WorldWideScience

Sample records for auxiliary power plants

  1. Start-up of a power unit of a thermal power plant auxiliary system with supply from a hydropower plant

    OpenAIRE

    Zbigniew Lubośny; Krzysztof Dobrzyński; Jacek Klucznik

    2013-01-01

    This article discusses the issues related to a power unit of a thermal power plant start-up with the use of a hydropower plant. Hydropower plant can supply and will enable start-up of auxiliary equipment in a power unit of a thermal power plant. Due to high capacity of auxiliary drives, startup of auxiliaries in a thermal power plant after blackout (and boiler shutdown) is not possible from emergency energy sources in the power plant. In such a case an external electricity source with high ca...

  2. Start-up of a power unit of a thermal power plant auxiliary system with supply from a hydropower plant

    Directory of Open Access Journals (Sweden)

    Zbigniew Lubośny

    2013-09-01

    Full Text Available This article discusses the issues related to a power unit of a thermal power plant start-up with the use of a hydropower plant. Hydropower plant can supply and will enable start-up of auxiliary equipment in a power unit of a thermal power plant. Due to high capacity of auxiliary drives, startup of auxiliaries in a thermal power plant after blackout (and boiler shutdown is not possible from emergency energy sources in the power plant. In such a case an external electricity source with high capacity is required.

  3. Using auxiliary gas power for CCS energy needs in retrofitted coal power plants

    OpenAIRE

    Bashadi, Sarah O.; Herzog, Howard J.

    2011-01-01

    Adding post-combustion capture technology to existing coal-fired power plants is being considered as a near-term option for mitigating CO[subscript 2] emissions. To supply the thermal energy needed for CO[subscript 2] capture, much of the literature proposes thermal integration of the existing coal plant’s steam cycle with the capture process’ stripper reboiler. This paper examines the option of using an auxiliary natural gas turbine plant to meet the energetic demands of carbon capture and c...

  4. ASCERTAINMENT OF ELECTRIC-SUPPLY SCHEMES RELIABILITY FOR THE ATOMIC POWER PLANT AUXILIARIES

    Directory of Open Access Journals (Sweden)

    A. L. Starzhinskij

    2015-01-01

    Full Text Available The paper completes ascertainment of electrical-supply scheme reliability for the auxiliaries of a nuclear power plant. Thereat the author considers the system behavior during the block normal operation, carrying out current maintenance, and capital repairs in combination with initiating events. The initiating events for reactors include complete blackout, i.e. the loss of outside power supply (normal and reserve; emergency switching one of the working turbogenerators; momentary dumping the normal rating to the level of auxiliaries with seating the cutout valve of one turbo-generator. The combination of any initiating event with the repairing mode in case of one of the system elements failure should not lead to blackout occurrence of more than one system of the reliable power supply. This requirement rests content with the help of the reliable power supply system self-dependence (electrical and functional and the emergency power-supply operational autonomy (diesel generator and accumulator batteries.The reliability indicators of the power supply system for the nuclear power plant auxiliaries are the conditional probabilities of conjoined blackout of one, two, and three sections of the reliable power supply conditional upon an initiating event emerging and the blackout of one, two, and three reliable power-supply sections under the normal operational mode. Furthermore, they also are the blackout periodicity of one and conjointly two, three, and four sections of normal operation under the block normal operational mode. It is established that the blackout of one bus section of normal operation and one section of reliable power-supply system of the auxiliaries that does not lead to complete blackout of the plant auxiliaries may occur once in three years. The probability of simultaneous power failure of two or three normal-operation sections and of two reliable power-supply sections during the power plant service life is unlikely.

  5. Multicriteria optimization of the investment in the auxiliary services of thermal power plants: A case study

    International Nuclear Information System (INIS)

    Highlights: • A multiobjective optimization model to improve the efficiency of auxiliary services. • Economic (investment and NPV) and energy saving criteria are considered. • Evolutionary multiobjective optimization is used for solving the problem with a DM. • A case study based on a real 1100 MW coal-fired power plant is considered. • Results show very profitable solutions from the economic and energy points of view. - Abstract: Thermal power plants have traditionally operated at rated power as base load, but nowadays they operate at partial loads because of the new situation of the electricity market. These plants have raised their auxiliary services consumption because, in most of the cases, the auxiliaries were not designed to efficiently operate at partial loads. This paper presents a multiple criteria study about the efficiency improvement of the auxiliary services. We consider the economic investment and the net present value, as economic criteria, together with the energy saving criterion. In the multiobjective model proposed, the energy model is validated using several measures taken in a 1100 megawatts coal power plant. Besides, the multiobjective problem associated to the case study considered is solved using evolutionary multiobjective optimization and considering preference information. The results obtained conclude that a significant efficiency improvement of the auxiliary services can be achieved by means of the improvement strategies considered. Indeed, the high net present values reached indicate that the investments required by the different solutions are really profitable from the economic perspective. Therefore, investing money in the efficiency improvement of the auxiliary services represents a very profitable option for improving the operation of power plants at partial loads

  6. Analysis of design of auxiliary system of Booshehr Nuclear Power Plant

    International Nuclear Information System (INIS)

    Power plant's internal auxiliary system has an important role in its safety operation. Because of the decay heat and safety aspects in the nuclear power plants, this role is more important. In this thesis, operation of the nuclear power plant with PWR reactor is studied and deferent nuclear systems described. In the next section all electrical loads in the Booshehr Nuclear Power Plant identified and feeding methods of each load is determined. by use of the single line diagram of the internal auxiliary system, the nominal rating of all electrical devices as transformers, inverters, Ups, diesel generators and etc. is determined. In the following, short circuit calculations performed and by above conclusion, rating values of circuit breakers is determined. At last the starting problems of electrical motors is studied and the results of motor's behavior at starting moment is discussed

  7. A reliability centered maintenance model applied to the auxiliary feedwater system of a nuclear power plant

    International Nuclear Information System (INIS)

    The main objective of maintenance in a nuclear power plant is to assure that structures, systems and components will perform their design functions with reliability and availability in order to obtain a safety and economic electric power generation. Reliability Centered Maintenance (RCM) is a method of systematic review to develop or optimize Preventive Maintenance Programs. This study presents the objectives, concepts, organization and methods used in the development of RCM application to nuclear power plants. Some examples of this application are included, considering the Auxiliary Feedwater System of a generic two loops PWR nuclear power plant of Westinghouse design. (author)

  8. Equipment Reliability Improvement for Koeberg Nuclear Power Plant Auxiliary Feedwater System

    International Nuclear Information System (INIS)

    This paper investigated how the performance of the Koeberg Auxiliary Feedwater System could be improved using the 'maintenance rule'. As a conclusion, this paper figured out AFWS pumps and the TDP control circuit need special attention in improving the reliability of the AFWS, this lead to an improved maintenance strategy for the system. The purpose of this study is to apply maintenance rule to enhance the Auxiliary Feedwater System (AFWS) maintenance strategy at Koeberg Nuclear Power Plant (KNPP). Currently, Koeberg AFWS health status is red, needing an improvement. This study seeks to use maintenance rule to identify components that enable AFWS to fulfill its essential functions so as to focus maintenance resources and have the greatest beneficial impact on improving reliability and availability of the system

  9. Seismic Back Calculation of an Auxiliary Building of the Nuclear Power Plant Muehleberg, Switzerland

    International Nuclear Information System (INIS)

    The auxiliary storage building of the Muehleberg nuclear power plant houses all the equipment for checking, intermediate storage and the treatment of all solid, liquid and gas products deriving from the operation of the plant, which may have been exposed to radiation. Due to the systems installed in the building it has to resist an earthquake of intensity level OBE (Operating Basis Earthquake). A corresponding verification was not carried out when the plant was constructed. To fulfil the requirements of the regulatory commission (HSK) the seismic safety of the storage facility had to undergo a detailed investigation. The following studies were made within the framework of this investigation: preparation of a concept; specifying the most important aspects and boundary conditions; calculation of the frequency-dependent impedance function of the ground with 3-D soil and foundation computational models for different depths of embedment; execution of the soil-structure interaction analysis with 3-D lumped mass models; preparation of a refined 3-D finite element model of the structure; verification of the model by checking the masses; execution of the modal analysis to determine the dynamic behaviour; execution of the static analysis with the operational loads; execution of the seismic analysis using the response spectrum method; superposition of stresses from the static and seismic analyses; execution of the geotechnical stability analyses; execution of the local stress and bearing capacity verifications; determination of the floor response spectra. The results are in agreement with observations from real earthquakes, which is a good indicator of the reliability of the methods employed and the computational models

  10. A CAE package for design of auxiliary buildings in nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power plants have a large number of auxiliary buildings housing various services and control systems in addition to the main reactor building. These are usually of the framed construction of two or three floors falling under seismic class I or II. Class I structures have to be qualified for seismic forces of intensity as given by SSE (safe shutdown earthquake) for three orthogonal components acting simultaneously while class II structures need to be qualified for seismic forces of intensity as given by OBE (operating basis earthquake) for two component motion-one horizontal and one vertical acting simultaneously. The seismic analysis of these buildings is carried out using the BLOCK model. For the analysis of three component motion, USNRC R.G. 1.92 permits time history method of analysis and timewise combination of responses of the three components in the proper phases. However, such a method of analysis is uneconomical for the buildings in question, more so when the layouts of such buildings during the planning phases undergo quite a few revisions necessitating reanalysis. As such, the response spectrum method of analysis is adopted for each directional component and the responses to the three component excitation are combined by adopting the SRSS criteria

  11. Aging and service wear of auxiliary feedwater pumps for PWR nuclear power plants

    International Nuclear Information System (INIS)

    This paper describes investigations on auxiliary feedwater pumps being done under the Nuclear Plant Aging Research (NPAR) Program. Objectives of these studies are: to identify and evaluate practical, cost-effective methods for detecting, monitoring, and assessing the severity of time-dependent degradation (aging and service wear); recommend inspection and maintenance practices; establish acceptance criteria; and help facilitate use of the results. Emphasis is given to identifying and assessing methods for detecting failure in the incipient stage and to developing degradation trends to allow timely maintenance, repair or replacement actions. 3 refs

  12. Auxiliary feedwater system risk-based inspection guide for the Virgil C. Summer Nuclear Power Plant

    International Nuclear Information System (INIS)

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the emergency/auxiliary feedwater (EFW/AFW) system at press water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses costing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify genetic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Virgil C. Summer plant was selected as one m a series of plants for study. The product of this effort is a priority listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at Virgil C. Summer plant

  13. Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

    International Nuclear Information System (INIS)

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant

  14. Experimental simulation of a light aircraft crash on to a nuclear power plant auxiliary building roof

    International Nuclear Information System (INIS)

    The experiments described were conducted at a reduced scale with geometric dimensions of prototype structures of one-fifth full size. The target was based on the auxiliary buildings for the proposed Sizewell PWR. Descriptions of the simulated aircraft model and the test panels are given, together with the instrumentation. Details are given of the test programme and the results are summarized and discussed. Comparison is made of the model aircraft tests with an equivalent hard missile impact. (U.K.)

