRICAS: PERSPECTIVAS Y APROXIMACIÓN DESDE LA HISTORIA ACTUAL

    Directory of Open Access Journals (Sweden)

    Carlos Nahuel Oddone

    2006-01-01

    Full Text Available En el texto se analiza la posición del Gobierno de México respecto de una eventual conformación del Área de Libre Comercio de las Américas, más conocida como el ALCA. La aproximación del estudio se hace desde lo que se ha denominado “historia actual”; en este sentido el TLCAN se constituye en una herramienta metodológica importante al momento de realizar las prospecciones del tema en cuestión. Asimismo, son analizados los problemas que existen hoy en el TLCAN y que difícilmente se solucionarán con el ALCA.

  7. International Space Station exhibit

    Science.gov (United States)

    2000-01-01

    The International Space Station (ISS) exhibit in StenniSphere at John C. Stennis Space Center in Hancock County, Miss., gives visitors an up-close look at the largest international peacetime project in history. Step inside a module of the ISS and glimpse how astronauts will live and work in space. Currently, 16 countries contribute resources and hardware to the ISS. When complete, the orbiting research facility will be larger than a football field.

  8. Virginia power nuclear power station engineer training program

    International Nuclear Information System (INIS)

    Williams, T.M.; Haberstroh-Timpano, S.

    1987-01-01

    In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

  9. Physical decommissioning of the Shippingport Atomic Power Station

    International Nuclear Information System (INIS)

    Crimi, F.P.

    1988-01-01

    The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

  10. Emergency Medical Service (EMS) Stations

    Data.gov (United States)

    Kansas Data Access and Support Center — EMS Locations in Kansas The EMS stations dataset consists of any location where emergency medical services (EMS) personnel are stationed or based out of, or where...

  11. Weigh-in-Motion Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  12. Automatic Traffic Recorder (ATR) Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  13. Factors influencing the decommissioning of large-scale nuclear plants

    International Nuclear Information System (INIS)

    Large, J.H.

    1988-01-01

    The decision-making process involving the decommissioning of the UK graphite moderated, gas-cooled nuclear power stations is complex. There are timing, engineering, waste disposal, cost and lost generation capacity factors to consider and the overall decision of when and how to proceed with decommissioning may include political and public tolerance dimensions. For the final stage of decommissioning the nuclear industry could either completely dismantle the reactor island leaving a green-field site or, alternatively, the reactor island could be maintained indefinitely with additional super- and substructure containment. At this time the first of these options, or deferred decommissioning, prevails and with this the nuclear industry has expressed considerable confidence that the technology required will become available with passing time, that acceptable radioactive waste disposal methods and facilities will be available and that the eventual costs of decommissioning will not escalate without restraint. If the deferred decommissioning strategy is wrong and it is not possible to completely dismantle the reactor islands a century into the future, then it may be too late to effect sufficient longer term containment to maintain the reactor hulks in a reliable condition. With respect to the final decommissioning of large-scale nuclear plant, it is concluded that the nuclear industry does not know quite how to do it, when it will be attempted and when it will be completed, and they do not know how much it will eventually cost. (author)

  14. Space Station fluid management logistics

    Science.gov (United States)

    Dominick, Sam M.

    1990-01-01

    Viewgraphs and discussion on space station fluid management logistics are presented. Topics covered include: fluid management logistics - issues for Space Station Freedom evolution; current fluid logistics approach; evolution of Space Station Freedom fluid resupply; launch vehicle evolution; ELV logistics system approach; logistics carrier configuration; expendable fluid/propellant carrier description; fluid carrier design concept; logistics carrier orbital operations; carrier operations at space station; summary/status of orbital fluid transfer techniques; Soviet progress tanker system; and Soviet propellant resupply system observations.

  15. Review of radioactive discharges from nuclear power stations

    International Nuclear Information System (INIS)

    1991-02-01

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report is a review of the arisings and concludes that suitable technologies exist, which if applied, could reduce discharges from nuclear power plants in England and Wales in line with the rest of Europe. (author)

  16. Thermal management of space stations

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    Thermal management aims at making full use of energy resources available in the space station to reduce energy consumption, waste heat rejection and the weight of the station. It is an extension of the thermal control. This discussion introduces the concept and development of thermal management, presents the aspects of thermal management and further extends its application to subsystems of the space station.

  17. Air and radiation monitoring stations

    CERN Multimedia

    AUTHOR|(SzGeCERN)582709

    2015-01-01

    CERN has around 100 monitoring stations on and around its sites. New radiation measuring stations, capable of detecting even lower levels of radiation, were installed in 2014. Two members of HE-SEE group (Safety Engineering and Environment group) in front of one of the new monitoring stations.

  18. Long-term performance of structures comprising nuclear power plants PART 1: Deterioration assessment of nuclear power station buildings PART 2: Long-term stability and the leak-tightness of reactor containments

    International Nuclear Information System (INIS)

    Pocock, D.C.; Worthington, J.C.; Oberpichler, R.; Van Exel, H.; Beukelmann, D.; Huth, R.; Rose, B.

    1990-01-01

    The objective of this research was to study the long-term performance of structures comprising nuclear power plants. The time period of interest for this study is 140 years (this figure is based on maximum periods of 40 years for operation and 100 years of storage). It was divided in two parts: - the first based on four UK nuclear power plants examine the principle deterioration mechanism of reinforced structure which is chloride ingress and carbonation penetration - the second based on 2 German nuclear power plants examine the long term behaviour of reinforced and prestressed concrete and also the corrosion of steel containments with particular reference on plastic seals and potential risk areas

  19. Subsurface occurrence and potential source areas of chlorinated ethenes identified using concentrations and concentration ratios, Air Force Plant 4 and Naval Air Station-Joint Reserve Base Carswell Field, Fort Worth, Texas

    Science.gov (United States)

    Garcia, C. Amanda

    2005-01-01

    The U.S. Geological Survey, in cooperation with the U.S. Air Force Aeronautical Systems Center, Environmental Management Directorate, conducted a study during 2003-05 to characterize the subsurface occurrence and identify potential source areas of the volatile organic compounds classified as chlorinated ethenes at U.S. Air Force Plant 4 (AFP4) and adjacent Naval Air Station-Joint Reserve Base Carswell Field (NAS-JRB) at Fort Worth, Texas. The solubilized chlorinated ethenes detected in the alluvial aquifer originated as either released solvents (tetrachloroethene [PCE], trichloroethene [TCE], and trans-1,2-dichloroethene [trans-DCE]) or degradation products of the released solvents (TCE, cis-1,2-dichloroethene [cis-DCE], and trans-DCE). The combined influences of topographic- and bedrock-surface configurations result in a water table that generally slopes away from a ground-water divide approximately coincident with bedrock highs and the 1-mile-long aircraft assembly building at AFP4. Highest TCE concentrations (10,000 to 920,000 micrograms per liter) occur near Building 181, west of Building 12, and at landfill 3. Highest PCE concentrations (500 to 920 micrograms per liter) occur near Buildings 4 and 5. Highest cis-DCE concentrations (5,000 to 710,000 micrograms per liter) occur at landfill 3. Highest trans-DCE concentrations (1,000 to 1,700 micrograms per liter) occur just south of Building 181 and at landfill 3. Ratios of parent-compound to daughter-product concentrations that increase in relatively short distances (tens to 100s of feet) along downgradient ground-water flow paths can indicate a contributing source in the vicinity of the increase. Largest increases in ratio of PCE to TCE concentrations are three orders of magnitude from 0.01 to 2.7 and 7.1 between nearby wells in the northeastern part of NAS-JRB. In the northern part of NAS-JRB, the largest increases in TCE to total DCE concentration ratios relative to ratios at upgradient wells are from 17 to

  20. Safety Distances for hydrogen filling stations

    Energy Technology Data Exchange (ETDEWEB)

    Matthijsen, A. J. C. M.; Kooi, E. S.

    2005-07-01

    In the Netherlands there is a growing interest in using natural gas as a transport fuel. The most important drivers behind this development are formed by poor inner city air quality and the decision to close several LPG filling stations. Dwellings are not allowed within the safety distances of 45 or 110 meters from the tanker filling point of these LPG stations, depending on the capacity of the station. Another driver is global warming. We are carrying out a study on station supply, compression, storage and filling for natural gas stations, and a similar, simultaneous study on hydrogen as a followup to our risk analysis for the hydrogen filling station in Amsterdam. Here, three buses drive on hydrogen as part of the European CUTE project. Driving on natural gas is an important step in the transition to cars on hydrogen. This study was commissioned by the Dutch Ministry of Spatial Planning, Housing and the Environment to advise on external safety aspects of future hydrogen filling stations. According to Dutch law homes may not be built within an individual risk contour of 10-6 per year of a dangerous object, such as a plant with hazardous materials or a filling station. An individual risk contour of 10-6 is represented by a line around a dangerous object that connects locations with an individual risk level of 10-6 per year. An individual 'located' within this contour line has a chance of one per million per year or more to be killed as a result of an accident caused by this object. The longest distance between the object and such a contour is called a 'safety distance'. A study on safety distances is now in progress for different kinds of hydrogen filling stations (e. g. gaseous and liquid hydrogen) and for different capacities, such as big, medium and small stations. The focus is on different kinds of hydrogen production and the hydrogen supply of the filling station. To decide on the design and supply of the hydrogen station, we examined the

  1. Station blackout calculations for Peach Bottom

    International Nuclear Information System (INIS)

    Hodge, S.A.

    1985-01-01

    A calculational procedure for the Station Blackout Severe Accident Sequence at Browns Ferry Unit One has been repeated with plant-specific application to one of the Peach Bottom Units. The only changes required in code input are with regard to the primary continment concrete, the existence of sprays in the secondary containment, and the size of the refueling bay. Combustible gas mole fractions in the secondary containment of each plant during the accident sequence are determined. It is demonstrated why the current state-of-the-art corium/concrete interaction code is inadequate for application to the study of Severe Accident Sequences in plants with the BWR MK I or MK II containment design

  2. Space station orbit maintenance

    Science.gov (United States)

    Kaplan, D. I.; Jones, R. M.

    1983-01-01

    The orbit maintenance problem is examined for two low-earth-orbiting space station concepts - the large, manned Space Operations Center (SOC) and the smaller, unmanned Science and Applications Space Platform (SASP). Atmospheric drag forces are calculated, and circular orbit altitudes are selected to assure a 90 day decay period in the event of catastrophic propulsion system failure. Several thrusting strategies for orbit maintenance are discussed. Various chemical and electric propulsion systems for orbit maintenance are compared on the basis of propellant resupply requirements, power requirements, Shuttle launch costs, and technology readiness.

  3. Capacity at Railway Stations

    DEFF Research Database (Denmark)

    Landex, Alex

    2011-01-01

    zone(s) the possible conflicts with other trains (also in the opposite direction) are taken into account leading to more trustworthy results. Although the UIC 406 methodology proposes that the railway network should be divided into line sections when trains turn around and when the train order...... is changed, this paper recommends that the railway lines are not always be divided. In case trains turn around on open (single track) line, the capacity consumption may be too low if a railway line is divided. The same can be the case if only few trains are overtaken at an overtaking station. For dead end...

  4. Submerged AUV Charging Station

    Science.gov (United States)

    Jones, Jack A.; Chao, Yi; Curtin, Thomas

    2014-01-01

    Autonomous Underwater Vehicles (AUVs) are becoming increasingly important for military surveillance and mine detection. Most AUVs are battery powered and have limited lifetimes of a few days to a few weeks. This greatly limits the distance that AUVs can travel underwater. Using a series of submerged AUV charging stations, AUVs could travel a limited distance to the next charging station, recharge its batteries, and continue to the next charging station, thus traveling great distances in a relatively short time, similar to the Old West “Pony Express.” One solution is to use temperature differences at various depths in the ocean to produce electricity, which is then stored in a submerged battery. It is preferred to have the upper buoy submerged a reasonable distance below the surface, so as not to be seen from above and not to be inadvertently destroyed by storms or ocean going vessels. In a previous invention, a phase change material (PCM) is melted (expanded) at warm temperatures, for example, 15 °C, and frozen (contracted) at cooler temperatures, for example, 8 °C. Tubes containing the PCM, which could be paraffin such as pentadecane, would be inserted into a container filled with hydraulic oil. When the PCM is melted (expanded), it pushes the oil out into a container that is pressurized to about 3,000 psi (approx equals 20.7 MPa). When a valve is opened, the high-pressure oil passes through a hydraulic motor, which turns a generator and charges a battery. The low-pressure oil is finally reabsorbed into the PCM canister when the PCM tubes are frozen (contracted). Some of the electricity produced could be used to control an external bladder or a motor to the tether line, such that depth cycling is continued for a very long period of time. Alternatively, after the electricity is generated by the hydraulic motor, the exiting low-pressure oil from the hydraulic motor could be vented directly to an external bladder on the AUV, such that filling of the bladder

  5. PlayStation purpura.

    Science.gov (United States)

    Robertson, Susan J; Leonard, Jane; Chamberlain, Alex J

    2010-08-01

    A 16-year-old boy presented with a number of asymptomatic pigmented macules on the volar aspect of his index fingers. Dermoscopy of each macule revealed a parallel ridge pattern of homogenous reddish-brown pigment. We propose that these lesions were induced by repetitive trauma from a Sony PlayStation 3 (Sony Corporation, Tokyo, Japan) vibration feedback controller. The lesions completely resolved following abstinence from gaming over a number of weeks. Although the parallel ridge pattern is typically the hallmark for early acral lentiginous melanoma, it may be observed in a limited number of benign entities, including subcorneal haematoma.

  6. Tether applications for space station

    Science.gov (United States)

    Nobles, W.

    1986-01-01

    A wide variety of space station applications for tethers were reviewed. Many will affect the operation of the station itself while others are in the category of research or scientific platforms. One of the most expensive aspects of operating the space station will be the continuing shuttle traffic to transport logistic supplies and payloads to the space station. If a means can be found to use tethers to improve the efficiency of that transportation operation, it will increase the operating efficiency of the system and reduce the overall cost of the space station. The concept studied consists of using a tether to lower the shuttle from the space station. This results in a transfer of angular momentum and energy from the orbiter to the space station. The consequences of this transfer is studied and how beneficial use can be made of it.

  7. Operation and management of United Central Piping LPG supply stations in Shenzhen

    Energy Technology Data Exchange (ETDEWEB)

    Lai Yankai

    1997-11-01

    Shenzhen has based its city gas development project on the eventual conversion to natural gas supply by way of central piping LPG supply stations. To fully exploit the potential gas supply capability of every central piping station and cut down the total running cost, we have been connecting the existing supply stations and their piping system into a network, which not only provided a more reliable gas supply performance, but can greatly simplify the evacuation of gas stations from the ever-expanding downtown areas to suburbs. Through this way, the periodic gas stock held by individual stations can be transferred to storage terminal or stations of enough holding capability; the supplying distance has been much lengthened and the gas volume held in the piping system increased; gas supply covered by small stations has been shifted to new and large stations. By linking these stations, we are able to provide pipeline LP gas supply for a large area, and in the same time lay down the pipeline infrastructure for the upcoming LNG supply so that an easy conversion to LNG supply can be secured as soon as the projected LNG terminal is put to service. (au)

  8. Operation of the UK Magnox Stations in a competitive market

    International Nuclear Information System (INIS)

    Corrigan, A.

    2000-01-01

    In 1955 the UK Government announced the first major civil nuclear power plant construction programme based on the Magnox design of reactor. This was followed in 1956 with the commencement of operation of Calder Hall, the world's first nuclear power station. The initial programme was for the construction of 1 500-2 000 MW of plant but, with the success of the early stations, this was increased to 5 000 MW by 1960. In total 11 Magnox nuclear power stations were commissioned in the UK over the period 1956 to 1971, comprising a total of 26 reactors (see Table 1). At present 20 of the reactors remain in operation, with an average life of 37 years. Output from the stations has been steady for many years and they have been regarded as the workhorses of the electricity generation industry in the UK. In 1990 the electricity supply and distribution system was deregulated and a market system introduced which has led to a reduction in the sale price of electricity. In addition to this it has been necessary to invest in the plants to maintain safety levels and operational reliability. The plant's can only continue in operation provided they remain safe and economic. This paper will review recent experience with the life management of the Magnox stations. (author)

  9. Safety planning for nuclear power stations

    International Nuclear Information System (INIS)

    Tadmor, J.

    1979-01-01

    The article shows that compared to the many industries and other human activities, nuclear power stations are among the safest. A short description of the measures taken to prevent accidents and of the additional safety means entering into action if an accident does occur is presented. It is shown that in nuclear plants the death frequency following malfunctioning is 1 death in 100.000 years whereas deaths following other human activities is 1 in 2 to 100 years and following natural calamities like earthquakes and floods is 1 in 10 years. As an example it is shown that for a population of 15.000.000 living in a radius of 40 km around 100 power stations the average number of deaths will be of 2 per year as compared to 4200 from road accidents with the corresponding number of injuries of 20 and 375.000 respectively. (B.G.)

  10. Draper Station Analysis Tool

    Science.gov (United States)

    Bedrossian, Nazareth; Jang, Jiann-Woei; McCants, Edward; Omohundro, Zachary; Ring, Tom; Templeton, Jeremy; Zoss, Jeremy; Wallace, Jonathan; Ziegler, Philip

    2011-01-01

    Draper Station Analysis Tool (DSAT) is a computer program, built on commercially available software, for simulating and analyzing complex dynamic systems. Heretofore used in designing and verifying guidance, navigation, and control systems of the International Space Station, DSAT has a modular architecture that lends itself to modification for application to spacecraft or terrestrial systems. DSAT consists of user-interface, data-structures, simulation-generation, analysis, plotting, documentation, and help components. DSAT automates the construction of simulations and the process of analysis. DSAT provides a graphical user interface (GUI), plus a Web-enabled interface, similar to the GUI, that enables a remotely located user to gain access to the full capabilities of DSAT via the Internet and Webbrowser software. Data structures are used to define the GUI, the Web-enabled interface, simulations, and analyses. Three data structures define the type of analysis to be performed: closed-loop simulation, frequency response, and/or stability margins. DSAT can be executed on almost any workstation, desktop, or laptop computer. DSAT provides better than an order of magnitude improvement in cost, schedule, and risk assessment for simulation based design and verification of complex dynamic systems.

  11. Wind turbine power stations

    International Nuclear Information System (INIS)

    Anon.

    1992-11-01

    The Countryside Council for Wales (CCW's) policy on wind turbine power stations needs to be read in the context of CCW's document Energy:Policy and perspectives for the Welsh countryside. This identifies four levels of action aimed at reducing emission of gases which contribute towards the risk of global warming and gases which cause acid deposition. These are: the need for investment in energy efficiency; the need for investment in conventional power generation in order to meet the highest environmental standards; the need for investment in renewable energy; and the need to use land use transportation policies and decisions to ensure energy efficiency and energy conservation. CCW views wind turbine power stations, along with other renewable energy systems, within this framework. CCW's policy is to welcome the exploitation of renewable energy sources as an element in a complete and environmentally sensitive energy policy, subject to the Environmental Assessment of individual schemes and monitoring of the long-term impact of the various technologies involved. (Author)

  12. Design of photovoltaic central power station concentrator array

    Energy Technology Data Exchange (ETDEWEB)

    1984-02-01

    A design for a photovoltaic central power station using tracking concentrators has been developed. The 100 MW plant is assumed to be located adjacent to the Saguaro Power Station of Arizona Public Service. The design assumes an advanced Martin Marietta two-axis tracking fresnel lens concentrator. The concentrators are arrayed in 5 MW subfields, each with its own power conditioning unit. The photovoltaic plant output is connected to the existing 115 kV switchyard. The site specific design allows detailed cost estimates for engineering, site preparation, and installation. Collector and power conditioning costs have been treated parametrically.

  13. Planning and preparedness for radiological emergencies at nuclear power stations

    International Nuclear Information System (INIS)

    Thomson, R.; Muzzarelli, J.

    1996-01-01

    The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

  14. Milliken Station Demonstration Project FDG retrofit update

    Energy Technology Data Exchange (ETDEWEB)

    Alder, R.C.; Jackson, C.E.; O`Dea, D.T. [and others

    1994-12-31

    The Milliken Clean Coal Demonstration Project is one of the nine Clean Coal Projects selected for funding in Round 4 of the U.S. DOE`s Clean Coal Demonstration Program. The project`s sponsor is New York State Electric and Gas Corporation (NYSEG). Project team members include CONSOL Inc., Saarberg-Holter-Umwelttechnik (SHU), NALCO/FuelTech, Stebbins Engineering and Manufacturing Co., DHR Technologies, and CE Air Preheater. Gilbert/Commonwealth is the Architect/Engineer and Construction Manager for the flue gas desulfurization (FGD) retrofit. The project will provide full-scale demonstration of a combination of innovative emission-reducing technologies and plant upgraded for the control of sulfur dioxide (SO{sub 2}) and nitrogen oxides (NO{sub x}) emissions from a coal-fired steam generator without a significant loss of station efficiency. The overall project goals are the following: 98% SO{sub 2} removal efficiency using limestone while burning high sulfur coal; up to 70% NO{sub x} reduction using the NOXOUT selective non-catalytic reduction (SNCR) technology in conjunction with combustion modifications; minimization of solid waste by producing marketable by-products including commercial grade gypsum, calcium chloride, and fly ash; zero wastewater discharge; maintenance of station efficiency by using a high efficiency heat-pipe air heater system and a low-power-consuming scrubber system. The demonstration project is being conducted at NYSEG`s Milliken Station, located in Lansing, New York. Milliken Station has two 150-MWe pulverized coal-fired units built in the 1950s by Combustion Engineering. The SHU FGD process and the combustion modifications are being installed on both units, but the NOXOUT process, Plant Economic Optimization Advisor (PEOA), and the high-efficiency air heater system will be installed on only one unit.

  15. Power station simulators

    International Nuclear Information System (INIS)

    Zanobetti

    1989-01-01

    The number and the variety of simulators have gown to such an extent that it has become necessary to classify the numerous types now available. Simulators are of paramount importance for the design of nuclear power plants, for optimizing their efficiency and for the training of their operators: factors that contribute to their overall security. This book contains chapters on the following subjects: the development of power plant simulators, the components and classification of simulators, simulator technology, simulator performance and problems in simulator training

  16. Modular power station

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, T; Kanazawa, T

    1979-03-19

    In order to shorten the construction period of powerstations, to reduce the number of specialists at site and to prevent technical breakdowns, it was proposed that considerable parts of the powerstation should be assembled on a floating platform and then be towed to site by water, where they are set on foundations and then connected. It is now proposed that the necessary additional equipment (such as water supply plant, storage plant, Diesel generator and service buildings etc.) should be assembled on a second platform, and also transported by water on this. This modular construction will also reduce costs.

  17. Shippingport station decommissioning project ALARA Program

    Energy Technology Data Exchange (ETDEWEB)

    Crimi, F.P. [Lockheed Environmental Systems and Technology Co., Houston, TX (United States)

    1995-03-01

    Properly planned and implemented ALARA programs help to maintain nuclear worker radiation exposures {open_quotes}As Low As Reasonably Achievable.{close_quotes}. This paper describes the ALARA program developed and implemented for the decontamination and decommissioning (D&D) of the Shippingport Atomic Power Station. The elements required for a successful ALARA program are discussed along with examples of good ALARA practices. The Shippingport Atomic Power Station (SAPS) was the first commercial nuclear power plant to be built in the United States. It was located 35 miles northwest of Pittsburgh, PA on the south bank of the Ohio river. The reactor plant achieved initial criticality in December 1959. During its 25-year life, it produced 7.5 billion kilowatts of electricity. The SAPS was shut down in October 1982 and was the first large-scale U.S. nuclear power plant to be totally decommissioned and the site released for unrestricted use. The Decommission Project was estimated to take 1,007 man-rem of radiation exposure and $.98.3 million to complete. Physical decommissioning commenced in September 1985 and was completed in September 1989. The actual man-rem of exposure was 155. The project was completed 6 months ahead of schedule at a cost of $91.3 million.

  18. Innovative Railway Stations

    Science.gov (United States)

    Rzepnicka, Sylwia; Załuski, Daniel

    2017-10-01

    In relation to modern demographic trends, evolving technologies and environment-friendly solutions increases the potential of rail considered as sustainable form of public transport. Contemporary tendencies of designing railway stations in Europe are focused on lowering energy consumption and reducing carbon emission. The main goal of the designers is to create a friendly and intuitive space for its users and at the same time a building that uses renewable energy sources and minimizes negative impact on the environment by the increase of biologically active areas, reuse of rainwater and greywater, innovative heating and cooling solutions and reduction of energy losses. The optimisation of a life circle in railway architecture introduces new approach to passenger service. Examples mentioned in the content of this article help to synthesize changes in approach to the design within the context of sustainability.