  15. Lessons learned from full-scale vibration tests on nuclear power plant auxiliary structure in Switzerland

    International Nuclear Information System (INIS)

    The Beznau Nuclear Power Plant is located in northern Switzerland. The plant is owned and operated by the Nordostschweizerische Kraftwerke AG (NOK) in Baden, Switzerland. It is a twin unit plant (2 x 350 MWe) which was designed in the early 1960's and placed into commercial operation between 1969 and 1971. In connection with a major backfit project, which will improve the safety of the plant against external events, the free-standing boric water tanks had to be relocated and were replaced by two boric water tanks in a new building (the so called BOTA-building). It enabled to plan and perform full scale vibration tests.The scope of experimental investigation was to determine the eigenfrequencies and damping values for fundamental soil-structure interaction. The vibration tests allowed identification of the important modes of the soil-structure system in the range 3 to 15 Hz. The excitation was strung enough to generate accelerations in the structure comparable to those of a small earthquake. From the comparisons of computed and measured results it is concluded that the rocking frequency can be reasonably well predicted by either Finite Element or Lumped Parameter models with springs simulating the soil-foundation stiffness, provided in the case of the latter the embedment is taken into account. The prediction of the amplitude of structural response appears to be more difficult, as shown by the differences in the mode shapes. In the frequency range 8 to 10 Hz the agreement between computed and test results was less satisfactory. The actual structural behaviour turned out to be more complex than expected and needs further investigation with the aid of more refined models for the soil-structure system

  16. Hovercraft auxiliary power units (APUs)

    Energy Technology Data Exchange (ETDEWEB)

    Russell, B.J.

    1983-08-01

    Auxiliary power units (APU) manufactured by British firms for use in hovercraft are characterized. Both diesel and gas-turbine APUs are found to be well suited to the demands of this application. The design features, dimensions, performance data, and installation requirements are discussed for the SS 90, SS 923, DA-1, BA-1, HM 5, and Gevaudan 9 APUs, as well as the TRS 18 gas-turbine smoke generator. The progress made in improving the fuel efficiency of gas turbines and reducing the weight of diesel engines is considered significant.

  17. Vertical vibration test results of auxiliary building of the No. 1 Genkai nuclear power plant utilizing explosion test of excavating base rocks of the No. 2 plant

    International Nuclear Information System (INIS)

    The vertical vibration behavior of the auxiliary building of the No. 1 Genkai nuclear power plant was examined, utilizing the explosion test of excavation for the No. 2 plant, about 60 m apart from the auxiliary building. The explosive from 2.25 to 33.8 kg was used for simultaneous explosion and 13.4 to 47.4 kg for stepwise explosions, and the tests of ten explosions were conducted, divided into three cases. Concerning the test results, the wave forms were obtained at many points in the auxiliaty building within about one second after explosion. The first mode natural frequency was about 10 - 25 Hz, and the damping coefficient was 1 - 10%. The elastic behavior and about two times amplifying response at the top as compared to the basement were observed in the vibration of the building. The local frequency in the vertical vibration was different according to the individual points in the building, as the building has large area and several floors with complicated structures. The running spectra, Fourier spectra and power spectra were obtained experimentally. On the other hand, the numerical analysis was conducted using the particle system model, and compared to the experimental results, and the calculated values were about 1.5 - 2.0 times as large as the experimental values in the maximum responses. As for the experiment, the horizontal vibration behavior was also measured, which showed a little different vibrating characteristic curves. This experiment was effective to get the qualitative knowledge for the vertical vibration behavior of the auxiliary building in a nuclear power plant. (Nakai, Y.)

  18. Safety analysis and justification for modification of auxiliary feed-water system in Daya Bay Nuclear Power Plant

    International Nuclear Information System (INIS)

    The major feed-water line break accident is re-analyzed, which is based on Guangdong Daya Bay nuclear power station final safety analysis report, to justify the impacts of the decreasing of auxiliary feed-water flow rate on the safety margin in Daya Bay. The results showed that the accident analysis can meet the demands of acceptance criteria with the auxiliary feed-water flowrate decreasing from 45 m3/h to 41.8 m3/h, and enough safety margin is still retained

  19. Auxiliary power unit for moving a vehicle

    Science.gov (United States)

    Akasam, Sivaprasad; Johnson, Kris W.; Johnson, Matthew D.; Slone, Larry M.; Welter, James Milton

    2009-02-03

    A power system is provided having at least one traction device and a primary power source configured to power the at least one traction device. In addition, the power system includes an auxiliary power source also configured to power the at least one traction device.

  20. Optimizationin Operational Analysis of Auxiliary Steam System in Thermal Power Plant%火力发电厂辅汽系统优化运行分析

    Institute of Scientific and Technical Information of China (English)

    王乃军; 白秀春; 王俊俊

    2015-01-01

    For choosing different steam source for the auxiliary steam system in Inner Mongolia Daihai Electric Power Generation Co.,Ltd., carry on the quantitative analysis to the influence of the unit efficiency, the result is the most economical when choosing No.4 extraction steam of second unit supplying, while slightly economical as using second unit cold reheater as first unit. According to the results of the analysis, it provides a theoretical basis and guidance for selecting the source of auxiliary steam in power plants, so as to achieve the purpose of saving energy and reducing consumption, improve the operation efficiency. At the same time, based on the actual operating mode, unit start-up and shutdown, accident conditions, combined with different seasons and temperature, auxiliary steam consumption, it proposes operation precautions.%对内蒙古岱海发电有限责任公司辅助蒸汽系统选择不同供汽汽源时,机组运行经济性受到的影响进行了定量分析,认为由二期机组四段抽汽供汽经济性最优,由二期机组冷段再热蒸汽供汽的经济性略优于由一期机组冷段再热蒸汽供汽。并结合机组实际运行方式、机组启停方式及机组发生事故时的运行情况等,根据不同季节环境温度及各辅汽用户用汽量情况,提出辅汽系统优化运行注意事项。

  1. Vacuum switchgear for power station auxiliary switchboards

    International Nuclear Information System (INIS)

    Sizewell B is the first UK power station in which vacuum switchgear is used for the auxiliary switchboards. Previously the 3.3kV, 6.6kV or 11kV switchgear has used air-break circuit breakers and fused air-break contactors, known as motor starting devices or fused switching devices (FSD). The use of vacuum interrupters is therefore a new technology in this application, although it has been established in the UK distribution network and in industrial installations from the mid 1970s. Vacuum switchgear was already in use in the USA for power station auxiliary switchgear at the time that it was proposed for Sizewell B. The Sizewell B high voltage auxiliary switchgear comprises eight Unit and Station Auxiliary Switchboards at 3.3kV and 11kV, and four 3.3kV Essential Switchboards for the essential safety related circuits, making a total of 65 circuit breakers plus FSD panels. (Author)

  2. Solid Oxide Fuel Cell Auxiliary Power Unit

    International Nuclear Information System (INIS)

    Solid Oxide Fuel Cell (SOFC) is an attractive, efficient, clean source of power for transportation, military, and stationary applications. Delphi has pioneered its application as an auxiliary Power Unit (APU) for transportation. Delphi is also interested in marketing this technology for stationary applications. Its key advantages are high efficiency and compatibility with gasoline, natural gas and diesel fuel. It's consistent with mechanizations that support the trend to low emissions. Delphi is committed to working with customers and partners to bring this novel technology to market

  3. Effects of auxiliary source connections in multichip power module

    DEFF Research Database (Denmark)

    Li, Helong; Munk-Nielsen, Stig; Beczkowski, Szymon;

    2016-01-01

    Auxiliary source bond wires and connections are widely used to in the power module with paralleled MOSFETs or IGBTs. This paper investigates the working mechanism and the effects of the auxiliary source connections in multichip power modules. It reveals that the auxiliary source connections cannot...

  4. A reliability centered maintenance model applied to the auxiliary feedwater system of a nuclear power plant; Um modelo de manutencao centrada em confiabilidade aplicada ao sistema de agua de alimentacaco auxiliar de uma usina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Jefferson Borges

    1998-01-15

    The main objective of maintenance in a nuclear power plant is to assure that structures, systems and components will perform their design functions with reliability and availability in order to obtain a safety and economic electric power generation. Reliability Centered Maintenance (RCM) is a method of systematic review to develop or optimize Preventive Maintenance Programs. This study presents the objectives, concepts, organization and methods used in the development of RCM application to nuclear power plants. Some examples of this application are included, considering the Auxiliary Feedwater System of a generic two loops PWR nuclear power plant of Westinghouse design. (author)

  5. Dedicated auxiliary power units for Hybrid Electric Vehicles

    NARCIS (Netherlands)

    Mourad, S.; Weijer, C.J.T. van de

    1998-01-01

    The use of a dedicated auxiliary power unit is essential to utilize the potential that hybrid vehicles offer for efficient and ultra-clean transportation. An example of a hybrid project at the TNO Road-Vehicles Research Institute shows the development and the results of a dedicated auxiliary power u

  6. Orbiter Auxiliary Power Unit Flight Support Plan

    Science.gov (United States)

    Guirl, Robert; Munroe, James; Scott, Walter

    1990-01-01

    This paper discussed the development of an integrated Orbiter Auxiliary Power Unit (APU) and Improved APU (IAPU) Flight Suuport Plan. The plan identifies hardware requirements for continued support of flight activities for the Space Shuttle Orbiter fleet. Each Orbiter vehicle has three APUs that provide power to the hydraulic system for flight control surface actuation, engine gimbaling, landing gear deployment, braking, and steering. The APUs contain hardware that has been found over the course of development and flight history to have operating time and on-vehicle exposure time limits. These APUs will be replaced by IAPUs with enhanced operating lives on a vehicle-by-vehicle basis during scheduled Orbiter modification periods. This Flight Support Plan is used by program management, engineering, logistics, contracts, and procurement groups to establish optimum use of available hardware and replacement quantities and delivery requirements for APUs until vehicle modifications and incorporation of IAPUs. Changes to the flight manifest and program delays are evaluated relative to their impact on hardware availability.