  19. Integrated microfluidic probe station.

    Science.gov (United States)

    Perrault, C M; Qasaimeh, M A; Brastaviceanu, T; Anderson, K; Kabakibo, Y; Juncker, D

    2010-11-01

    The microfluidic probe (MFP) consists of a flat, blunt tip with two apertures for the injection and reaspiration of a microjet into a solution--thus hydrodynamically confining the microjet--and is operated atop an inverted microscope that enables live imaging. By scanning across a surface, the microjet can be used for surface processing with the capability of both depositing and removing material; as it operates under immersed conditions, sensitive biological materials and living cells can be processed. During scanning, the MFP is kept immobile and centered over the objective of the inverted microscope, a few micrometers above a substrate that is displaced by moving the microscope stage and that is flushed continuously with the microjet. For consistent and reproducible surface processing, the gap between the MFP and the substrate, the MFP's alignment, the scanning speed, the injection and aspiration flow rates, and the image capture need all to be controlled and synchronized. Here, we present an automated MFP station that integrates all of these functionalities and automates the key operational parameters. A custom software program is used to control an independent motorized Z stage for adjusting the gap, a motorized microscope stage for scanning the substrate, up to 16 syringe pumps for injecting and aspirating fluids, and an inverted fluorescence microscope equipped with a charge-coupled device camera. The parallelism between the MFP and the substrate is adjusted using manual goniometer at the beginning of the experiment. The alignment of the injection and aspiration apertures along the scanning axis is performed using a newly designed MFP screw holder. We illustrate the integrated MFP station by the programmed, automated patterning of fluorescently labeled biotin on a streptavidin-coated surface.

  20. Report of study group 3.3 ''LNG and LPG peak shaving and satellite plants''; Rapport du groupe d'etude 3.3 ''usines d'ecretement de pointes et stations satellites GNL et GPL''

    Energy Technology Data Exchange (ETDEWEB)

    Klein Nagelvoort, R.

    2000-07-01

    This report presents a world-wide overview of LNG and LPG Peak Shaving and Satellite Plants, compiled by the study group 3.3 of the International Gas Union. The scope of the work of the study group includes: - LPG peak shavers (LPG + air, N{sub 2}) in gas distribution networks; - LPG peak shavers for start-up and back-up fuel for LNG terminals and power stations; - LNG peak shavers for gas distribution networks; - Small-scale liquefaction plants for distribution to satellites and dedicated consumers (e.g. power generators, chemical plants, trucking companies etc.); - LNG peak shavers as back-up for large consumers; - Alternative liquefaction technologies for LNG and LPG (e.g. refrigeration cycles, supersonic expansion, thermo-acoustic designs); - Alternative storage tank designs for LNG and LPG. The report presents an overview of current installations world-wide and considers the prospects of technological developments with respect to equipment, remote operations and safety constraints. It also includes where possible a review of capital and operating costs, regulations, and an identification of opportunities and trends. The report collates the information available to the study group at the time of the writing, which may explain some heterogeneity in the document. (author)

  1. Multivariable control in nuclear power stations

    International Nuclear Information System (INIS)

    Parent, M.; McMorran, P.D.

    1982-11-01

    Multivariable methods have the potential to improve the control of large systems such as nuclear power stations. Linear-quadratic optimal control is a multivariable method based on the minimization of a cost function. A related technique leads to the Kalman filter for estimation of plant state from noisy measurements. A design program for optimal control and Kalman filtering has been developed as part of a computer-aided design package for multivariable control systems. The method is demonstrated on a model of a nuclear steam generator, and simulated results are presented

  2. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

    The US Department of Energy (DOE) Shippingport Station Decommissioning Project (SSDP) decontaminated and dismantled the world's first nuclear-fueled, commercial-size electric power plant. The SSDP programmatic goal direction for technology transfer is documentation of project management and operations experience. The objective is to provide future nuclear facility decommissioning projects with pertinent SSDP performance data for project assessment, planning, and operational implementation. This paper sets out access and availability directions for SSDP technology acquisition. Discusses are technology transfer definition; technology transfer products including topical and other project reports, professional-technical society presentations, other project liaison and media relations, visual documentation, and technology transfer data base; and retrieving SSDP information

  3. Discharges from nuclear power stations

    International Nuclear Information System (INIS)

    1991-02-01

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report contains details of the technologies used at many nuclear power stations to treat and control radioactive discharges and gives, where information was available, details of discharges and authorised discharge limits. (author)

  4. Application for the Tape Station

    CERN Document Server

    Solero, A

    2003-01-01

    The Tape Station is used as an Isolde facility to observe the variations of intensity and the lifespan of certain isotopes. A Siemens Simatic FM-352-5 module controls the Tape Station in a PLC system then a DSC controls the PLC, which will be controlled the Tape station program. During the Isolde consolidation project, the Tape Station has been rebuilt, and the control system has been fully integrated in the PS control. Finally, a new application has been written in JAVA Development kit 1.4 and the PS Java environment. The main purpose of this note is to explain how to use this program.

  5. Space Station Engineering Design Issues

    Science.gov (United States)

    Mcruer, Duane T.; Boehm, Barry W.; Debra, Daniel B.; Green, C. Cordell; Henry, Richard C.; Maycock, Paul D.; Mcelroy, John H.; Pierce, Chester M.; Stafford, Thomas P.; Young, Laurence R.

    1989-01-01

    Space Station Freedom topics addressed include: general design issues; issues related to utilization and operations; issues related to systems requirements and design; and management issues relevant to design.

  6. Photochemical Assessment Monitoring Stations (PAMS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — Photochemical Assessment Monitoring Stations (PAMS). This file provides information on the numbers and distribution (latitude/longitude) of air monitoring sites...

  7. 76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

    Science.gov (United States)

    2011-04-29

    ... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS... Plants: Supplement 43, Regarding Palo Verde Nuclear Generating Station,'' issued January 2011, discusses...

  8. Reliable, fault tolerant control systems for nuclear generating stations

    International Nuclear Information System (INIS)

    McNeil, T.O.; Olmstead, R.A.; Schafer, S.

    1990-01-01

    Two operational features of CANDU Nuclear Power Stations provide for high plant availability. First, the plant re-fuels on-line, thereby eliminating the need for periodic and lengthy refuelling 'outages'. Second, the all plants are controlled by real-time computer systems. Later plants are also protected using real-time computer systems. In the past twenty years, the control systems now operating in 21 plants have achieved an availability of 99.8%, making significant contributions to high CANDU plant capacity factors. This paper describes some of the features that ensure the high degree of system fault tolerance and hence high plant availability. The emphasis will be placed on the fault tolerant features of the computer systems included in the latest reactor design - the CANDU 3 (450MWe). (author)

  9. Station History Of The Seismic Station In Ahmadu Bello University ...

    African Journals Online (AJOL)

    Dominants in the selected events are events from Meditterranian, East Kazakhstan, India/Burma/China, South and Central America and North Ascension island regions. The limited number of events reporting at the station was due to low operational gain at the station which permitted only events whose magnitudes are ...

  10. Working in a virtual power plant

    International Nuclear Information System (INIS)

    Thibault, G.; Smadja, S.

    1999-01-01

    Graphical simulations on computer providing a virtual and reversible experience can now be used for maintenance in nuclear power plants allowing operations to be tested and tools to be optimised. Eventually, operatives will be trained to work in virtual nuclear power plants in complete safety. (authors)

  11. Bern Power Station Co

    International Nuclear Information System (INIS)

    1981-01-01

    The Bernische Kraftwerke electricity generation/supply company supplies about one eighth of the Swiss electrical energy demand with about one sixth of the Swiss generating capacity. Directly or indirectly one million inhabitants are supplied, a substantial contribution to the Swiss economy. Data given on BKW includes: historical background, structure, organisation, operations, generating plant, transmission/distribution equipment, electricity generated, supplied, exported and imported, financial aspects, accounting practice and cooperation arrangements with other utilities. (P.G.R.)

  12. Experience with refuse-fuelled industrial heating power stations during licensing, construction and operation. Continental heating power plant, Korbach; Erfahrungen mit EBS-Industrieheizkraftwerken in Genehmigung, Bau und Betrieb. Industrieheizkraftwerk Continental, Korbach

    Energy Technology Data Exchange (ETDEWEB)

    Kaiser, F. [MVV Energie Industrial Solutions West GmbH, Sollingen (Germany)

    2007-07-01

    In this project, all licensing-relevant boundary conditions of the site were clarified beforehand and were taken into account in the conception of the plant. Particular regard was given to the fact that the plant will be sited in a water protection area and to the area's pre-pollution history. The licensing procedure showed that the stipulations of the 17. BImSchV and other protective regulations are insufficient in the opinion of some citizens, who expect a deterioration of their living conditions and even health problems arising from a technical systems that are not state of the art. The legal representatives of the concerned citizens assume a lack of basic data and wrong assumptions for the licensing procedure. Greater transparence by better advance information may lead to a more objective discussion but it cannot quench citizens' fears. (orig.)

  13. Training of engineers for nuclear power station operation

    International Nuclear Information System (INIS)

    Myerscough, P.B.

    1980-01-01

    The requirements for staffing and training of a nuclear electric utility are described. Current training facilities at the Central Electricity Generating Board are applicable to gas-cooled technology with the possibility of the introduction of a thermal water system and fast reactors in the future. The CEGB training centres provide for the initial training of operational staff, revision training of experienced operational staff, and training of non-operational staff from the stations and supporting departments. Details are given of the content of the training courses which also provide simulation facilities of the basic dynamics of the CEGB stations. Further developments in simulation will include dynamics of the boiler and turbine plants in Magnox stations. The flexibility of the AGR simulations will enable the training exercises to be adjusted to meet changing operating patterns for each AGR station. (U.K.)

  14. Sizewell 'B' power station public inquiry: CEGB proof of evidence

    International Nuclear Information System (INIS)

    Youngman, P.

    1982-11-01

    The scenic effect of the proposed Sizewell B power station is considered. Offsite planting of trees, landscaping of the areas around the new access road and of the site itself are discussed. The landscape designs are in a separate volume. (U.K.)

  15. Space Station life science research facility - The vivarium/laboratory

    Science.gov (United States)

    Hilchey, J. D.; Arno, R. D.

    1985-01-01

    Research opportunities possible with the Space Station are discussed. The objective of the research program will be study gravity relationships for animal and plant species. The equipment necessary for space experiments including vivarium facilities are described. The cost of the development of research facilities such as the vivarium/laboratory and a bioresearch centrifuge is examined.

  16. Early Site Permit Demonstration Program: Station design alternatives report

    International Nuclear Information System (INIS)

    1993-03-01

    This report provides the results of investigating the basis for including Station Design Alternatives (SDAs) in the regulatory guidance given for nuclear plant environmental reports (ERs), explains approaches or processes for evaluating SDAs at the early site permit (ESP) stage, and applies one of the processes to each of the ten systems or subsystems considered as SDAS. The key objective o this report s to demonstrate an adequate examination of alternatives can be performed without the extensive development f design data. The report discusses the Composite Suitability Approach and the Established Cutoff Approach in evaluating station design alternatives and selects one of these approaches to evaluate alternatives for each of the plant or station that were considered. Four types of ALWRs have been considered due to the availability of extensive plant data: System 80+, AP600, Advanced Boiling Reactor (ABWR), and Simplified Boiling Water Reactor (SBWR). This report demonstrates the feasibility of evaluating station design alternatives when reactor design detail has not been determined, quantitatively compares the potential ental impacts of alternatives, and focuses the ultimate selection of a alternative on cost and applicant-specific factors. The range of alternatives system is deliberately limited to a reasonable number to demonstrate the or to the three most commonly used at operating plants

  17. Port construction works in the Sendai Nuclear Power Station

    International Nuclear Information System (INIS)

    Narahara, Akio; Minamata, Hisashi; Harada, Kensaku

    1982-01-01

    Sendai Nuclear Power Station is the second nuclear power station of Kyushu Electric Power Co., Inc., with two PWR plants of 890 MW each, and the operation of No.1 plant will be started in July, 1984, and that of No.2 plant in March, 1986. The civil engineering works for both plants were started in June, 1978, and March, 1981, respectively, and the rate of progress as of the end of September, 1982, was 97 % and 66 %, respectively. In the construction of this power station, the port facility was provided for the transport of construction materials and spent fuel, and for the intake of condenser cooling water. In order to make the construction by dry work, the double cofferdam structures with steel sheet piles were made offshore. The use of the wharf was started in March, 1980, though typhoons hit the area several times, and the dredging in the port was completed in May, 1982. The outline of the plan of this power station, the state of affairs before the start of construction, the outline of the port construction works, the topography, geological features and sea conditions, the design of the port such as breakwaters, unloading wharf and water intake, the manufacture and installation of caissons, dredging, and the temporary cofferdam works for water intake are described. (author)

  18. SA silent on talk of a second nuclear station

    International Nuclear Information System (INIS)

    Waddacor, M.

    1983-01-01

    Local nuclear energy officials have either denied or will not comment on recent European reports suggesting South Africa plans to construct a second nuclear power station. The probability of South Africa building a second nuclear power plant is discussed. The recent sabotage at the Koeberg-1 reactor is also mentioned

  19. Developments in health physics at Electricite de France, implementation at Guangdong Nuclear Power Station

    International Nuclear Information System (INIS)

    Yang Maochun

    1993-01-01

    The Guangdong Nuclear Power Station intend to apply the same organization and the same principle in health physics as EDF (ELECTRICITE DE FRANCE). The permanent 'clean plant' objective has ensured that the internal exposure of nuclear plant workers has remained virtually zero. This, then, is the basis on which EDF is now continuing to develop health physics in its plants

  20. RF-Station control crate

    International Nuclear Information System (INIS)

    Beuzekom, M.G. van; Es, J.T. van.

    1992-01-01

    This report gives a description of the electronic control-system for the RF-station of AmPS. The electronics form the connection between the computer-system and the hardware of the RF-station. Only the elements of the systems which are not described in the other NIKHEF-reports are here discussed in detail. (author). 7 figs

  1. Balloon launching station, Mildura, Victoria

    International Nuclear Information System (INIS)

    The Mildura Balloon Launching Station was established in 1960 by the Department of Supply (now the Department of Manufacturing Industry) on behalf of the United States Atomic Energy Commission (USAEC) to determine the content of radioactive material in the upper atmosphere over Australia. The Station location and layout, staffing, balloon launching equipment, launching, tracking and recovery are described. (R.L.)

  2. Small wind power plants : results of the Nordic wind diesel projects for large telecommunications companies; Implantation d'une centrale eolienne comme source d'energie d'appoint pour des stations de telecommunications

    Energy Technology Data Exchange (ETDEWEB)

    Ilinca, A.; Chaumel, J.L. [ATI Eolien, Rimouski, PQ (Canada); Thibault, G. [Entreprises MB, PQ (Canada)

    2005-07-01

    Two wind-diesel generating stations have been installed at telecommunication towers in the remote communities of Kuujjuarapik and Lac Julien in northern Quebec. The use of wind power contributes to the sustainable development in these remote areas by lowering the reliance on costly helicopter-transported diesel fuel and by reducing the release of greenhouse gases to the atmosphere. The technical characteristics of the Bergey 100 kW turbine with battery charger were presented along with the technical characteristics of the EolDie control panel that controls the supply of electricity from either the wind or diesel power generators. For the first time, the ATI-Wind technology system that was installed can supply the needs of the large telecommunication towers of Bell Canada and Telebec from either the wind or the diesel generators. The system is also capable of shutting down the diesel generators when wind energy is sufficient to take over. Early results from June 2005 showed that the diesel generators could be turned off for 55 per cent of the time. Preliminary results of these 2 projects were discussed by the firms in charge of the diesel and wind aspects and recommendations for improvements to the control systems were presented. 11 figs.

  3. Situation and future developments in the power station engineering of the GDR

    International Nuclear Information System (INIS)

    Effenberger, H.; Weidlich, H.G.

    1990-01-01

    Starting with the present state of power stations in the GDR and their evaluation in respect of energy and ecology, the authors have developed a concept for the future objectives and possibilities of the power stations. With regard to the modification of the power station engineering, considered as urgently required due to reasons of energy and environment, there was suggestions for modern plant conceptions, such as fluidized bed combustors, combined and gas/steam power plants, besides the retrofitting and the new building of proven conventional plants. It includes also the extension of combined heat and power systems, of nuclear energy, and the use of regenerative energy sources as parts of this concept. The power station modifications intended are shown in tables for the various power station locations. (orig.) [de

  4. Control Centre operations as the focus for building station teamwork - issues and resource impacts

    International Nuclear Information System (INIS)

    Mathews, G.; Lane, L.; Davey, E.

    2006-01-01

    Effective teamwork among station work groups is essential for plant production and safety in all phases of plant operation. To achieve effective teamwork, all contributing work groups must have ongoing access to and share a common perspective on station work priorities, and recognize how their individual contributions fit with and support the contributions of other groups in support of the larger station goals. Achieving and maintaining this alignment in perspective across all workgroups can be a challenge in large organizations. This paper discusses the experience at Darlington in building and maintaining station teamwork among the station workgroups in support of day-to-day plant operations. The issues encountered and the resource impacts of specific teamwork supporting practices adopted are outlined. (author)

  5. The role of industrial-sanitary laboratory of medical aid station of Federal administration in prophylaxis of emergency situations at the plants of nuclear-energy complex and liquidation of their after-effects

    International Nuclear Information System (INIS)

    Antipin, E.B.

    1995-01-01

    On the example of several radiation accidents the author summarized the personal practical experience in organization of work in industrial-sanitary laboratories based at the nuclear energy plants of nuclear-energy complex, in respect of prophylaxis of emergency radiation situations and liquidation of their after-effects. It is pointed out that successful activity in rendering emergency medical aid in emergency situations, caused by radiation accidents, is possible only subject to close contact of science, practical medical care and sanitary service which should become a part of the uniform public health system. 4 refs

  6. Obrigheim nuclear power station. Annual report 1987

    International Nuclear Information System (INIS)

    Koerner, C.

    1988-01-01

    The Obrigheim nuclear power station was operated at full load during the year 1987; 7.351 operating hours procuded electrical energy of 2.607 GWh. This is the fifth best annual result during Obrigheim's operating period. Since commissioning in October 1968, 139.310 hours of operation have generated 46.681 GWh (gross) and from test operation in March 1969 until the end of 1987, 138.530 hours of operation have generated 46.569 GWh. This is an availability of power of 81.6% in this period and a time availability of 83.9%. In 1987, the plant was shut down for 1.222 hours for the 18th refueling including testing, inspection and repair work. Apart from refueling, the plant had a good time availability and therefore contributed 5% to the safe, economical and environmentally acceptable electricity supply of the Land Baden-Wuerttemberg. The power station is of great significance to the region, both in terms of power supply and the economy. (orig./HP) [de

  7. Seismometer array station processors

    International Nuclear Information System (INIS)

    Key, F.A.; Lea, T.G.; Douglas, A.

    1977-01-01

    A description is given of the design, construction and initial testing of two types of Seismometer Array Station Processor (SASP), one to work with data stored on magnetic tape in analogue form, the other with data in digital form. The purpose of a SASP is to detect the short period P waves recorded by a UK-type array of 20 seismometers and to edit these on to a a digital library tape or disc. The edited data are then processed to obtain a rough location for the source and to produce seismograms (after optimum processing) for analysis by a seismologist. SASPs are an important component in the scheme for monitoring underground explosions advocated by the UK in the Conference of the Committee on Disarmament. With digital input a SASP can operate at 30 times real time using a linear detection process and at 20 times real time using the log detector of Weichert. Although the log detector is slower, it has the advantage over the linear detector that signals with lower signal-to-noise ratio can be detected and spurious large amplitudes are less likely to produce a detection. It is recommended, therefore, that where possible array data should be recorded in digital form for input to a SASP and that the log detector of Weichert be used. Trial runs show that a SASP is capable of detecting signals down to signal-to-noise ratios of about two with very few false detections, and at mid-continental array sites it should be capable of detecting most, if not all, the signals with magnitude above msub(b) 4.5; the UK argues that, given a suitable network, it is realistic to hope that sources of this magnitude and above can be detected and identified by seismological means alone. (author)

  8. Plant Pathogenicity in Spaceflight Environments

    OpenAIRE

    Bishop, Deborah L.; Levine, Howard G.; Anderson, Anne J.

    1996-01-01

    Plants grown in microgravity are subject to many environmental stresses, which may promote microbial growth and result in pathogenicity to the plant. Recent plant experiments with super dwarf wheat aboard the NASA Space Shuttle and NASA/Russian Mir Space Station returned from the mission with severe degrees of fungal contamination. Understanding the cause of such microbial contamination and methods to eliminate it are necessary prerequisites for continued plant growth and development studies ...

  9. Plant Habitat (PH)

    Science.gov (United States)

    Onate, Bryan

    2016-01-01

    The International Space Station (ISS) will soon have a platform for conducting fundamental research of Large Plants. Plant Habitat (PH) is designed to be a fully controllable environment for high-quality plant physiological research. PH will control light quality, level, and timing, temperature, CO2, relative humidity, and irrigation, while scrubbing ethylene. Additional capabilities include leaf temperature and root zone moisture and oxygen sensing. The light cap will have red (630 nm), blue (450 nm), green (525 nm), far red (730 nm) and broad spectrum white LEDs. There will be several internal cameras (visible and IR) to monitor and record plant growth and operations.

  10. Impact of Auxiliary Equipments Consumption on Electricity Generation Cost in Selected Power Plants of Pakistan

    Directory of Open Access Journals (Sweden)

    DILEEP KUMAR

    2017-04-01

    Full Text Available This study focuses on higher generation cost of electricity in selected TPPs (Thermal Power Plants in Sindh, Pakistan. It also investigates the energy consumed by the auxiliary equipment of the selected TPPs in Sindh, Pakistan. The AC (Auxiliary Consumption of selected TPPs is compared with that in UK and other developed countries. Results show that the AC in selected TPPs in Sindh, Pakistan exceeds the average AC of the TPPs situated in developed countries. Many energy conservation measures such as impeller trimming and de-staging, boiler feed pump, high voltage inverter, variable frequency drive, and upgrading the existing cooling tower fan blades with fiber reinforced plastic are discussed to overcome higher AC. This study shows that harnessing various available energy conservative measures the AC and unit cost can be reduced by 4.13 and 8.8%; also adverse environmental impacts can be mitigated. Results show that the unit cost of electricity can be reduced from Rs.20 to19/kWh in JTPP (Jamshoro Thermal Power Plant, Rs.9 to 8.8/kWh in GTPS (Gas Turbine Power Station Kotri and Rs. 11 to 10.27/ kWh in LPS (Lakhara Power Station. Thus, electricity production can be improved with the existing capacity, which will eventually assist to manage the current energy crisis and ensure its conservation

  11. Solar-Assisted Electric Vehicle Charging Station Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Lapsa, Melissa Voss [ORNL; Durfee, Norman [ORNL; Maxey, L Curt [ORNL; Overbey, Randall M [ORNL

    2011-09-01

    Oak Ridge National Laboratory (ORNL) has been awarded $6.8 million in the Department of Energy (DOE) American Recovery and Reinvestment Act (ARRA) funds as part of an overall $114.8 million ECOtality grant with matching funds from regional partners to install 125 solar-assisted Electric Vehicle (EV) charging stations across Knoxville, Nashville, Chattanooga, and Memphis. Significant progress has been made toward completing the scope with the installation of 25 solar-assisted charging stations at ORNL; six stations at Electric Power Research Institute (EPRI); and 27 stations at Nissan's Smyrna and Franklin sites, with three more stations under construction at Nissan's new lithium-ion battery plant. Additionally, the procurement process for contracting the installation of 34 stations at Knoxville, the University of Tennessee Knoxville (UTK), and Nashville sites is underway with completion of installation scheduled for early 2012. Progress is also being made on finalizing sites and beginning installations of 30 stations in Nashville, Chattanooga, and Memphis by EPRI and Tennessee Valley Authority (TVA). The solar-assisted EV charging station project has made great strides in fiscal year 2011. A total of 58 solar-assisted EV parking spaces have been commissioned in East and Middle Tennessee, and progress on installing the remaining 67 spaces is well underway. The contract for the 34 stations planned for Knoxville, UTK, and Nashville should be underway in October with completion scheduled for the end of March 2012; the remaining three Nissan stations are under construction and scheduled to be complete in November; and the EPRI/TVA stations for Chattanooga, Vanderbilt, and Memphis are underway and should be complete by the end of March 2012. As additional Nissan LEAFs are being delivered, usage of the charging stations has increased substantially. The project is on course to complete all 125 solar-assisted EV charging stations in time to collect meaningful data

  12. Space station propulsion requirements study

    Science.gov (United States)

    Wilkinson, C. L.; Brennan, S. M.