  7. Indirect combustion noise of auxiliary power units

    Science.gov (United States)

    Tam, Christopher K. W.; Parrish, Sarah A.; Xu, Jun; Schuster, Bill

    2013-08-01

    Recent advances in noise suppression technology have significantly reduced jet and fan noise from commercial jet engines. This leads many investigators in the aeroacoustics community to suggest that core noise could well be the next aircraft noise barrier. Core noise consists of turbine noise and combustion noise. There is direct combustion noise generated by the combustion processes, and there is indirect combustion noise generated by the passage of combustion hot spots, or entropy waves, through constrictions in an engine. The present work focuses on indirect combustion noise. Indirect combustion noise has now been found in laboratory experiments. The primary objective of this work is to investigate whether indirect combustion noise is also generated in jet and other engines. In a jet engine, there are numerous noise sources. This makes the identification of indirect combustion noise a formidable task. Here, our effort concentrates exclusively on auxiliary power units (APUs). This choice is motivated by the fact that APUs are relatively simple engines with only a few noise sources. It is, therefore, expected that the chance of success is higher. Accordingly, a theoretical model study of the generation of indirect combustion noise in an Auxiliary Power Unit (APU) is carried out. The cross-sectional areas of an APU from the combustor to the turbine exit are scaled off to form an equivalent nozzle. A principal function of a turbine in an APU is to extract mechanical energy from the flow stream through the exertion of a resistive force. Therefore, the turbine is modeled by adding a negative body force to the momentum equation. This model is used to predict the ranges of frequencies over which there is a high probability for indirect combustion noise generation. Experimental spectra of internal pressure fluctuations and far-field noise of an RE220 APU are examined to identify anomalous peaks. These peaks are possible indirection combustion noise. In the case of the

  8. Power consumption of the ASCV and auxiliary equipment

    DEFF Research Database (Denmark)

    Pedersen, Knud Ole Helgesen; Pedersen, Jørgen Kaas

    1998-01-01

    Operating an ASCV requires power - to cover the losses in the ASCV itself and to run auxiliary equipment. It is necessary to take this power consumption into account when considering the economical aspects of installing an ASCV.Field measurements of this consumption of the ASCV in Rejsby Hede are...

  9. Space Shuttle Orbiter auxiliary power unit status

    Science.gov (United States)

    Reck, M.; Loken, G.; Horton, J.; Lukens, W.; Scott, W.; Baughman, J.; Bauch, T.

    An overview of the United States Space Shuttle Orbiter APU, which provides power to the Orbiter vehicle hydraulic system, is presented. Three complete APU systems, each with its own separate fuel system, supply power to three dedicated hydraulic systems. These in turn provide power to all Orbiter vehicle critical flight functions including launch, orbit, reentry, and landing. The basic APU logic diagram is presented. The APU includes a hydrazine-powered turbine that drives a hydraulic pump and various accessories through a high-speed gearbox. The APU also features a sophisticated thermal management system designed to ensure safe and reliable operation in the various launch, orbit, reentry, and landing environments.

  10. Disturbance in the power system caused by auxiliary DC installation failure of switchyard

    Energy Technology Data Exchange (ETDEWEB)

    Mesic, M. [HEP Transmission System Operator, Zagreb (Croatia); Tesnjak, S.; Skok, S. [Zagreb Univ. (Croatia). Faculty of Electrical Engineering and Computing

    2008-07-01

    Auxiliary direct current (DC) installation failures can lead to outages in power plants and compromise the security of power systems. In this study, a simplified stationary model was used to simulate an auxiliary DC installation in a switchyard. The aim of the study was to evaluate new International Electrotechnical Commission (IEC) standards for auxiliary DC installation dimensioning and analysis. Criteria included the dimensioning and selection of batteries; the calculation of conductor heating; voltage drop calculations; conductor squares in relation to permanent currents; and the evaluation of protection elements. The new standards were compared with the previous auxiliary system installation methodology. Results of the study suggested that the new standard has introduced significant improvements in short circuit current calculation. Laboratory tests for the measurement of short circuits showed that the active network has less of an impact on the auxiliary system than previous measuring methods. Alterations to the IEC standard will be required as a result of limitations to the short circuit current and new rectifier technology. Results of the study will be used to develop a new model and scheme for dimensioning and analyzing auxiliary DC installations. 9 refs., 4 tabs., 5 figs.

  11. 40 CFR 1033.510 - Auxiliary power units.

    Science.gov (United States)

    2010-07-01

    ... locomotive is equipped with an auxiliary power unit (APU) that operates during an idle shutdown mode, you must account for the APU's emissions rates as specified in this section, unless the APU is part of an... emission rate (g/hr) as specified in § 1033.530. Add the APU emission rate (g/hr) that you determine...

  12. Green Propulsion Auxiliary Power Unit Demonstration at MSFC

    Science.gov (United States)

    Robinson, Joel W.

    2014-01-01

    MSFC has embarked on use of green propellant replacement of hydrazine for a variety of applications. This paper focused on activities for auxiliary power unit but MSFC is actively investigating use of green propellants for thruster applications. MSFC is interested in partnership with the international community to address the infusion of green propellant into greater use.

  13. Nuclear power plant erection

    International Nuclear Information System (INIS)

    The erection of a nuclear power plant covers all the installation operations related to mechanical and electrical equipment in buildings designed for this specific purpose. Some of these operations are described: erection of the nuclear boiler, erection work carried out in the building accomodating the nuclear auxiliary and ancillary equipment and the methods and the organization set up in order to carry out this work satisfactorily are analyzed

  14. 14 CFR 33.96 - Engine tests in auxiliary power unit (APU) mode.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Engine tests in auxiliary power unit (APU... Engine tests in auxiliary power unit (APU) mode. If the engine is designed with a propeller brake which... in operation, and remain stopped during operation of the engine as an auxiliary power unit (“APU...

  15. 20--500 watt AMTEC auxiliary electric power system

    Energy Technology Data Exchange (ETDEWEB)

    Ivanenok, J.F. III; Sievers, R.K. [Advanced Modular Power Systems, Inc., Ann Arbor, MI (United States)

    1996-12-31

    Numerous design studies have been completed on Alkali Metal Thermal to Electric Converter (AMTEC) power systems for space applications demonstrating their substantial increase in performance. Recently design studies have been initiated to couple AMTEC power conversion with fossil fueled combustion systems. This paper describes the results of a Phase 1 SBIR effort to design an innovative, efficient, reliable, long life AMTEC Auxiliary Electric Power System (AEPS) for remote site applications (20--500 watts). The concept uses high voltage AMTEC cells, each containing 7 to 9 small electrolyte tubes, integrated with a combustor and recuperator. These multi-tube AMTEC cells are low cost, reliable, long life static converters. AMTEC technology is ideal for auxiliary electric power supplies that must operate reliably over a broad range of temperatures, fuel sources, power levels, and operational specifications. The simplicity, efficiency (20% systems) and modularity of this technology allow it to fill applications as varied as light-weight backpacks, remote site power supplies, and military base power. Phase 1 demonstrated the feasibility of a 20% system design, and showed that the development needs to focus on identifying long life AMTEC cell components, determining the AMTEC cell and system reliability, and demonstrating that a 20 watt AMTEC system is 3--5 times more efficient than existing systems for the same application.

  16. PSA effect analysis of a design modification of the auxiliary feedwater system for a Westinghouse type plant

    International Nuclear Information System (INIS)

    The auxiliary feedwater system is an important system used to mitigate most accidents considered in probabilistic safety assessment (PSA). The reference plant has produced electric power for about thirty years. Due to age related deterioration and lack of parts, a turbine driven auxiliary feedwater pump (TD AFWP), some valves, and piping of the auxiliary feedwater system should be replaced. This change includes relocation of some valves, installation of valves for maintenance of the steam generator, and a new cross tie line. According to the design change, the Final Safety Analysis Report (FSAR) has been revised. Therefore, this design modification affects the PSA. It is thus necessary to assess the improvement of plant safety. In this paper, the impact of the design change of the auxiliary feedwater system on the PSA is assessed. The results demonstrate that this modification considering the plant safety decreased the total CDF

  17. 基于年费用法的电站辅机投资项目经济评价研究%Economic Evaluation of Auxiliary Equipment Project in Power Plants Based on the Annualized Cost Method

    Institute of Scientific and Technical Information of China (English)

    陈晓霞

    2013-01-01

    The economic evaluation is an important part of feasibility study and project proposals. It also can help making decision. The thesis, in accordance with characteristics of the electric power project and the specific property of evaluation, analyzes the component elements, establishes evaluating indicator, and constructs economic assessment method of auxiliary equipment project in power plants. Through empirical analysis, scientific and practiced characters of index system and evaluating method have been validated.%  经济评价是电力项目可行性研究与项目建议书的重要组成部分,是项目决策科学化的据。论文从电站辅机项目的特点和评价独特性入手,分析和甄别构成要素、设置评价指标,构建了基年费用法的电站辅机设备的经济性评价方法,并通过实证分析,验证了指标体系和评价方法的科学性和实践可行性。

  18. Auxiliary quasi-resonant dc tank electrical power converter

    Science.gov (United States)

    Peng, Fang Z.

    2006-10-24

    An auxiliary quasi-resonant dc tank (AQRDCT) power converter with fast current charging, voltage balancing (or charging), and voltage clamping circuits is provided for achieving soft-switched power conversion. The present invention is an improvement of the invention taught in U.S. Pat. No. 6,111,770, herein incorporated by reference. The present invention provides faster current charging to the resonant inductor, thus minimizing delay time of the pulse width modulation (PWM) due to the soft-switching process. The new AQRDCT converter includes three tank capacitors or power supplies to achieve the faster current charging and minimize the soft-switching time delay. The new AQRDCT converter further includes a voltage balancing circuit to charge and discharge the three tank capacitors so that additional isolated power supplies from the utility line are not needed. A voltage clamping circuit is also included for clamping voltage surge due to the reverse recovery of diodes.

  19. Feasibility of AN Ecrh System for Jet:. Plant Layout, Auxiliaries and Services

    Science.gov (United States)

    Lennholm, M.; Bouquey, F.; Braune, H.; Farthing, J.; Garavaglia, S.; Giruzzi, G.; Granucci, G.; Jennison, M.; Parkin, A.

    2011-02-01

    A study conducted over the last year to asses the desirability and feasibility of installing an ECRH system on the JET tokamak has concluded that such a system is indeed both desirable and feasible. Details of physics studies, launcher and transmission line design, and power supplies are presented elsewhere in these proceedings. This paper concentrates on the logistical implications of installing this system at JET. The paper addresses issues such as port allocation and plant location. The study has concluded that a new building will be needed to house the ECRH plant. Building layout proposals are presented together with considerations regarding the required auxiliary equipment.