    1985-01-01

    Propulsion system requirements to support Low Earth Orbit (LEO) manned space station development and evolution over a wide range of potential capabilities and for a variety of STS servicing and space station operating strategies are described. The term space station and the overall space station configuration refers, for the purpose of this report, to a group of potential LEO spacecraft that support the overall space station mission. The group consisted of the central space station at 28.5 deg or 90 deg inclinations, unmanned free-flying spacecraft that are both tethered and untethered, a short-range servicing vehicle, and a longer range servicing vehicle capable of GEO payload transfer. The time phasing for preferred propulsion technology approaches is also investigated, as well as the high-leverage, state-of-the-art advancements needed, and the qualitative and quantitative benefits of these advancements on STS/space station operations. The time frame of propulsion technologies applicable to this study is the early 1990's to approximately the year 2000.

  13. 47 CFR 97.109 - Station control.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Station control. 97.109 Section 97.109... SERVICE Station Operation Standards § 97.109 Station control. (a) Each amateur station must have at least one control point. (b) When a station is being locally controlled, the control operator must be at the...

  14. Application of Activated Sludge Process at Phenol Water Treatment Station in Yanzhou Coal Mine Distract Coking Plant%活性污泥法在兖州矿区焦化厂酚水处理站的应用

    Institute of Scientific and Technical Information of China (English)

    许寒冰; 牟增越

    2001-01-01

    论述活性污泥法处理焦化酚水的若干问题,包括活性污泥的培养、驯化、运行工艺指标、参数,管理中应把握的几个工艺点,运行中常出现的问题及对策,几点探索和体会。%Some of the technical problems of phenol water treatment in coking plant by using the activated sludge process are discussed. These technical problems are including culture, domestication, operation process index of activated sludge; a few of process point control in management; often happened technical problems and countermeasures in operation.

  15. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION and PLANNING FOR REVRIEVAL TREATMENT and EVENTUAL DISPOSAL AT WIPP

    International Nuclear Information System (INIS)

    KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

    2006-01-01

    The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP)

  16. Biotechnology opportunities on Space Station

    Science.gov (United States)

    Deming, Jess; Henderson, Keith; Phillips, Robert W.; Dickey, Bernistine; Grounds, Phyllis

    1987-01-01

    Biotechnology applications which could be implemented on the Space Station are examined. The advances possible in biotechnology due to the favorable microgravity environment are discussed. The objectives of the Space Station Life Sciences Program are: (1) the study of human diseases, (2) biopolymer processing, and (3) the development of cryoprocessing and cryopreservation methods. The use of the microgravity environment for crystal growth, cell culturing, and the separation of biological materials is considered. The proposed Space Station research could provide benefits to the fields of medicine, pharmaceuticals, genetics, agriculture, and industrial waste management.

  17. Space Station Freedom food management

    Science.gov (United States)

    Whitehurst, Troy N., Jr.; Bourland, Charles T.

    1992-01-01

    This paper summarizes the specification requirements for the Space Station Food System, and describes the system that is being designed and developed to meet those requirements. Space Station Freedom will provide a mix of frozen, refrigerated, rehydratable, and shelf stable foods. The crew will pre-select preferred foods from an approved list, to the extent that proper nutrition balance is maintained. A galley with freezers, refrigerators, trash compactor, and combination microwave and convection ovens will improve crew efficiency and productivity during the long Space Station Freedom (SSF) missions.

  18. Snubber reduction program at the Byron Station, Unit 1

    International Nuclear Information System (INIS)

    Arterburn, J.; Bakhtiari, S.

    1987-01-01

    Commonwealth Edison Company's (CECo's) Byron Station, unit 1, was originally designed with approximately 1200 snubbers supporting the plant's large- and small-bore piping systems. This relatively large number of snubbers is attributed to excessive conservatism in nuclear piping codes and regulations effective during the original piping design. A recent pilot program at CECo's LaSalle County Station, a boiling water reactor plant, demonstrated that a 50% or greater reduction in total snubber population is achievable in plants of this design vintage. Based on the successful results of the pilot program, CECo initiated a full scale snubber reduction program at Byron, a pressurized water reactor plant of the same vintage at the LaSalle County Station. The benefits from a reduced snubber population are described. To realize the maximum potential benefits, all snubbers in the plant were prioritized in order of desirability for removal. The priority designations are discussed. The major results from phase 1 of the Byron program are summarized. The NRC inspection of the project addressed a variety of issues and is discussed. The conclusions that can be drawn from the phase 1 program are summarized

  19. Ethnobotanical Research at the Kutukú Scientific Station, Morona-Santiago, Ecuador

    Science.gov (United States)

    Bracco, Francesco; Cerna, Marco; Vita Finzi, Paola; Vidari, Giovanni

    2016-01-01

    This work features the results of an ethnobotanical study on the uses of medicinal plants by the inhabitants of the region near to the Kutukú Scientific Station of Universidad Politécnica Salesiana, located in the Morona-Santiago province, southeast of Ecuador. In the surroundings of the station, one ethnic group, the Shuar, has been identified. The survey hereafter reports a total of 131 plant species, with 73 different therapeutic uses. PMID:28074189

  20. Ethnobotanical Research at the Kutukú Scientific Station, Morona-Santiago, Ecuador

    Directory of Open Access Journals (Sweden)

    Jose Luis Ballesteros

    2016-01-01

    Full Text Available This work features the results of an ethnobotanical study on the uses of medicinal plants by the inhabitants of the region near to the Kutukú Scientific Station of Universidad Politécnica Salesiana, located in the Morona-Santiago province, southeast of Ecuador. In the surroundings of the station, one ethnic group, the Shuar, has been identified. The survey hereafter reports a total of 131 plant species, with 73 different therapeutic uses.

  1. Ethnobotanical Research at the Kutukú Scientific Station, Morona-Santiago, Ecuador.

    Science.gov (United States)

    Ballesteros, Jose Luis; Bracco, Francesco; Cerna, Marco; Vita Finzi, Paola; Vidari, Giovanni

    2016-01-01

    This work features the results of an ethnobotanical study on the uses of medicinal plants by the inhabitants of the region near to the Kutukú Scientific Station of Universidad Politécnica Salesiana, located in the Morona-Santiago province, southeast of Ecuador. In the surroundings of the station, one ethnic group, the Shuar, has been identified. The survey hereafter reports a total of 131 plant species, with 73 different therapeutic uses.

  2. VT Data - Electric Charging Stations

    Data.gov (United States)

    Vermont Center for Geographic Information — Locations of Electric Charging Stations provided by the NREL national laboratory of the U.S. Department of Energy, Office of Energy Efficiency and Renewable Energy....

  3. NOAA Weather Radio - Station Listing

    Science.gov (United States)

    Non-Zero All Hazards Logo Emergency Alert Description Event Codes Fact Sheet FAQ Organization Search COVERAGE County Coverage Listings State Coverage Listings NWR Station Search Maps SAME SAME Coding Using

  4. Services for nuclear power stations

    International Nuclear Information System (INIS)

    Fremann, M.; Ryckelynck

    1987-01-01

    This article gives an information as complete as possible about the activities of the french nuclear industry on the export-market. It describes the equipment and services available in the field of services for nuclear power stations [fr

  5. Interior Alaska Gravity Station Data

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 9416 records. This data base was received in March 1997. Principal gravity parameters include Free-air Anomalies which have been...

  6. Gravity Station Data for Spain

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 28493 records. This data base was received in April 1997. Principal gravity parameters include Free-air Anomalies which have been...

  7. WVU Hydrogen Fuel Dispensing Station

    Energy Technology Data Exchange (ETDEWEB)

    Davis, William [West Virginia University Research Corporation, Morgantown, WV (United States)

    2015-09-01

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

  8. Gravity Station Data for Portugal

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 3064 records. This data base was received in April 1997. Principal gravity parameters include Free-air Anomalies which have been...

  9. Shippingport Station Decommissioning Project Start of Physical Decommissioning

    International Nuclear Information System (INIS)

    Crimi, F. P.

    1987-01-01

    The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy, and the turbine-generator and balance of plant, which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by DOE from Duquesne Light Company. The Shippingport Station Decommissioning Project is being performed under contract to the DOE by the General Electric Company and its integrated subcontractor, Morrison-Knudsen Company. as the Decommissioning Operations Contractor. This paper describes the current status of the physical decommissioning work, which started September 1985. The preparations required to start a major decommissioning work effort in a safe and cost effective manner are discussed including the development and implementation of a cost/schedule control system. The detailed plan required to ensure that people, property, and procedures are ready in sufficient time to support the start of physical decommissioning is also discussed. The total estimated cost of the Shippingport Station Decommissioning Project should be $98.3 M, with the Project scheduled for completion in April 1990. As the decommissioning of the first commercial-scale nuclear power plant, the Shippingport Project is expected to set the standard for safe, cost-effective demolition of nuclear plants

  10. Isar-2 nuclear power station twenty-five years

    International Nuclear Information System (INIS)

    Fischer, Erwin; Luginger, Markus

    2013-01-01

    The Isar-2 nuclear power station (KKI 2) began commercial power operation on April 9, 1988. In these past 25 years the plant generated a total of approx. 285 billion kWh of electricity. The annual electricity production of KKI 2 of approx. 12 billion kWh corresponds to a share of approx. 15 % in the cumulated Bavarian electricity production. This amount of electricity, theoretically, could supply some 3 million three person households, or meet two thirds of the electricity requirement of the Bavarian industry, for one year. In its 25 years of power operation the Isar-2 nuclear power plant has recorded the highest annual gross electricity production of all nuclear power plants in the world nine times so far. A plant performance as impressive as this necessitates a plant availability far above the average. This, in turn, is based on short revision times and faultfree plant operation. However, high plant safety and availability must not be taken for granted, but are the result of responsible, safety-minded plant operation combined with continuous plant optimization and permanent execution of comprehensive checks, inspections, and maintenance measures. Besides plant technology also organization and administration were permanently advanced and adapted to changing requirements so as to safeguard reliable, safe, and non-polluting plant operation.

  11. Alternative Fuels Data Center: Ethanol Fueling Stations

    Science.gov (United States)

    ... More in this section... Ethanol Basics Benefits & Considerations Stations Locations Infrastructure fueling stations by location or along a route. Infrastructure Development Learn about ethanol fueling infrastructure; codes, standards, and safety; and ethanol equipment options. Maps & Data E85 Fueling Station

  12. Non-Coop Station History (Unindexed)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Station history documentation for stations outside the US Cooperative Observer network. Documents should be compared with those in the Non-Coop Station History...

  13. Refurbishment of Point Lepreau Generating Station

    International Nuclear Information System (INIS)

    Thompson, P.D.; Jaitly, R.; Ichiyen, N.; Petrilli, M.A.

    2004-01-01

    NB Power is planning to conduct an 18-month maintenance outage of the Point Lepreau Generating Station (PLGS) beginning in April 2008. The major activity would be the replacement of all 380 Fuel Channel and Calandria Tube Assemblies and the connecting feeder pipes. This activity is referred to as Retube. NB Power would also take advantage of this outage to conduct a number of repairs, replacements, inspections and upgrades (such as rewinding or replacing the generator, replacement of shutdown system trip computers, replacement of certain valves and expansion joints, inspection of systems not normally accessible, etc). These collective activities are referred to as Refurbishment. This would allow the station to operate for an additional 25 to 30 years. The scope of the project was determined from the outcome of a two-year study involving a detailed condition assessment of the station that examined issues relating to ageing and obsolescence. The majority of the plant components were found to be capable of supporting extended operation without needing replacement or changes. In addition to the condition assessment, a detailed review of Safety and Licensing issues associated with extended operation was performed. This included a review of known regulatory and safety issues, comparison of the station against current codes and standards, and comparison of the station against safety related modifications made to more recent CANDU 6 units. Benefit cost analyses (BCA) were performed to assist the utility in determining which changes were appropriate to include in the project scope. As a Probabilistic Safety Assessment (PSA) for PLGS did not exist at the time, a risk baseline for the station had to be determined for use in the BCA. Extensive dialogue with the Canadian Nuclear Safety Commission staff was also undertaken during this phase. A comprehensive Licensing Framework was produced upon which the CNSC provided feedback to NB Power. This feedback was important in terms of

  14. Autonomous Electrical Vehicles’ Charging Station

    OpenAIRE

    Józef Paska; Mariusz Kłos; Łukasz Rosłaniec; Rafał Bielas; Magdalena Błędzińska

    2016-01-01

    This paper presents a model of an autonomous electrical vehicles’ charging station. It consists of renewable energy sources: wind turbine system, photovoltaic cells, as well as an energy storage, load, and EV charging station. In order to optimise the operating conditions, power electronic converters were added to the system. The model was implemented in the Homer Energy programme. The first part of the paper presents the design assumptions and technological solutions. Further in the paper...