  20. Seismic qualification of PWR plant auxiliary feedwater systems

    Energy Technology Data Exchange (ETDEWEB)

    Lu, S.C.; Tsai, N.C.

    1983-08-01

    The NRC Standard Review Plan specifies that the auxiliary feedwater (AFW) system of a pressurized water reactor (PWR) is a safeguard system that functions in the event of a Safe Shutdown Earthquake (SSE) to remove the decay heat via the steam generator. Only recently licensed PWR plants have an AFW system designed to the current Standard Review Plan specifications. The NRC devised the Multiplant Action Plan C-14 in order to make a survey of the seismic capability of the AFW systems of operating PWR plants. The purpose of this survey is to enable the NRC to make decisions regarding the need of requiring the licensees to upgrade the AFW systems to an SSE level of seismic capability. To implement the first phase of the C-14 plan, the NRC issued a Generic Letter (GL) 81-14 to all operating PWR licensees requesting information on the seismic capability of their AFW systems. This report summarizes Lawrence Livermore National Laboratory's efforts to assist the NRC in evaluating the status of seismic qualification of the AFW systems in 40 PWR plants, by reviewing the licensees' responses to GL 81-14.

  1. Seismic qualification of PWR plant auxiliary feedwater systems

    International Nuclear Information System (INIS)

    The NRC Standard Review Plan specifies that the auxiliary feedwater (AFW) system of a pressurized water reactor (PWR) is a safeguard system that functions in the event of a Safe Shutdown Earthquake (SSE) to remove the decay heat via the steam generator. Only recently licensed PWR plants have an AFW system designed to the current Standard Review Plan specifications. The NRC devised the Multiplant Action Plan C-14 in order to make a survey of the seismic capability of the AFW systems of operating PWR plants. The purpose of this survey is to enable the NRC to make decisions regarding the need of requiring the licensees to upgrade the AFW systems to an SSE level of seismic capability. To implement the first phase of the C-14 plan, the NRC issued a Generic Letter (GL) 81-14 to all operating PWR licensees requesting information on the seismic capability of their AFW systems. This report summarizes Lawrence Livermore National Laboratory's efforts to assist the NRC in evaluating the status of seismic qualification of the AFW systems in 40 PWR plants, by reviewing the licensees' responses to GL 81-14

  2. Analysis of Heat Removal Capability of PAFS (Passive Auxiliary Feedwater System) in APR (Advanced Power Reactor Plus)

    International Nuclear Information System (INIS)

    As passive safety features for nuclear power plants receive increasing attention, South Korea has designed PAFS (Passive Auxiliary Feedwater System) for APR+ (Advanced Power Reactor Plus). Because the PAFS replaces a conventional active auxiliary feedwater system and plays a role in the ultimate heat sink for decay heat, it is necessary to evaluate the heat removal capability of PAFS under postulated accidents conditions. Therefore, the performance analysis is carried out for two accident cases: Loss of Condenser Vacuum (LOCV) and Feedwater Line Break (FLB) accidents. For the analysis, MARS-KS code is used and MARS-KS model is developed by adding PAFS model to the existing APR1400 model

  3. Analysis of Heat Removal Capability of PAFS (Passive Auxiliary Feedwater System) in APR (Advanced Power Reactor Plus)

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Y. J.; Kang, K. H.; Yun, B. J. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-03-15

    As passive safety features for nuclear power plants receive increasing attention, South Korea has designed PAFS (Passive Auxiliary Feedwater System) for APR+ (Advanced Power Reactor Plus). Because the PAFS replaces a conventional active auxiliary feedwater system and plays a role in the ultimate heat sink for decay heat, it is necessary to evaluate the heat removal capability of PAFS under postulated accidents conditions. Therefore, the performance analysis is carried out for two accident cases: Loss of Condenser Vacuum (LOCV) and Feedwater Line Break (FLB) accidents. For the analysis, MARS-KS code is used and MARS-KS model is developed by adding PAFS model to the existing APR1400 model.

  4. 核电厂辅助给水系统控制方案设计研究%Study on Control System of Auxiliary Feedwater System of Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    鲁超

    2015-01-01

    Auxiliary water supply system is an important system in the design of safety facilities of nuclear power station. The common cause fault of software and the power plant station blackout are two key factors for control system of ASG. So in the design of the control system, in order to deal with the two failure factors, the control strategy of diversity and emergency power supply are respectively adopted. Through analysis diversity control strategy is an effect method to prevent the failure of the safety functions resulting from software common cause failure which meets single failure criterion. In the case of station blackout, it is necessary to provide emergency power supply for control system of the starting ASG, and ensure the system safety functions workable.%辅助给水系统(ASG)是核电厂专设安全设施中重要的系统。对于实现对ASG功能控制的安全级系统,软件共因故障和全厂失电是导致控制失效的两个关键因素。因此,在进行控制系统设计时,为应对这两大失效因素,分别采用了多样性和增加应急电源的控制策略。通过分析,采用多样性控制策略可以有效地防止软件共因故障导致安全功能丧失的风险,保证系统满足单一故障的要求。同时在全厂断电的情况下,增加应急供电电源,对启动ASG功能的控制系统进行紧急供电,保证系统安全功能可执行。

  5. Green Propulsion Auxiliary Power Unit Demonstration at MSFC

    Science.gov (United States)

    Robinson, Joel W.

    2014-01-01

    In 2012, the National Aeronautics & Space Administration (NASA) Space Technology Mission Directorate (STMD) began the process of building an integrated technology roadmap, including both technology pull and technology push strategies. Technology Area 1 (TA-01)1 for Launch Propulsion Systems is one of fourteen TAs that provide recommendations for the overall technology investment strategy and prioritization of NASA's space technology activities. Identified within TA-01 was the need for a green propulsion auxiliary power unit (APU) for hydraulic power by 2015. Engineers led by the author at the Marshall Space Flight Center (MSFC) have been evaluating green propellant alternatives and have begun the development of an APU test bed to demonstrate the feasibility of use. NASA has residual APU assets remaining from the retired Space Shuttle Program. Likewise, the F-16 Falcon fighter jet also uses an Emergency Power Unit (EPU) that has similar characteristics to the NASA hardware. Both EPU and APU components have been acquired for testing at MSFC. This paper will summarize the status of the testing efforts of green propellant from the Air Force Research Laboratory (AFRL) propellant AFM315E based on hydroxyl ammonium nitrate (HAN) with these test assets.

  6. Diesel Fueled SOFC for Class 7/Class 8 On-Highway Truck Auxiliary Power

    Energy Technology Data Exchange (ETDEWEB)

    Vesely, Charles John-Paul [Cummins Power Generation; Fuchs, Benjamin S. [Cummins Power Generation; Booten, Chuck W. [Protonex Technology, LLC

    2010-03-31

    The following report documents the progress of the Cummins Power Generation (CPG) Diesel Fueled SOFC for Class 7/Class 8 On-Highway Truck Auxiliary Power (SOFC APU) development and final testing under the U.S. Department of Energy (DOE) Energy Efficiency and Renewable Energy (EERE) contract DE-FC36-04GO14318. This report overviews and summarizes CPG and partner development leading to successful demonstration of the SOFC APU objectives and significant progress towards SOFC commercialization. Significant SOFC APU Milestones: Demonstrated: Operation meeting SOFC APU requirements on commercial Ultra Low Sulfur Diesel (ULSD) fuel. SOFC systems operating on dry CPOX reformate. Successful start-up and shut-down of SOFC APU system without inert gas purge. Developed: Low cost balance of plant concepts and compatible systems designs. Identified low cost, high volume components for balance of plant systems. Demonstrated efficient SOFC output power conditioning. Demonstrated SOFC control strategies and tuning methods.

  7. Green Propulsion Auxiliary Power Unit Demonstration at MSFC

    Science.gov (United States)

    Robinson, Joel W.; Beckel, Steve

    2014-01-01

    In 2012, the National Aeronautics & Space Administration (NASA) Space Technology Mission Directorate (STMD) began the process of building an integrated technology roadmap, including both technology pull and technology push strategies. Technology Area 1 (TA-01) for Launch Propulsion Systems is one of fourteen TA's that provide recommendations for the overall technology investment strategy and prioritization of NASA's space technology activities. Identified within TA-01 was the need for a green propulsion auxiliary power unit (APU) for hydraulic power by 2015. Engineers led by the author at the Marshall Space Flight Center (MSFC) have been evaluating green propellant alternatives and have begun the development of an APU testbed to demonstrate the feasibility of use. NASA has residual APU assets remaining from the retired Space Shuttle Program. Likewise, the F-16 Falcon fighter jet also uses an Emergency Power Unit (EPU) that has similar characteristics to the NASA hardware. Both EPU's and APU components have been acquired for testing at MSFC. In concert with this effort, ATK has been developing green propellant technology based on the Swedish Space Corp ECAPS LMP-103S propellant. Propellant blending and test facilities have been established at ATK's Elkton MD facility with the intent to provide suitable propellant blends for application to green APU systems as well as thrusters. This paper will summarize the status of the testing efforts with ATK for use of the green propellant LMP-103S based on ammonium dinitramide and use of the Air Force Research Laboratory (AFRL) propellant AF-M315E based on hydroxyl ammonium nitrate with these test assets.

  8. Compact propane fuel processor for auxiliary power unit application

    Science.gov (United States)

    Dokupil, M.; Spitta, C.; Mathiak, J.; Beckhaus, P.; Heinzel, A.

    With focus on mobile applications a fuel cell auxiliary power unit (APU) using liquefied petroleum gas (LPG) is currently being developed at the Centre for Fuel Cell Technology (Zentrum für BrennstoffzellenTechnik, ZBT gGmbH). The system is consisting of an integrated compact and lightweight fuel processor and a low temperature PEM fuel cell for an electric power output of 300 W. This article is presenting the current status of development of the fuel processor which is designed for a nominal hydrogen output of 1 k Wth,H2 within a load range from 50 to 120%. A modular setup was chosen defining a reformer/burner module and a CO-purification module. Based on the performance specifications, thermodynamic simulations, benchmarking and selection of catalysts the modules have been developed and characterised simultaneously and then assembled to the complete fuel processor. Automated operation results in a cold startup time of about 25 min for nominal load and carbon monoxide output concentrations below 50 ppm for steady state and dynamic operation. Also fast transient response of the fuel processor at load changes with low fluctuations of the reformate gas composition have been achieved. Beside the development of the main reactors the transfer of the fuel processor to an autonomous system is of major concern. Hence, concepts for packaging have been developed resulting in a volume of 7 l and a weight of 3 kg. Further a selection of peripheral components has been tested and evaluated regarding to the substitution of the laboratory equipment.