  15. Space stations systems and utilization

    CERN Document Server

    Messerschmid, Ernst

    1999-01-01

    The design of space stations like the recently launched ISS is a highly complex and interdisciplinary task. This book describes component technologies, system integration, and the potential usage of space stations in general and of the ISS in particular. It so adresses students and engineers in space technology. Ernst Messerschmid holds the chair of space systems at the University of Stuttgart and was one of the first German astronauts.

  16. Space Station Freedom operations costs

    Science.gov (United States)

    Accola, Anne L.; Williams, Gregory J.

    1988-01-01

    Measures to reduce the operation costs of the Space Station which can be implemented in the design and development stages are discussed. Operational functions are described in the context of an overall operations concept. The provisions for operations cost responsibilities among the partners in the Space Station program are presented. Cost estimating methodologies and the way in which operations costs affect the design and development process are examined.

  17. Pretreatment of lignocellulosic material with fungi capable of higher lignin degradation and lower carbohydrate degradation improves substrate acid hydrolysis and the eventual conversion to ethanol

    Energy Technology Data Exchange (ETDEWEB)

    Kuhar, S.; Nair, L.M.; Kuhad, R.C. [Delhi Univ., New Delhi (India). Dept. of Microbiology, Lignocellulose Biotechnology Laboratory

    2008-04-15

    Lignocellulosic biomass is the most abundant energy resource in the world and is a potential source of carbon substrate for the production of ethanol via fermentation. However, the presence of lignin restricts access to holocellulose. It is necessary to break or remove the lignin in plant residues prior to their hydrolysis. Pretreatment is needed to liberate cellulose and hemicellulose from the lignins. This paper discussed a biological delignification method that avoided the use of toxic and corrosive chemicals. The in situ microbial delignification process used white rot fungi as a basidiomycetes for biological pretreatment. The study examined the capability of 4 basidiomycetes fungi, notably: (1) Phanerochaete chrysosporium; (2) Pycnoporus cinnabarinus; (3) fungal isolate RCK-1; and (4) fungal isolate RCK-3. The fungi were used to delignify wheat straw and improve hydrolysis procedures. Attempts were also made to ferment the acid hydrolysates from fungal-pretreated lignocellulosic materials. Results of the experiment showed that higher yields of ethanol were obtained using selective lignin-degrading fungi as a pretreatment method. 39 refs., 3 tabs., 4 figs.

  18. Advances in power station construction

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    This book is about power stations - specifically about the construction of modern power stations by the Central Electricity Generating Board in England and Wales over the past decade. It describes the work of the CEGB's Generation Development and Construction Division, perhaps better known throughout the world as simply 'Barnwood' where it has its Headquarters in Gloucester, UK. Barnwood was formed in the early 1970s to concentrate the CEGB's then dispersed engineering construction resources to cope with the smaller number but greatly increased size and complexity of modern power station projects. Perhaps uniquely over the ten years since its formation Barnwood has managed the construction of all types of station; coal-fired, oil-fired, nuclear, pumped storage and hydro. This book tells the story of these various projects and gives detailed descriptions of the respective stations. However, it is not intended as a comprehensive description of power station technology. Rather it is intended to convey the scale of such projects and the many decisions and compromises which have to be made in the course of managing their construction

  19. Severe accident sequences simulated at the Grand Gulf Nuclear Station

    International Nuclear Information System (INIS)

    Carbajo, J.J.

    1999-01-01

    Different severe accident sequences employing the MELCOR code, version 1.8.4 QK, have been simulated at the Grand Gulf Nuclear Station (Grand Gulf). The postulated severe accidents simulated are two low-pressure, short-term, station blackouts; two unmitigated small-break (SB) loss-of-coolant accidents (LOCAs) (SBLOCAs); and one unmitigated large LOCA (LLOCA). The purpose of this study was to calculate best-estimate timings of events and source terms for a wide range of severe accidents and to compare the plant response to these accidents

  20. Computer based training simulator for Hunterston Nuclear Power Station

    International Nuclear Information System (INIS)

    Bowden, R.S.M.; Hacking, D.

    1978-01-01

    For reasons which are stated, the Hunterston-B nuclear power station automatic control system includes a manual over-ride facility. It is therefore essential for the station engineers to be trained to recognise and control all feasible modes of plant and logic malfunction. A training simulator has been built which consists of a replica of the shutdown monitoring panel in the Central Control Room and is controlled by a mini-computer. This paper highlights the computer aspects of the simulator and relevant derived experience, under the following headings: engineering background; shutdown sequence equipment; simulator equipment; features; software; testing; maintenance. (U.K.)

  1. Reactor coolant pump shaft seal stability during station blackout

    International Nuclear Information System (INIS)

    Rhodes, D.B.; Hill, R.C.; Wensel, R.G.

    1987-05-01

    Results are presented from an investigation into the behavior of Reactor Coolant Pump shaft seals during a potential station blackout (loss of all ac power) at a nuclear power plant. The investigation assumes loss of cooling to the seals and focuses on the effect of high temperature on polymer seals located in the shaft seal assemblies, and the identification of parameters having the most influence on overall hydraulic seal performance. Predicted seal failure thresholds are presented for a range of station blackout conditions and shaft seal geometries

  2. Reactor coolant pump shaft seal stability during station blackout

    Energy Technology Data Exchange (ETDEWEB)

    Rhodes, D B; Hill, R C; Wensel, R G

    1987-05-01

    Results are presented from an investigation into the behavior of Reactor Coolant Pump shaft seals during a potential station blackout (loss of all ac power) at a nuclear power plant. The investigation assumes loss of cooling to the seals and focuses on the effect of high temperature on polymer seals located in the shaft seal assemblies, and the identification of parameters having the most influence on overall hydraulic seal performance. Predicted seal failure thresholds are presented for a range of station blackout conditions and shaft seal geometries.

  3. 47 CFR 73.6016 - Digital Class A TV station protection of TV broadcast stations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital Class A TV station protection of TV... Class A TV station protection of TV broadcast stations. Digital Class A TV stations must protect authorized TV broadcast stations, applications for minor changes in authorized TV broadcast stations filed on...

  4. 75 FR 22674 - Moynihan Station Development Project

    Science.gov (United States)

    2010-04-29

    ... DEPARTMENT OF TRANSPORTATION Federal Railroad Administration Moynihan Station Development Project... availability of and public comment period for the Moynihan Station Development Project Environmental Assessment... 22675

  5. Build-up forces at Military Institute of Medical Radiology and Oncology for emergency medical response to some eventualities of radiological accidents - some suggestions

    International Nuclear Information System (INIS)

    Ho Van Cu; Nguyen Huu Nghia

    2011-01-01

    Nowadays, the use of various nuclear sources in some fields of the life has brought many practical advantages in general; especially in the next several years, our country will begin construction of the first nuclear plant. However, if there were user carelessness or objective disadvantageous factors (earthquake, tsunami, etc.), that disadvantages could lead to a radiation accident or nuclear accident which causes damages not only for economy but also for public health. Therefore, the emergency response to radiation accident, especially the emergency medical response that has a great important position. To satisfy this real demand, in 1996, Vietnam Ministry of Defence made the decision to establish Center for Nuclear Medicine and Radiation Protecting (now becomes Military Institute of Medical Radiology and Oncology) with the main missions are research, applying radiation protecting methods and organizing treatments to radiation injured victims. To fulfill above main missions, with the help of Vietnam Atomic Energy Institute (VAEI), Vietnam Agency for Radiation and Nuclear Safety (VARANS), the doctors and staffs of our Institute have been participated in the international training courses and workshops that organized in Vietnam or in regional countries about emergency medical response to radiation accidents, they get valuable information, knowledge and documents from these courses and workshops. Depending on the principles of radiation emergency medical response to nuclear/ radiation accidents that International Atomic Energy Agency (IAEA) guided, and with the experience learned from other countries in Asia region, our Institute have been gradually improving on organization and curing processes for the radiation victims and also setting the preparedness for emergency medical response to radiation accidents if maybe they could occur. (author)

  6. The Miksova water power station

    International Nuclear Information System (INIS)

    2005-01-01

    This leaflet describes the Miksova water power station. The Miksova water power station is part of the second derived cascade of hydro power stations on the river Vah. It was built at the end of a huge development in Slovak hydro-energy in the late 1950's and the beginning of the 1960's. It is the second water power station on this derived cascade, which is situated downstream the Hricov reservoir and water power station. At the power station, three turbine sets with vertical Kaplan turbines are installed with a total power output of 3 x 31.2 = 93.6 MW. With this power output the Miksova water power station (Miksova I) was the biggest water power station in the Slovak Republic until the construction of Pumping water power station Liptovska Mara. And it is still the biggest channel water power station on the Vah so far. It was put into operation during the period 1963 to 1965. There are three turbine sets with Kaplan turbines from CKD Blansko, with a synchronous hydro-alternator installed in the power station. Their installed capacity is 93.6 MW in total and the projected annual production of electrical energy is 207 GWh. The turbines are fi ve-bladed (on the Hricov and Povazska Bystrica water power stations they are four-bladed) and the impeller wheel has a diameter of 4800 mm. They are designed for extension of the head from 24.1 to 22.21 m and each of them has an absorption capacity of 134 m 3 .s -1 nd a nominal operating speed of 2.08 m 3 .s -1 , runaway speed 4.9 m 3 .s -1 . Each synchronous hydro-alternator has a maximum power output of 31.2 MW, a nominal voltage of 10.5 kV and power factor cos φ of 0.8. Power from the power station is led out through 110 kV switchgear. The water power station operates under automatic turbine mode of operation with remote indication and control from the Dispatch Centre at Vodne elektrarne, in Trencin. From start of operation until the end of 2003 all three turbine sets operated for a total of 450,500 running hours and the

  7. Pumped energy transfer stations (STEP)

    International Nuclear Information System (INIS)

    Tournery, Jean-Francois

    2015-12-01

    As objectives of development are high for renewable energies (they are supposed to cover 50 per cent of new energy needs by 2035), pumped energy transfer stations are to play an important role in this respect. The author first discusses the consequences of the development of renewable energies on the exploitation of electric grids: issue of intermittency for some of them, envisaged solutions. Then, he addresses one of the solutions: the storage of electric power. He notices that increasing the potential energy of a volume of water is presently the most mature solution to face massive needs of the power system. Dams and pumped energy transfer stations represent now almost the whole installed storage power in the world. The author then presents these pumped energy transfer stations: principle, brief history (the first appeared in Italy and Switzerland at the end of the 1890's). He indicates the various parameters of assessment of such stations: maximum stored energy, installed power in pumping mode and turbine mode, time constant, efficiency, level of flexibility. He discusses economic issues. He describes and comments the operation of turbine-pump groups: ternary groups, reversible binary groups. He discusses barriers to be overcome and technical advances to be made for varying speed groups and for marine stations. He finally gives an overview (table with number of stations belonging to different power ranges, remarkable installations) of existing stations in China, USA, Japan, Germany, Austria, Spain, Portugal, Italy, Switzerland, France and UK, and indicate predictions regarding storage needs at the world level. Some data are finally indicated for the six existing French installations

  8. Plasma Hazards and Acceptance for International Space Station Extravehicular Activities

    Science.gov (United States)