  9. Operation auxiliary system (SAO)

    International Nuclear Information System (INIS)

    This work presents an auxiliary system for nuclear power plants operation (SAO). The development purpose consisted in a computing supervision system to be installed at different sites of a reactor, mainly in the control room. The inclusion of this system to a nuclear power plant minimizes the possibility of human error for the facility operation. (Author)

  10. Mechanical (turbines and auxiliary equipment)

    CERN Document Server

    Sherry, A; Cruddace, AE

    2013-01-01

    Modern Power Station Practice, Volume 3: Mechanical (Turbines and Auxiliary Equipment) focuses on the development of turbines and auxiliary equipment used in power stations in Great Britain. Topics covered include thermodynamics and steam turbine theory; turbine auxiliary systems such as lubrication systems, feed water heating systems, and the condenser and cooling water plants. Miscellaneous station services, and pipework in power plants are also described. This book is comprised of five chapters and begins with an overview of thermodynamics and steam turbine theory, paying particular attenti

  11. Nuclear power plants

    International Nuclear Information System (INIS)

    Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.)

  12. The modeling of a standalone solid-oxide fuel cell auxiliary power unit

    Science.gov (United States)

    Lu, N.; Li, Q.; Sun, X.; Khaleel, M. A.

    In this research, a Simulink model of a standalone vehicular solid-oxide fuel cell (SOFC) auxiliary power unit (APU) is developed. The SOFC APU model consists of three major components: a controller model; a power electronics system model; and an SOFC plant model, including an SOFC stack module, two heat exchanger modules, and a combustor module. This paper discusses the development of the nonlinear dynamic models for the SOFC stacks, the heat exchangers and the combustors. When coupling with a controller model and a power electronic circuit model, the developed SOFC plant model is able to model the thermal dynamics and the electrochemical dynamics inside the SOFC APU components, as well as the transient responses to the electric loading changes. It has been shown that having such a model for the SOFC APU will help design engineers to adjust design parameters to optimize the performance. The modeling results of the SOFC APU heat-up stage and the output voltage response to a sudden load change are presented in this paper. The fuel flow regulation based on fuel utilization is also briefly discussed.

  13. PWR reactors for BBR nuclear power plants

    International Nuclear Information System (INIS)

    Structure and functioning of the nuclear steam generator system developed by BBR and its components are described. Auxiliary systems, control and load following behaviour and fuel management are discussed and the main data of PWR given. The brochure closes with a perspective of the future of the Muelheim-Kaerlich nuclear power plant. (GL)

  14. 福清核电1、2号机组增大应急给水箱容积安全分析%Safety Analysis on the Volume Increase of Auxiliary Water Tank for Number One and Two Units of Fuqing Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    佟立丽; 邵舸; 顾健; 薛峻峰; 彭建平; 王志强

    2013-01-01

    When main feed water system or start-up feed water system is unavailable, auxiliary feed water system, as Engineered Safety Facility (ESF), provides water for Steam Generators (SG) to remove the stored and decay heat from the reactor core. In order to improve the safety of Nuclear Power Plants (NPPs) and increase operational flexibility, the water inventory of the auxiliary feed water tank is increased in the number one and two units of Fuqing NPP. The model of the NPP is built based on mechanical safety analytical code, and conservative assumptions are used in the calculation. Three typical accident sequences, such as loss of main feed water, loss of offsite power in category Ⅱ accident, and main feed water line break in category IV, are selected to analyze whether or not the inventory in auxiliary water tank after improvement satisfies the relevant requirements in RCC-R The results show that auxiliary water inventory of 713m3 is needed for loss of main feed water accident, auxiliary water inventory of 723m3 is needed for loss of offsite power accident, and auxiliary water inventory of 799m3 is needed for main feed water line break accident. The inventory in auxiliary water tank after improvement satisfies the requirements for category Ⅱ and Ⅳ accidents. The safety of NPP is improved due to the inventory redundancy and a time window is also provided for the operators to perform related accident procedures.%辅助给水系统(ASG)作为专设安全设施在主给水或启动给水不可用时向蒸汽发生器供水,以导出堆芯余热.为了提高电厂安全性,增加运行灵活性,福清核电1、2号机组对应急给水箱的有效容积进行了增加.本文采用机理性安全分析程序,建立核电厂分析模型,在计算过程中采用保守假设条件,选取Ⅱ类工况下正常给水丧失事故,厂外电丧失事故,Ⅳ类工况下主给水管道破裂事故3条典型事故序列,分析改进后的应急给水箱容量是否满足压水

  15. Strategic analysis of a manufacturing company and the North American auxiliary power unit market

    OpenAIRE

    Fisher, Craig B.

    2005-01-01

    Power Systems has been the leader in the truck auxiliary power unit business since 2000 and has been making significant advancements in the price of the product as well as its reliability and robustness. Unfortunately the reliability and robustness requirement is increasing further and the profit margin is shrinking to the point that Power Systems needs to undertake a new product development program. The new product offering will result in zero increase in the price to the customer but provid...

  16. Auxiliary building structures

    International Nuclear Information System (INIS)

    Five types of auxiliary structures are described such as were used during the construction of the Dukovany nuclear power plant, namely a portable staircase tower, a stable staircase tower, mobile tower scaffolding, mobile scaffolding on a crane track and a scaffold cradle. Basic technical data for all types of scaffolding are given. (Pu)

  17. Kansas Power Plants

    Data.gov (United States)

    Kansas Data Access and Support Center — The Kansas Power Plants database depicts, as point features, the locations of the various types of power plant locations in Kansas. The locations of the power...

  18. Performance of turbine auxiliaries and service systems at Rajasthan Atomic Power Station

    International Nuclear Information System (INIS)

    Performance of the turbine auxiliaries and service systems at the Rajasthan Atomic Power Station, India are described. Some of the specific problems encountered in connection with the feed water, turbine governing and common services like compressed air, chilled water, water treatment and chlorination systems are outlined. (K.B.)

  19. Wind power plants

    Energy Technology Data Exchange (ETDEWEB)

    Stiller, W.

    1980-01-01

    Wind power plants have practically faded into oblivion in Germany. These wind power plants are systems converting wind power into other usable energy forms, mainly into electric current. The irregularity of wind currents requires storage of the energy produced. The cost situation is calculated for a small wind power plant.

  20. Power Plant Cycling Costs

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, N.; Besuner, P.; Lefton, S.; Agan, D.; Hilleman, D.

    2012-07-01

    This report provides a detailed review of the most up to date data available on power plant cycling costs. The primary objective of this report is to increase awareness of power plant cycling cost, the use of these costs in renewable integration studies and to stimulate debate between policymakers, system dispatchers, plant personnel and power utilities.

  1. Hydroelectric Power Plants Dobsina

    International Nuclear Information System (INIS)

    In this brochure the Hydroelectric Power Plants Dobsina, (VED), subsidiary of the utility Slovenske Elektrarne, a.s. (Slovak Electric, plc. Bratislava) are presented. VED is mainly aimed at generating peak-load electrical energy and maintenance of operational equipment. Reaching its goals, company is first of all focused on reliability of production, economy and effectiveness, keeping principles of work safety and industry safety standards and also ecology. VED operates eight hydroelectric power plants, from which PVE Ruzin I and PVE Dobsina I are pump storage ones and they are controlled directly by the Slovak Energy Dispatch Centre located in Zilina thought the system LS 3200. Those power plants participate in secondary regulation of electrical network of Slovakia. They are used to compensate balance in reference to foreign electrical networks and they are put into operation independently from VED. Activity of the branch is focused mainly on support of fulfilment of such an important aim as electric network regulation. Beginnings of the subsidiary Hydroelectric Power Plants Dobsina are related to the year of 1948. After commissioning of the pump storage Hydroelectric Power Plants Dobsina in 1953, the plant started to carry out its mission. Since that time the subsidiary has been enlarged by other seven power plants, through which it is fulfilling its missions nowadays. The characteristics of these hydroelectric power plants (The pump-storage power plant Dobsina, Small hydroelectric power plant Dobsina II, Small hydroelectric power plant Rakovec, Small hydroelectric power plant Svedlar, Hydroelectric power plant Domasa, The pump-storage power plant Ruzin, and Small hydroelectric power plant Krompachy) are described in detail. Employees welfare and public relations are presented

  2. Comparative LCA of methanol-fuelled SOFCs as auxiliary power systems on-board ships

    International Nuclear Information System (INIS)

    Fuel cells own the potential for significant environmental improvements both in terms of air quality and climate protection. Through the use of renewable primary energies, local pollutant and greenhouse gas emissions can be significantly minimized over the full life cycle of the electricity generation process, so that marine industry accounts renewable energy as its future energy source. The aim of this paper is to evaluate the use of methanol in Solid Oxide Fuel Cells (SOFC), as auxiliary power systems for commercial vessels, through Life Cycle Assessment (LCA). The LCA methodology allows the assessment of the potential environmental impact along the whole life cycle of the process. The unit considered is a 20 kWel fuel cell system. In a first part of the study different fuel options have been compared (methanol, bio-methanol, natural gas, hydrogen from cracking, electrolysis and reforming), then the operation of the cell fed with methanol has been compared with the traditional auxiliary power system, i.e. a diesel engine. The environmental benefits of the use of fuel cells have been assessed considering different impact categories. The results of the analysis show that fuel production phase has a strong influence on the life cycle impacts and highlight that feeding with bio-methanol represents a highly attractive solution from a life cycle point of view. The comparison with the conventional auxiliary power system shows extremely lower impacts for SOFCs.