    Patton, Thomas

    2010-09-01

    Extravehicular activity(EVA) is accepted by NASA and other space faring agencies as a necessary risk in order to build and maintain a safe and efficient laboratory in space. EVAs are used for standard construction and as contingency operations to repair critical equipment for vehicle sustainability and safety of the entire crew in the habitable volume. There are many hazards that are assessed for even the most mundane EVA for astronauts, and the vast majority of these are adequately controlled per the rules of the International Space Station Program. The need for EVA repair and construction has driven acceptance of a possible catastrophic hazard to the EVA crewmember which cannot currently be controlled adequately. That hazard is electrical shock from the very environment in which they work. This paper describes the environment, causes and contributors to the shock of EVA crewmembers attributed to the ionospheric plasma environment in low Earth orbit. It will detail the hazard history, and acceptance process for the risk associated with these hazards that give assurance to a safe EVA. In addition to the hazard acceptance process this paper will explore other factors that go into the decision to accept a risk including criticality of task, hardware design and capability, and the probability of hazard occurrence. Also included will be the required interaction between organizations at NASA(EVA Office, Environments, Engineering, Mission Operations, Safety) in order to build and eventually gain adequate acceptance rationale for a hazard of this kind. During the course of the discussion, all current methods of mitigating the hazard will be identified. This paper will capture the history of the plasma hazard analysis and processes used by the International Space Station Program to formally assess and qualify the risk. The paper will discuss steps that have been taken to identify and perform required analysis of the floating potential shock hazard from the ISS environment

  9. Shippingport Atomic Power Station decommissioning program and applied technology

    Energy Technology Data Exchange (ETDEWEB)

    Crimi, F P; Skavdahl, R E

    1985-01-01

    The Shippingport Station decommissioning project is the first decommissioning of a large scale nuclear power plant, and also the first nuclear power plant to be decommissioned which has continued the power operation as long as 25 years. The nuclear facilities which have been decommissioned so far have operated for shorter period and were small as compared with commercial power reactors, but the experience gained by those decommissionings as well as that gained by nuclear plant maintenance and modification has helped to establish the technology and cost basis for Shippingport and future decommissioning projects. In this paper, the current status of the preparation being made by the General Electric Co., its subcontractor and the US Department of Energy for starting the decommissioning phase of the Shippingport Atomic Power Station is described. Also remote metal cutting, decontamination, concrete removal, the volume reduction of liquids and solids and robotics which will be applied to the project are discussed. The Shippingport Station is a 72 MWe PWR plant having started operation in 1957, and permanently shut down in 1982, after having generated over 7.4 billion kWh of electricity.

  10. Tampa Electric Company Polk Power Station IGCC project: Project status

    Energy Technology Data Exchange (ETDEWEB)

    McDaniel, J.E.; Carlson, M.R.; Hurd, R.; Pless, D.E.; Grant, M.D. [Tampa Electric Co., FL (United States)

    1997-12-31

    The Tampa Electric Company Polk Power Station is a nominal 250 MW (net) Integrated Gasification Combined Cycle (IGCC) power plant located to the southeast of Tampa, Florida in Polk County, Florida. This project is being partially funded under the Department of Energy`s Clean Coal Technology Program pursuant to a Round II award. The Polk Power Station uses oxygen-blown, entrained-flow IGCC technology licensed from Texaco Development Corporation to demonstrate significant reductions of SO{sub 2} and NO{sub x} emissions when compared to existing and future conventional coal-fired power plants. In addition, this project demonstrates the technical feasibility of commercial scale IGCC and Hot Gas Clean Up (HGCU) technology. The Polk Power Station achieved ``first fire`` of the gasification system on schedule in mid-July, 1996. Since that time, significant advances have occurred in the operation of the entire IGCC train. This paper addresses the operating experiences which occurred in the start-up and shakedown phase of the plant. Also, with the plant being declared in commercial operation as of September 30, 1996, the paper discusses the challenges encountered in the early phases of commercial operation. Finally, the future plans for improving the reliability and efficiency of the Unit in the first quarter of 1997 and beyond, as well as plans for future alternate fuel test burns, are detailed. The presentation features an up-to-the-minute update on actual performance parameters achieved by the Polk Power Station. These parameters include overall Unit capacity, heat rate, and availability. In addition, the current status of the start-up activities for the HGCU portion of the plant is discussed.

  11. Nuclear power station main control room habitability

    International Nuclear Information System (INIS)

    Paschal, W.B.; Knous, W.S.

    1989-01-01

    The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews

  12. Pressurized-water-reactor station blackout

    International Nuclear Information System (INIS)

    Dobbe, C.A.

    1983-01-01

    The purpose of the Severe Accident Sequence Analysis (SASA) Program was to investigate accident scenarios beyond the design basis. The primary objective of SASA was to analyze nuclear plant transients that could lead to partial or total core melt and evaluate potential mitigating actions. The following summarizes the pressurized water reactor (PWR) SASA effort at the Idaho National Engineering Laboratory (INEL). The INEL is presently evaluating Unresolved Safety Issue A-44 - Station Blackout from initiation of the transient to core uncovery. The balance of the analysis from core uncovery until fission product release is being performed at Sandia National Laboratory (SNL). The current analyses involve the Bellefonte Nuclear Steam Supply System (NSSS), a Babcock and Wilcox (B and W) 205 Fuel Assembly (205-FA) raised loop design to be operated by the Tennessee Valley Authority

  13. Iodine filters in nuclear power stations

    International Nuclear Information System (INIS)

    Wilhelm, J.G.

    1977-04-01

    On the basis of calculated and recorded release rates of nuclear power plants, the significance of iodine releases in the invironmental impact relative to other nuclides is discussed. The release pathways for iodine in LWR-type reactors and the efficiency of various methods to lower the activity release are given. The airborne species of iodine are discussed with regard to their removal in iodine sorption filters and environmental impact. The technical status of iodine removal by means of iodine sorption filters is studied for normal operation and accident conditions in nuclear power stations on the basis of the data given in the relevant literature for the efficiency of a number of iodine sorption materials. The applicability of concepts for ventilation and containment and their influence on iodine filter systems are discussed. Design, structure, and testing of iodine sorption filters are treated in detail; recommendations for design are given, and failure sources are mentioned. (orig.) [de

  14. Complex Mobile Independent Power Station for Urban Areas

    Science.gov (United States)

    Tunik, A. A.; Tolstoy, M. Y.

    2017-11-01

    A new type of a complex mobile independent power station developed in the Department of Engineering Communications and Life-Support Systems of Irkutsk National Research Technical University, is presented in this article. This station contains only solar panel, wind turbine, accumulator, diesel generator and microbial fuel cell for to produce electric energy, heat pump and solar collector to generate heat energy and also wastewater treatment plant and new complex control system. The complex mobile independent power station is intended for full power supply of a different kind of consumers located even in remote areas thus reducing their dependence from centralized energy supply systems, decrease the fossil fuel consumption, improve the environment of urban areas and solve the problems of the purification of industrial and municipal wastewater.

  15. Exchange of pressurizer safeguarding system at Biblis nuclear power station

    International Nuclear Information System (INIS)

    Weber, D.; Hofbeck, W.

    1991-01-01

    Valves and piping of the pressurizer safeguarding system are exchanged and reset in such a way that they are suitable not only for discharging steam, but also for discharging a water-steam mixture and hot pressurized water; for the emergency measure of primary depressurization by hand (bleed) in the event of failure of the entire feedwater supply and station black-out, and in the event of operational transients with supposed failure of the reactor scram (ATWS). To achieve this, in addition to the requirements of the pressurizer discharging station, changes have to be made to the valve drive to dominate the water loads. During the 1990 inspection this exchange of the pressurizer discharging station was performed at the Biblis A unit as the first German plant. (orig.) [de

  16. The Paks Nuclear Power Station

    International Nuclear Information System (INIS)

    Erdosi, N.; Szabo, L.

    1978-01-01

    As the first stage in the construction of the Paks Nuclear Power Station, two units of 440 MW(e) each will be built. They are operated with two coolant loops each. The reactor units are VVER 440 type water-moderated PWR type heterogeneous power reactors designed in the Soviet Union and manufactured in Czechoslovakia. Each unit operates two Soviet-made K-220-44 steam turbines and Hungarian-made generators of an effective output of 220 MW. The output of the transformer units - also of Hungarian made - is 270 MVA. The radiation protection system of the nuclear power station is described. Protection against system failures is accomplished by specially designed equipment and security measures especially within the primary circuit. Some data on the power station under construction are given. (R.P.)

  17. Hungarian repeat station survey, 2010

    Directory of Open Access Journals (Sweden)

    Péter Kovács

    2013-03-01

    Full Text Available The last Hungarian repeat station survey was completed between October 2010 and February 2011. Declination, inclination and the total field were observed using one-axial DMI fluxgate magnetometer mounted on Zeiss20A theodolite and GSM 19 Overhauser magnetometer. The magnetic elements of the sites were reduced to the epoch of 2010.5 on the basis of the continuous recordings of Tihany Geophysical Observatory. In stations located far from the reference observatory, the observations were carried out in the morning and afternoon in order to decrease the effect of the distant temporal correction. To further increase the accuracy, on-site dIdD variometer has also been installed near the Aggtelek station, in the Baradla cave, during the survey of the easternmost sites. The paper presents the technical details and the results of our last campaign. The improvement of the accuracy of the temporal reduction by the use of the local variometer is also reported.

  18. Monitoring of nuclear power stations

    International Nuclear Information System (INIS)

    Ull, E.; Labudda, H.J.

    1987-01-01

    The purpose of the invention is to create a process for undelayed automated detection and monitoring of accidents in the operation of nuclear power stations. According to the invention, this problem is solved by the relevant local measurements, such as radiation dose, components and type of radiation and additional relevant meteorological parameters being collected by means of wellknown data collection platforms, these being transmitted via transmission channels by means of satellites to suitable worldwide situated receiving stations on the ground, being processed there and being evaluated to recognise accidents. The local data collection platforms are used in the immediate vicinity of the nuclear power station. The use of aircraft, ships and balloons as data collection systems is also intended. (HWJ)

  19. 47 CFR 73.1120 - Station location.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Station location. 73.1120 Section 73.1120... Rules Applicable to All Broadcast Stations § 73.1120 Station location. Each AM, FM, TV and Class A TV... be the geographical station location. [65 FR 30003, May 10, 2000] ...

  20. Multi-Unit Aspects of the Pickering Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Morison, W. G. [Atomic Energy of Canada Ltd, Sheridan Park, ON (Canada)

    1968-04-15

    The Pickering nuclear generating station is located on the north shore of Lake Ontario, about 20 miles east of the city of Toronto, Canada. The station has been planned and laid out on an eight-unit station, four units of which have now been authorized for construction. Each of these four units consists of a single heavy-water moderated and cooled CANDU-type reactor and auxiliaries coupled to a single tandem compound turbine generator with a net output of approximately 500 MW(e). The units are identical and are scheduled to come into operation at intervals of one year from 1970 to 1973. The station has been planned with central facilities for: administration maintenance laboratories, stores, change rooms, decontamination and waste management services. A common control centre, cooling water intake and discharge system, and spent fuel storage bay for four units has been arranged. A feature of the multi-unit station is a common containment system. Cost savings in building a number of identical units on the same site result from a single exclusion area, shared engineering costs, equipment purchase contracts for four identical components, and efficient use of construction plant. Operating cost savings are anticipated in the use of a common operating and maintenance staff and spare parts inventory. The plant has been arranged to minimize problems of operating, commissioning and constructing units at the same time on the same site. The layout and construction sequence have been arranged so that the first unit can be commissioned and operated with little or no interference from the construction forces working on succeeding units. During the construction phase barriers will be erected in the common control centre between operating control equipment and that being installed. Operations and construction personnel will enter the plant by separate routes and work in areas separated by physical barriers. (author)

  1. Developments of space station; Uchu station no kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    Hashimoto, H. [National Space Development Agency of Japan, Tokyo (Japan)

    1996-03-05

    This paper introduces the Japanese experiment module (JEM) in developing a space station. The JEM consists of systems of a pressurizing section, an exposure section, a pressurizing portion of a supply section, a manipulator and an exposure portion of the supply section. The pressurizing section circulates and controls air so that crews can perform experiments under pressurized environment. The exposure section is a part in which experiments are carried out under exposure environment. The supply section runs between a station and the ground, with required devices loaded on it. The manipulator performs attaching a payload for the exposure section and replaces experimental samples. The JEM undergoes a schedule of fabricating an engineering model, testing for a certification a prototype flight model, and putting the model on a flight. The pressurizing section, exposure section and manipulator are at the stage of system tests. Surveillance of the JEM and control of the experiments are carried out at the Tsukuba Space Center. The Center is composed of a space experiment building, a zero-gravity environment testing building, an astronaut training building, a space station operating building, and a space station testing building. 7 figs., 2 tabs.