  3. Resolution of concerns in auxiliary feedwater piping

    International Nuclear Information System (INIS)

    Auxiliary feedwater piping systems at pressurized water reactor (PWR) nuclear power plants have experienced unanticipated operating conditions during plant operation. These unanticipated conditions have included plant events involving backleakage through check valves, temperatures in portions of the auxiliary feedwater piping system that exceed design conditions, and the occurrence of unanticipated severe fluid transients. The impact of these events has had an adverse effect at some nuclear stations on plant operation, installed plant components and hardware, and design basis calculations. Beaver Valley Unit 2, a three loop pressurized water reactor nuclear plant, has observed anomalies with the auxiliary feedwater system since the unit went operational in 1987. The consequences of these anomalies and plant events have been addressed and resolved for Beaver Valley Unit 2 by performing engineering and construction activities. These activities included pipe stress, pipe support and pipe rupture analysis, the monitoring of auxiliary feedwater system temperature and pressure, and the modification to plant piping, supports, valves, structures and operating procedures

  4. Small hydroelectric power plants

    International Nuclear Information System (INIS)

    Small hydroelectric power plants are power plants of 1 - 10 MW. For a supplier, this is an unnatural limit. A more natural limit involves compact engine design and simplified control system. The article discusses most of the engine and electrotechnical aspects in the development, construction and operation of such a plant

  5. Design of condensation heat exchanger for the PAFS (Passive Auxiliary Feedwater System) of APR+ (Advanced Power Reactor Plus)

    International Nuclear Information System (INIS)

    Highlights: ► Condensation heat exchanger for the PAFS (Passive Auxiliary Feedwater System) was designed. ► The requirement of the heat removal rate and the prevention of water hammer phenomena were considered. ► The proposed design of the heat exchanger satisfied the requirement of the passive heat removal system. - Abstract: The APR+ (Advanced Power Reactor Plus), a next generation nuclear power plant in Korea, has adopted the PAFS (Passive Auxiliary Feedwater System) on the secondary system of the steam generator (SG) as an advanced safety feature. It is intended to replace the conventional auxiliary feedwater system, which consists of active components for the SG in a passive way. It removes decay heat from the reactor core by cooling down the secondary system of the SG using a condensation heat exchanger installed in the PCCT (Passive Condensation Cooling Tank). The objective of this study is to design a condensation heat exchanger for the PAFS and to evaluate the cooling performance for the proposed design using the thermal hydraulic system analysis code, MARS (Multi-dimensional Analysis for Reactor Safety). Requirements such as the heat removal capacity and the prevention of water hammer were preferentially considered to determine the design parameters of the heat exchanger tube. The MARS code analysis result showed that the proposed design of the PAFS heat exchanger is able to cool down the required amount of decay heat. The distribution of a liquid volume fraction and flow regime predicted by the MARS code shows that the proposed design of the heat exchanger excludes the water hammer inside the tube. Estimation of a two-phase flow pressure drop indicates that the pressure drop inside the tube is negligible compared to the total pressure drop in the PAFS. From the MARS code analysis, it is concluded that the proposed design of the condensation heat exchanger in the PAFS satisfies the overall criteria for the performance of the passive heat removal

  6. Containment vessel, its auxiliary system and plant air conditioning system of advanced thermal reactor Fugen

    International Nuclear Information System (INIS)

    The functional requirement for, the design and the construction of, and the functional test on the containment vessel, its auxiliary system, the plant air conditioning and ventilation system of the advanced thermal reactor, Fugen, are described in detail. The main specifications of the containment vessel are as follows: The type enclosed cylinder, the maximum operating pressure 1.35 kg/cm2g, the maximum operating temperature 100 deg C, the leak rate 0.4%/day, the inner diameter 36 m. The height 64 m, the volume 40,900 m3, and the material JIS G3118, SGV-49. The containment vessel is provided with an hatch of 5 m diameter for carrying equipments in two air locks, many high and low voltage cable penetrations, pipe penetrations, a transfer shoot and isolation values. The functions and the specifications of the containment vessel and its auxiliary equipments are explained. The relating auxiliary systems are composed of the containment vessel spray system, the pool facility for steam blow-down, the recirculation system for the air in the vessel, the annulus evacuation system and its pressure control devices, the pressure measuring instruments and pressure relief valves and the temperature measuring devices for the containment vessel, and the object, function, layout and installation of these systems are explained. Concerning the air conditioning system, each main building has the special subsystem, and they are introduced. The progress stage of construction works and the procedure and results of the functional test at the site are described. (Nakai, Y.)

  7. Determination of the thermal loadings affecting the auxiliary lines of the reactor coolant system in French PWR plants

    International Nuclear Information System (INIS)

    The various incidents, imputed to thermal fatigue, which occurred throughout the world on the auxiliary lines of Reactor Coolant System (SIS, RHR, CVC), led EDF to urge a research program in order to determine the origins and the consequences of these problems for the French nuclear power plants. In 1992, following the crossing crack discovered at Dampierre 2 on the un-isolable part of a Safety Injection System pipe, a program of instrumentation was defined and is described in this paper. Among the objectives, two of the principal goals were to determine the thermal loadings really supported by the various lines and to highlight the thermal hydraulic phenomena affecting them. Indeed, in order to explain the discovered damages, it was essential to know the real thermal loadings to compare them with those of design and to carry out mechanical calculations of resistance to thermal fatigue. The instrumentations installed on the 900 MW units enabled to check the resistance with the fatigue of all the auxiliary lines in spite of significant differences between the real loadings and those envisaged at the design. They contributed to the knowledge improvement on the local thermal hydraulic phenomena but the incidents at Dampierre 1 showed that this knowledge is still imperfect. The results of these instrumentations are also used for the design of the future units by the use of the feedback of several cycles of acquisition on the 900 MW units, but also 1300 MW and 1450 MW since similar instrumentations were installed on the auxiliary lines in Golfech 2 and Chooz B1

  8. Solar thermal power plants

    International Nuclear Information System (INIS)

    The solar thermal power plant technology, the opportunities it presents and the developments in the market are outlined. The focus is on the technology of parabolic trough power plants, a proven technology for solar power generation on a large scale. In a parabolic trough power plant, trough-shaped mirrors concentrate the solar irradiation onto a pipe in the focal line of the collector. The thermal energy thus generated is used for electricity generation in a steam turbine. Parabolic trough plants can be combined with thermal storage and fossil or biomass fired heat exchangers to generate electricity even when the sun is not shining. Solar Millennium AG in Erlangen has developed the first power plant of this kind in Europe. After two years of construction the plant started operation in Southern Spain in 2008. This one and its sister projects are important steps leading the way for the whole market. The paper also covers the technological challenges, the key components used and the research and development activities concerning this technology. Solar thermal power plants are ideal for covering peak and medium loads in power grids. In hybrid operation they can also cover base-load. The Solar Chimney power plant, another striking technology for the conversion of solar into electric energy, is described briefly. The paper concludes with a look at the future - the import of solar energy from the deserts of North Africa to central Europe. (author)

  9. Power plant chemical technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    17 contributions covering topies of fossil fuel combustion, flue gas cleaning, power plant materials, corrosion, water/steam cycle chemistry, monitoring and control were presented at the annual meeting devoted to Power Plant Chemical Technology 1996 at Kolding (Denmark) 4-6 September 1996. (EG)

  10. Nuclear Power Plants. Revised.

    Science.gov (United States)

    Lyerly, Ray L.; Mitchell, Walter, III

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

  11. The Kuroshio power plant

    CERN Document Server

    Chen, Falin

    2013-01-01

    By outlining a new design or the Kuroshio power plant, new approaches to turbine design, anchorage system planning, deep sea marine engineering and power plant operations and maintenance are explored and suggested. The impact on the local environment, particularly in the face of natural disasters, is also considered to provide a well rounded introduction to plan and build a 30MW pilot power plant. Following a literature review, the six chapters of this book propose a conceptual design by focusing on the plant's core technologies and establish the separate analysis logics for turbine design and

  12. Nuclear power plant simulator

    International Nuclear Information System (INIS)

    In this paper, real time nuclear power plant simulator for student education is described. The simulator is composed of a hybrid computer and an operating console. Simulated power plant is a 36 MWt PWR plant, and the average temperature of the primary coolant within the reactor is controlled to be constant. Reactor Kinetics, fuel temperature, primary coolant temperature, temperature and pressure of steam within the steam generator, steam flow, control rod driving system, and feed water controlling system are simulated. The use of the hybrid computer made it possible to simulate a relatively large scale power plant with a comparatively small size computing system. (auth.)

  13. STS-31 Discovery, OV-103, auxiliary power unit 1 (APU-1) controller

    Science.gov (United States)

    1990-01-01

    The controller for Discovery's, Orbiter Vehicle (OV) 103's, auxiliary power unit 1 (APU-1) is documented before removal following the launch scrub on 04-10-90. The controller weighs about 15 pounds and controls the speed of the APU. It was flown to the vendor, Sundstrand Corp., Rockford, Illinois, for analysis and testing. Launch of OV-103 on mission STS-31 has been rescheduled for 04-24-90 following the successful replacement of the APU-1 and the recharging of the Hubble Space Telescope's (HST's) nickel-hydrogen batteries. View provided by the Kennedy Space Center (KSC) with alternate KSC number KSC-90PC-663.

  14. On the switching of NPP power unit transformers from auxiliary network

    International Nuclear Information System (INIS)

    In order to clarify the parameters of direct transformer connection the oscillography of a number of parameters of Zaporozhe NPP network and generators was performed, when switching the 1000 MW power unit transformer complex with 750 kV buses. The complex of transformers consisted of three single-phase 787/24 kV ORts-417000/750-77 type transformers and two auxiliary 24/6.3/6.3 kV of TRDNS-63000/35-72 type tramsformers connected to their 24 kV windings. It is shown that generator excitation forcing conditions arise for several seconds when applying voltage to a power unit step-up transformer through closure of the switch onto NPP high-voltage buses due to high jumps of magnetizing current. A technique of switching power unit transformer through application of voltage from 6 kV auxiliary section with subsequent connection to NPP high-voltage buses via a short-term mode of parallel operation, is mastered

  15. Optimal control systems in hydro power plants

    International Nuclear Information System (INIS)

    The aim of the research done in this work is focused on obtaining the optimal models of hydro turbine including auxiliary equipment, analysis of governors for hydro power plants and analysis and design of optimal control laws that can be easily applicable in real hydro power plants. The methodology of the research and realization of the set goals consist of the following steps: scope of the models of hydro turbine, and their modification using experimental data; verification of analyzed models and comparison of advantages and disadvantages of analyzed models, with proposal of turbine model for design of control low; analysis of proportional-integral-derivative control with fixed parameters and gain scheduling and nonlinear control; analysis of dynamic characteristics of turbine model including control and comparison of parameters of simulated system with experimental data; design of optimal control of hydro power plant considering proposed cost function and verification of optimal control law with load rejection measured data. The hydro power plant models, including model of power grid are simulated in case of island ing and restoration after breakup and load rejection with consideration of real loading and unloading of hydro power plant. Finally, simulations provide optimal values of control parameters, stability boundaries and results easily applicable to real hydro power plants. (author)

  16. Hydrogen environment embrittlement of turbine disk alloys. [for space shuttle auxiliary power unit

    Science.gov (United States)

    Gray, H. R.; Joyce, J. P.

    1976-01-01

    Astroloy and V-57, two candidate turbine disk alloys for the auxiliary power unit (APU) of the space shuttle propulsion and power system were tested for their resistance to embrittlement in hydrogen environments. Samples of both these nickel-base alloys were subjected to notch and smooth tensile testing and to creep testing in hydrogen. The high resistance exhibited by Astroloy forgings to embrittlement by hydrogen is attributed to the microstructure produced by forging and also to the special heat treatment schedule. V-57 turbine disks successfully completed short-time performance testing in the experimental APU. The use of the Astroloy, however, would permit increasing turbine inlet temperature and the rotational speed beyond those possible with V-57.