  2. Space Station personal hygiene study

    Science.gov (United States)

    Prejean, Stephen E.; Booher, Cletis R.

    1986-01-01

    A personal hygiene system is currently under development for Space Station application that will provide capabilities equivalent to those found on earth. This paper addresses the study approach for specifying both primary and contingency personal hygiene systems and provisions for specified growth. Topics covered are system definition and subsystem descriptions. Subsystem interfaces are explored to determine which concurrent NASA study efforts must be monitored during future design phases to stay up-to-date on critical Space Station parameters. A design concept for a three (3) compartment personal hygiene facility is included as a baseline for planned test and verification activities.

  3. Evaluation of data from HEPA filter quality assurance testing stations

    International Nuclear Information System (INIS)

    Collins, J.T.; Bellamy, R.R.; Allen, J.R.

    1979-01-01

    In Revision 1 to Regulatory Guide 1.52, issued in July 1976, the NRC recommended that high efficiency particulate air (HEPA) filters for use in engineered safety features (ESF) atmosphere cleanup systems be visually inspected and dioctylphtalate (DOP) tested at either of two Department of Energy (DOE) operated QA Filter Testing Stations prior to their installation and use in commercial nuclear power plants. This practice was initiated because filter vendors were unable to consistently provide a HEPA filter that would meet the stringent requirements established by DOE and NRC and its predecessor the AEC. In 1977, the NRC staff undertook a program to revise Regulatory Guide 1.52 to reflect recently issued industry standards (e.g., ANSI N509 and N510) and current industry practices. Revision 2 to Regulatory Guide 1.52 was formally issued in March 1978. In conducting this review, the recommendation that HEPA filters, intended for use in ESF systems in commercial nuclear power plants, be routinely tested at the DOE-QA Filter Testing Stations was revaluated. As part of this evluation a detailed analysis of the filter test results recorded by the two QA Testing Stations during the period 1971 to 1977 was conducted. This paper summarizes the results of the analysis and explains the rationale for deleting the requirement that all HEPA filters intended for use in ESF systems be tested at the AQ Testing Station

  4. Commissioning and operation of the CEBAF end station refrigeration system

    International Nuclear Information System (INIS)

    Arenius, D.; Bevins, B.; Chronis, W.C.; Ganni, V.

    1996-01-01

    The CEBAF End Station Helium Refrigerator (ESR) System provides refrigeration at 80 K, 20 K and 4.5 K to three End Station experimental halls. The facility consists of a two stage helium screw compressor system, 4.5 K refrigerator, cryogen distribution valve box, and transfer lines to the individual experimental halls. The 4.5 K cold box and compressors were originally part of the ESCAR 1500 W, 4 K refrigeration system at Lawrence Berkeley Laboratory which was first commissioned in 1977. The compressors, 4.5 K cold box, and control system design were modified to adapt the plant for the requirements of the CEBAF experimental halls. Additional subsystems of cryogen distribution, transfer lines, warm gas management, and computer control interface were added. This paper describes the major plant subsystems, modifications, operational experiences and performance

  5. Shippingport Station Decommissioning Project (SSDP). A progress report

    International Nuclear Information System (INIS)

    Mullee, G.R.; Usher, J.M.

    1986-01-01

    The Shippingport Atomic Power Station was shutdown in October, 1982 by the Plant Operator, Duquesne Light Company, for decommissioning by the US Department of Energy. The planning for decommissioning was completed in September, 1983. In September, 1984 operational responsibility for the station was transferred to the DOE's Decommissioning Operations Contractor - the General Electric Company (assisted by an integrated subcontractor, MK Ferguson Company). Significant accomplishments to date include the completion of all prerequisites for decommissioning, the removal of asbestos from plant systems, loading of irradiated reactor components into the reactor vessel for shipment, the commencement of electrical deactivations and the commencement of piping/component removal. Decontamination and waste processing are progressing in support of the project schedule. The reactor vessel will be shipped as one piece on a barge for burial at Hanford, Washington. The final release of the site is scheduled for April, 1990. A technology transfer program is being utilized to disseminate information about the project

  6. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    Zagorski, J. F.

    1980-01-01

    At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

  7. The duty health physicist program at Byron Nuclear Power Station

    International Nuclear Information System (INIS)

    Goldsmith, D.G.; Carey, T.R.

    1987-01-01

    The Duty Health Physicist Program at Byron Station was established to deal with routine health physics tasks and provide an interface between frontline and upper radiation-chemistry management. The program consists of a weekly rotation of selected members of the health physics staff into the duty health physicist position to handle the assigned duty tasks. The tasks include, but are not limited to, daily isotopic and air sample review, effluent release package review, maximum permissible concentration calculations, dose approvals, as-low-as-reasonably-achievable action review of pending jobs, and general availability to answer questions and address problems in health-physics-related areas of plant operation. The daily attendance of the duty health physicist at the radiation-chemistry and station plan-of-the-day meetings has increased the overall presence and visibility of the health physics program to upper station management and other station departments. Since its inception in July of 1985, the Duty Health Physics Program has been a major contributor to the observed 50% reduction in reportable personnel errors in the radiation-chemistry department (based on personnel-error-related deviation reports and license event reports generated on the radiation-chemistry department at Byron Station). Although difficulty to quantify, other important benefits of this program are also discussed in this paper

  8. Remerschen nuclear power station with BBR pressurized water reactor

    International Nuclear Information System (INIS)

    Hoffmann, J.P.

    1975-01-01

    On the basis of many decades of successful cooperation in the electricity supply sector with the German RWE utility, the Grand Duchy of Luxemburg and RWE jointly founded Societe Luxembourgeoise d'Energie Nucleaire S.A. (SENU) in 1974 in which each of the partners holds a fifty percent interest. SENU is responsible for planning, building and operating this nuclear power station. Following an international invitation for bids on the delivery and turnkey construction of a nuclear power station, the consortium of the German companies of Brown, Boveri and Cie. AG (BBC), Babcock - Brown Boveri Reaktor GmbH (BBR) and Hochtief AG (HT) received a letter of intent for the purchase of a 1,300 MW nuclear power station equipped with a pressurized water reactor. The 1,300 MW station of Remerschen will be largely identical with the Muelheim-Kaerlich plant under construction by the same consortium near Coblence on the River Rhine since early 1975. According to present scheduling, the Remerschen nuclear power station could start operation in 1981. (orig.) [de

  9. Modelling and controlling hydropower plants

    CERN Document Server

    Munoz-Hernandez, German Ardul; Jones, Dewi Ieuan

    2013-01-01

    Hydroelectric power stations are a major source of electricity around the world; understanding their dynamics is crucial to achieving good performance.  Modelling and Controlling Hydropower Plants discusses practical and well-documented cases of modelling and controlling hydropower station modelling and control, focussing on a pumped storage scheme based in Dinorwig, North Wales.  Single-input-single-output and multiple-input-multiple-output models, which cover the linear and nonlinear characteristics of pump-storage hydroelectric power stations, are reviewed. The most important dynamic features are discussed, and the verification of these models by hardware in the loop simulation is described. To show how the performance of a pump-storage hydroelectric power station can be improved, classical and modern controllers are applied to simulated models of the Dinorwig power plant. These include PID, fuzzy approximation, feed-forward and model-based predictive control with linear and hybrid prediction models. Mod...

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

    International Nuclear Information System (INIS)

    Subudhi, M.; Carroll, D.P.; Kasturi, S.

    1994-01-01

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

  11. Improved monolithic reinforced concrete construction for nuclear power stations

    International Nuclear Information System (INIS)

    Guenther, P.; Fischer, K.

    1983-01-01

    Experience has shown that in applying monolithic reinforced concrete in nuclear power plant construction the following auxiliary means are useful: measuring sheets in assembling, welding gauges for reaching high tolerance accuracies of prefabricated reinforced concrete members, suitable lining materials, formwork anchorage and formwork release agents, concrete workability agents, mechanized procedures for finishing and assembling. These means were successfully tested in constructing the Greifswald nuclear power station

  12. Implementing an effective self-assessment program at Millstone Station

    International Nuclear Information System (INIS)

    Venable, J.M.

    1996-01-01

    The nuclear industry is becoming ever more reliant on self-assessments to ensure operational safety and to meet our increasingly competitive business challenges. This trend includes utility assessments modeled after major U.S. Nuclear Regulatory Commission (NRC) inspections such as safety system functional inspections (SSFI). Utility conducted SSFIs leveraged the limited resources of the NRC, making possible many evaluations that simply would not have been conducted otherwise. This report describes a self-assessment program at the Millstone Station plant

  13. Distributed systems for the protection of nuclear stations

    International Nuclear Information System (INIS)

    Jover, P.

    1980-01-01

    The advantages of distributed control systems usually mentioned are improved exploitation, cost reduction, and adaptation to changes in technology. These advantages are obviously very interesting for nuclear power plant applications, and many such systems have been proposed. This note comments on the application of the distributed system concept to protection systems - what should be distributed - and closes with a brief description of a protection system based on microprocessors for pressurized water stations being built in France. (auth) [fr

  14. Remote input/output station

    CERN Multimedia

    1972-01-01

    A general view of the remote input/output station installed in building 112 (ISR) and used for submitting jobs to the CDC 6500 and 6600. The card reader on the left and the line printer on the right are operated by programmers on a self-service basis.

  15. Merchant funding for power stations

    International Nuclear Information System (INIS)

    Johnston, B.; Bartlam, M.

    1997-01-01

    The next frontier for project finance is merchant generation: the financing of IPPs without long-term offtake contracts. Banks are just beginning to finance merchant generation power stations. One of the first was Destec's Indian Queens project in Cornwall, UK. Bruce Johnston and Martin Bartlam of Wilde Sapte discuss the project. (UK)

  16. The Medicina Station Status Report

    Science.gov (United States)

    Orfei, Alessandro; Orlati, Andrea; Maccaferri, Giuseppe

    2013-01-01

    General information about the Medicina Radio Astronomy Station, the 32-m antenna status, and the staff in charge of the VLBI observations is provided. In 2012, the data from geodetic VLBI observations were acquired using the Mark 5A recording system with good results. Updates of the hardware were performed and are briefly described.

  17. "Artificial intelligence" at streamgaging stations

    Science.gov (United States)

    R. B. Thomas

    1985-01-01

    Two types of problems are related to collecting hydrologic data at stream gaging stations. One includes the technical/logistical questions associated with measuring and transferring data for processing. Effort spent on these problems ranges from improving devices for sensing data to using electronic data loggers.

  18. Automating Space Station operations planning

    Science.gov (United States)

    Ziemer, Kathleen A.

    1989-01-01

    The development and implementation of the operations planning processes for the Space Station are discussed. A three level planning process, consisting of strategic, tactical, and execution level planning, is being developed. The integration of the planning procedures into a tactical planning system is examined and the planning phases are illustrated.

  19. Performance of Existing Hydrogen Stations

    Energy Technology Data Exchange (ETDEWEB)

    Sprik, Samuel [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Kurtz, Jennifer M [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Ainscough, Christopher D [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Saur, Genevieve [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Peters, Michael C [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2017-12-01

    In this presentation, the National Renewable Energy Laboratory presented aggregated analysis results on the performance of existing hydrogen stations, including performance, operation, utilization, maintenance, safety, hydrogen quality, and cost. The U.S. Department of Energy funds technology validation work at NREL through its National Fuel Cell Technology Evaluation Center (NFCTEC).

  20. Space Station power system issues

    International Nuclear Information System (INIS)

    Giudici, R.J.

    1985-01-01

    Issues governing the selection of power systems for long-term manned Space Stations intended solely for earth orbital missions are covered briefly, drawing on trade study results from both in-house and contracted studies that have been conducted over nearly two decades. An involvement, from the Program Development Office at MSFC, with current Space Station concepts began in late 1982 with the NASA-wide Systems Definition Working Group and continued throughout 1984 in support of various planning activities. The premise for this discussion is that, within the confines of the current Space Station concept, there is good reason to consider photovoltaic power systems to be a venerable technology option for both the initial 75 kW and 300 kW (or much greater) growth stations. The issue of large physical size required by photovoltaic power systems is presented considering mass, atmospheric drag, launch packaging and power transmission voltage as being possible practicality limitations. The validity of searching for a cross-over point necessitating the introduction of solar thermal or nuclear power system options as enabling technologies is considered with reference to programs ranging from the 4.8 kW Skylab to the 9.5 gW Space Power Satellite