  17. Development of a solid oxide fuel cell (SOFC) automotive auxiliary power unit (APU) fueled by gasoline

    International Nuclear Information System (INIS)

    This paper describes the design and the development progress of a 3 to 5 auxiliary power unit (APU) based on a gasoline fueled solid oxide fuel cell (SOFC). This fuel cell was supplied reformate gas (reactant) by a partial oxidation (POx) catalytic reformer utilizing liquid gasoline and designed by Delphi Automotive Systems. This reformate gas consists mainly of hydrogen, carbon monoxide and nitrogen and was fed directly in to the SOFC stack without any additional fuel reformer processing. The SOFC stack was developed by Global Thermoelectric and operates around 700oC. This automotive APU produces power to support future 42 volt vehicle electrical architectures and loads. The balance of the APU, designed by Delphi Automotive Systems, employs a packaging and insulation design to facilitate installation and operation on-board automobiles. (author)

  18. Auxiliary power unit based on a solid oxide fuel cell and fuelled with diesel

    Science.gov (United States)

    Lawrence, Jeremy; Boltze, Matthias

    An auxiliary power unit (APU) is presented that is fuelled with diesel, thermally self-sustaining, and based on a solid oxide fuel cell (SOFC). The APU is rated at 1 kW electrical, and can generate electrical power after a 3 h warm-up phase. System features include a "dry" catalytic partial oxidation (CPOX) diesel reformer, a 30 cell SOFC stack with an open cathode, and a porous-media afterburner. The APU does not require a supply of external water. The SOFC stack is an outcome of a development partnership with H.C. Starck GmbH and Fraunhofer IKTS, and is discussed in detail in an accompanying paper.

  19. Nuclear power plant construction

    International Nuclear Information System (INIS)

    The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.)

  20. Operation of the main feedwater system turbopump following plant trip with total failure of the auxiliary feedwater system

    International Nuclear Information System (INIS)

    The Auxiliary Feedwater System (AF) is a safeguard system which has been designed to supply feedwater to the steam generators, cool the primary system and remove decay heat from the reactor when the main feedwater pumps fail due to loss of power or any other reason. Thus, when plant trip occurs, the AF system pumps start up automatically, allowing removal of decay heat from the reactor. However, even though this system (2 motor-driven pumps and 1 turbopump) is highly reliable, injection of water to the steam generators must be ensured when it fails completely. To do this, if plant trip has not been caused by loss of off site power or failure of the Main Feedwater System (FW) turbopumps, one of these turbopumps can be used to achieve removal of decay heat. Since a large amount of steam is consumed by these turbopumps, an analysis has been performed to determine whether one of these pumps can be used and what actions are necessary to inject water into the steam generators. Results show that, for the case in question, a FW turbopump can be used to remove decay heat from the reactor. (author)

  1. Technology and power plants

    International Nuclear Information System (INIS)

    In this paper the contributions presented at the 18th IAEA Fusion Energy Conference in the field of technology and power plants are summarised with reference to the following distinct issues: ITER EDA Design, ITER Technology R and D, Progress Towards Advanced Performance and Steady State, Compact Cu Burning Plasma Experiments and Neutron Sources, Advanced Materials Research, Power Plant Design and Economic Forecasts, and Conclusions

  2. PEMFC Optimization Strategy with Auxiliary Power Source in Fuel Cell Hybrid Vehicle

    Directory of Open Access Journals (Sweden)

    Tinton Dwi Atmaja

    2012-02-01

    Full Text Available Page HeaderOpen Journal SystemsJournal HelpUser You are logged in as...aulia My Journals My Profile Log Out Log Out as UserNotifications View (27 new ManageJournal Content SearchBrowse By Issue By Author By Title Other JournalsFont SizeMake font size smaller Make font size default Make font size largerInformation For Readers For Authors For LibrariansKeywords CBPNN Displacement FLC LQG/LTR Mixed PMA Ventilation bottom shear stress direct multiple shooting effective fuzzy logic geoelectrical method hourly irregular wave missile trajectory panoramic image predator-prey systems seawater intrusion segmentation structure development pattern terminal bunt manoeuvre Home About User Home Search Current Archives ##Editorial Board##Home > Vol 23, No 1 (2012 > AtmajaPEMFC Optimization Strategy with Auxiliary Power Source in Fuel Cell Hybrid VehicleTinton Dwi Atmaja, Amin AminAbstractone of the present-day implementation of fuel cell is acting as main power source in Fuel Cell Hybrid Vehicle (FCHV. This paper proposes some strategies to optimize the performance of Polymer Electrolyte Membrane Fuel Cell (PEMFC implanted with auxiliary power source to construct a proper FCHV hybridization. The strategies consist of the most updated optimization method determined from three point of view i.e. Energy Storage System (ESS, hybridization topology and control system analysis. The goal of these strategies is to achieve an optimum hybridization with long lifetime, low cost, high efficiency, and hydrogen consumption rate improvement. The energy storage system strategy considers battery, supercapacitor, and high-speed flywheel as the most promising alternative auxiliary power source. The hybridization topology strategy analyzes the using of multiple storage devices injected with electronic components to bear a higher fuel economy and cost saving. The control system strategy employs nonlinear control system to optimize the ripple factor of the voltage and the current

  3. Offshore atomic power plants

    International Nuclear Information System (INIS)

    Various merits of offshore atomic power plants are illustrated, and their systems are assessed. The planning of the offshore atomic power plants in USA is reviewed, and the construction costs of the offshore plant in Japan were estimated. Air pollution problem may be solved by the offshore atomic power plants remarkably. Deep water at low temperature may be advantageously used as cooling water for condensers. Marine resources may be bred by building artificial habitats and by providing spring-up equipments. In the case of floating plants, the plant design can be standardized so that the construction costs may be reduced. The offshore plants can be classified into three systems, namely artificial island system, floating system and sea bottom-based system. The island system may be realized with the present level of civil engineering, but requires the development of technology for the resistance of base against earthquake and its calculation means. The floating system may be constructed with conventional power plant engineering and shipbuilding engineering, but the aseismatic stability of breakwater may be a problem to be solved. Deep water floating system and deep water submerging system are conceivable, but its realization may be difficult. The sea bottom-based system with large caissons can be realized by the present civil engineering, but the construction of the caissons, stability against earthquake and resistance to waves may be problems to be solved. The technical prediction and assessment of new plant sites for nuclear power plants have been reported by Science and Technology Agency in 1974. The construction costs of an offshore plant has been estimated by the Ministry of International Trade and Industry to be yen71,026/kW as of 1985. (Iwakiri, K.)

  4. Power plants 2010. Lectures

    International Nuclear Information System (INIS)

    The proceedings include the following lectures: Facing the challenges - new structures for electricity production. Renewable energies in Europe - chances and challenges. Nuclear outlook in the UK. Sustainable energy for Europe. Requirements of the market and the grid operator at the electricity production companies. Perspectives for the future energy production. Pumped storage plants - status and perspectives. Nuclear power/renewable energies -partners or opponents? New fossil fired power stations in Europe - status and perspectives. Nuclear energy: outlook for new build and lifetime extension in Europe. Biomass in the future European energy market - experiences for dong energy. Meeting the EU 20:20 renewable energy targets: the offshore challenges. DESERTEC: sustainable electricity for Europe, Middle East and North Africa. New power plants in Europe - a challenge for project and quality management. Consideration of safely in new build activities of power plants. Challenges to an integrated development in Maasvlakte, Netherlands. Power enhancement in EnBW power plants. Operational experiences of CCS pilot plants worldwide. Two years of operational experiences with Vattenfall's oxyfuel pilot plant. Pre-conditions for CCS. Storage technologies for a volatile generation. Overview: new generation of gas turbines.

  5. Power plant at sea

    International Nuclear Information System (INIS)

    Drilling platforms are rather inefficient when it comes to their own power supply. In view of ecotax and their environmental image, the offshore industry particularly the Norwegians is highly committed to changing this situation. An efficient power plant, specially designed for the offshore industry, might just prove to be the answer to their prayers

  6. Nuclear power plant outages

    International Nuclear Information System (INIS)

    The Finnish Radiation and Nuclear Safety Authority (STUK) controls nuclear power plant safety in Finland. In addition to controlling the design, construction and operation of nuclear power plants, STUK also controls refuelling and repair outages at the plants. According to section 9 of the Nuclear Energy Act (990/87), it shall be the licence-holder's obligation to ensure the safety of the use of nuclear energy. Requirements applicable to the licence-holder as regards the assurance of outage safety are presented in this guide. STUK's regulatory control activities pertaining to outages are also described

  7. LNG plant combined with power plant

    International Nuclear Information System (INIS)

    The LNG plant consumers a lot of power of natural gas cooling and liquefaction. In some LNG plant location, a rapid growth of electric power demand is expected due to the modernization of area and/or the country. The electric power demand will have a peak in day time and low consumption in night time, while the power demand of the LNG plant is almost constant due to its nature. Combining the LNG plant with power plant will contribute an improvement the thermal efficiency of the power plant by keeping higher average load of the power plant, which will lead to a reduction of electrical power generation cost. The sweet fuel gas to the power plant can be extracted from the LNG plant, which will be favorable from view point of clean air of the area. (Author). 5 figs

  8. Bowmanville central switching plant for the Canadian power network

    International Nuclear Information System (INIS)

    The Darlington nuclear power station is sited about 80 km east of Toronto on the border of Lake Ontario. Commissioning is planned to be completed by 1992, and the plant will then own four units with 935 MW each, for power input to the eastwestern line of the 500 kV network of Ontario Hydro. The unit and plant auxiliary transformers of the power station are connected by 500 kV transmission lines with the Bowmanville central switching plant at a distance of 700 m. The collecting bar for the outgoing 500 kV overhead transmission lines is north of the switching plant. (orig.)

  9. Power plants 2002. Lectures

    International Nuclear Information System (INIS)

    Main topics of the meeting: Power economy for the Eastern European countries and their economical growth during overtaking by utilities; climatic change by fossil-fuel power plants; deregulation and competition challenges; cogeneration from fossil fuels and renewable energy sources; research programs for advanced energy systems and problems of certification and regulations; power trade and influence on the operators; air pollution and kyoto protocol and climatic change between policy and engineering tasks. (GL)

  10. Kruemmel nuclear power plant

    International Nuclear Information System (INIS)

    This short description of the site and the nuclear power plant with information on the presumable effects on the environment and the general public is to provide some data material to the population in a popular form so that the citizens may in form themselves about the plant. In this description which shall be presented to the safety report, the site, the technical design and the operation mode of the nuclear power plant are described. Some problems of the emission and the effects of radioactive materials as well as other issues related to the plant which are of interest to the public are dealt with. The supposed accidents and their handling are discussed. The description shows that the selected site is suitable for both setting-up and operation of the plant without affecting the safety of the people living there and that in admissible burdens of the environment shall not have to be expected. (orig./HP)

  11. Construction and operation of nuclear power plants

    International Nuclear Information System (INIS)

    How does a nuclear power plant work. Which reactor types are in use. What safety measures are being taken. These questions and the like are frequently asked by those interested in nuclear power generation. The respective answers are to be found in the report ''Construction and Operation of Nuclear Power Plants''. Nuclear-physical fundamentals and the basic safety measures are explained, and four reactor types that are most common in the Federal Republic of Germany are described: PWR-, BWR-, HTR-type and faster breeder reactors. For each reactor type, the principle of operation, steam generator system, auxiliary and service buildings as well as the respective safety devices are indicated, and visualized by means of numerous illustrations. The report is meant to be instrumental to the purpose of getting objectiveness into the public discussion on the peaceful use of nuclear energy. (orig.)

  12. DESIGN AND ANALYSIS OF TURBINE BLADES IN STEAM POWER PLANT SYED

    Directory of Open Access Journals (Sweden)

    ATAUL REHAMAN BASHA

    2014-11-01

    Full Text Available The development of any country directly relates on capital energy consumption. The demand for power generation on the large scale is increasing day by day. Owing to their major contribution towards power production, thermal power plants have a vital role to play in the development of nation. Due to the scarcity of power every power plant needs to be operated at maximum level of efficiency. In case of thermal power plants this applies equally to all its auxiliaries.

  13. Fuel Cell Auxiliary Power Study Volume 1: RASER Task Order 5

    Science.gov (United States)

    Mak, Audie; Meier, John

    2007-01-01

    This study evaluated the feasibility of a hybrid solid oxide fuel cell (SOFC) auxiliary power unit (APU) and the impact in a 90-passenger More-Electric Regional Jet application. The study established realistic hybrid SOFC APU system weight and system efficiencies, and evaluated the impact on the aircraft total weight, fuel burn, and emissions from the main engine and the APU during cruise, landing and take-off (LTO) cycle, and at the gate. Although the SOFC APU may be heavier than the current conventional APU, its weight disadvantage can be offset by fuel savings in the higher SOFC APU system efficiencies against the main engine bleed and extraction during cruise. The higher SOFC APU system efficiency compared to the conventional APU on the ground can also provide considerable fuel saving and emissions reduction, particularly at the gate, but is limited by the fuel cell stack thermal fatigue characteristic.

  14. Model-based prediction of suitable operating range of a SOFC for an Auxiliary Power Unit

    Science.gov (United States)

    Pfafferodt, Matthias; Heidebrecht, Peter; Stelter, Michael; Sundmacher, Kai

    This paper presents a one-dimensional steady state model of a solid oxide fuel cell (SOFC) to be used in an Auxiliary Power Unit (APU). The fuel cell is fed a prereformed gas from an external autothermic reformer. In addition to the three electrochemical reactions (reduction of oxygen at the cathode, oxidation of hydrogen and carbon monoxide at the anode) the water-gas shift reaction and the methane steam reforming reaction are taken into account in the anode channel. The model predicts concentrations and temperatures and uses an equivalent circuit approach to describe the current-voltage characteristics of the cell. The model equations are presented and their implementation into the commercial mathematical software FEMLAB is discussed. An application of this model is used to determine suitable operating parameters with respect to optimum performance and allowable temperature.

  15. Multiplex Tokamak power plant

    International Nuclear Information System (INIS)

    The concept of multiplexing for a fusion power core as an option for producing power is explored. Superconducting, as well as normal magnet, coils in either first or second stability regimes are considered. The results show that multiplex plants with superconducting magnets operating in the second stability regime could be competitive with the single-unit plants in some unit sizes. The key issues that impact the expected benefits of multiplexing must be investigated further. These are factory fabrication, economy of scale, the extent of equipment sharing, inherent safety, maintainability, and utility load management

  16. 75 FR 3622 - Revisions to Rules Authorizing the Operation of Low Power Auxiliary Stations in the 698-806 MHz...

    Science.gov (United States)

    2010-01-22

    .... The Commission will assist consumers, including those who have previously purchased wireless... Street, SW., Room CY-A257, Washington, DC 20554. It also may be purchased from the Commission's... option, notify any entity operating low power auxiliary stations of its intention to initiate...

  17. 75 FR 34347 - Airworthiness Directives; Honeywell International Inc. Auxiliary Power Unit Models GTCP36-150(R...

    Science.gov (United States)

    2010-06-17

    ... published the proposed AD in the Federal Register on December 23, 2009 (74 FR 68196). That action proposed... Policies and Procedures (44 FR 11034, February 26, 1979); and (3) Will not have a significant economic...) for Honeywell International Inc. auxiliary power unit (APU) models GTCP36- 150(R) and...

  18. Advances in materials for fossil power plants

    International Nuclear Information System (INIS)

    The external constraints on the electric power industry over the past 10-15 years have resulted in increased demands on the performance and reliability of materials used in fossil power plants. At the same time, the construction of new plants has been at a low ebb, because of reduced capacity growth and surplus capacity. This led to creation of new institutions to support materials research and development during a period of malaise in industrial support. A remarkable surge of new materials and components for turbines, boilers, and auxiliaries have emerged. Some of the materials advances developed during this period are described. These include improved 1 CrMoV and 12 Cr rotors, temper resistant low Mn 3.5 NiCrMoV, super 9 Cr for heavy section piping and castings, super 12 Cr tubing for superheaters, Nimonic 80A high temperature bolting, titanium alloy blading for L.P. turbines, and many others covered by the present conference

  19. GEOTHERMAL POWER GENERATION PLANT

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, Tonya

    2013-12-01

    Oregon Institute of Technology (OIT) drilled a deep geothermal well on campus (to 5,300 feet deep) which produced 196oF resource as part of the 2008 OIT Congressionally Directed Project. OIT will construct a geothermal power plant (estimated at 1.75 MWe gross output). The plant would provide 50 to 75 percent of the electricity demand on campus. Technical support for construction and operations will be provided by OIT’s Geo-Heat Center. The power plant will be housed adjacent to the existing heat exchange building on the south east corner of campus near the existing geothermal production wells used for heating campus. Cooling water will be supplied from the nearby cold water wells to a cooling tower or air cooling may be used, depending upon the type of plant selected. Using the flow obtained from the deep well, not only can energy be generated from the power plant, but the “waste” water will also be used to supplement space heating on campus. A pipeline will be construction from the well to the heat exchanger building, and then a discharge line will be construction around the east and north side of campus for anticipated use of the “waste” water by facilities in an adjacent sustainable energy park. An injection well will need to be drilled to handle the flow, as the campus existing injection wells are limited in capacity.

  20. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

    The author recognizes a body of basic knowledge in nuclear power plant technoogy that can be taught in school programs, and lists the various courses, aiming to fill the anticipated need for nuclear-trained manpower--persons holding an associate degree in engineering technology. (Author/BP)

  1. VISIT - Virtual visits to nuclear power plants

    International Nuclear Information System (INIS)

    For more than twenty years, EDFs Communication Division has conducted a policy of opening its generation sites to the general public. Around 300,000 people visit a nuclear power plant every year. However, for the security of persons and the safety of facilities, those parts of the plant situated in controlled areas are not accessible to visitors. For the sake of transparency, EDF has taken an interest in the technologies offered by virtual reality to show the general public what a nuclear power plant is really like, so as to initiate dialogue on nuclear energy, particularly with young people. Visit has been developed with virtual reality technologies. It serves to show the invisible (voyage to the core of fission), the inaccessible and to immerse the visitors in environments which are usually closed to the general public (discovery of the controlled area of a nuclear power plant). Visit is used in Public Information Centres which receive visitors to EDF power plants and during international exhibitions and conferences. Visit allows a virtual tour of the following controlled areas: locker room hot area/cold area, a necessary passage before entering the controlled areas; reactor building; fuel building; waste auxiliary building (liquid, solid and gaseous effluents). It also includes a tour of the rooms or equipment usually accessible to the general public: control room, turbine hall, transformer, air cooling tower

  2. Development and implementation of thermal signature testing protocol of auxiliary power unit (APU) and diesel tractor

    Science.gov (United States)

    Jenkins, Chelsea L.; Bourne, Stefanie M.; Rowley, Matthew J.; Miles, Jonathan J.

    2004-04-01

    Thermal signature may be one of the defining factors in determining the applicability of fuel cell auxiliary power unit (APU) technology in military applications. Thermal characterization is important for military applications given that identification and detection may be accomplished through observation of its thermal signature. The operating modes and power takeoff operations of a vehicle will likely determine the thermal profile. The objective of our study was to develop and implement a protocol for quantifying the thermal characteristics of a methanol fuel cell and an idling tractor engine under representative characteristic operations. APU thermal characteristics are a special case for which standardized testing procedures do not presently exist. A customized testing protocol was developed and applied that is specific to an APU-equipped vehicle. Initial testing was conducted on the methanol APU-equipped Freightliner tractor using a high-performance radiometric infrared system. The APU profile calls for a series of infrared images to be collected at three different viewing angles and two different elevations under various loads. The diesel engine was studied in a similar fashion using seven different viewing angles and two different elevations. Raw data collected according to the newly developed methodology provided the opportunity for computer analysis and thermal profiling of both the fuel cell and the diesel engine.

  3. Auxiliary power unit noise of Boeing B737 and B747 aircraft

    Science.gov (United States)

    Kwan, Jimmy S. W.; Yang, S. J. Eric

    Most modern civil aircraft have an Auxiliary Power Unit (APU) which provides compressed air for engine starting and the air-conditioning system on ground and electrical power for aircraft use both on-ground and in-fligth. It is basically a gas turbine engine and it consists of a compressor section, a turbine section, and an accessory drive section. For Boeing B737 and B747 aircraft, the APU is located inside a compartment in the tail section of the aircraft and is completely enclosed by a sound-reduction fire-proof titanium shroud. APU noise is one of the major noise sources at many airports and is extremely important for a densely populated city such as Hong Kong. The noise from APU can affect many people, including ground crew aircraft maintenance staff, and people living in the vicinity of the airport. However, there is very little information available in the literature about APU noise. This paper describes the noise measurement method and presents the measurement results for APUs of one B747 and two B737 aircraft under both 'loaded' and 'no-load' conditions.

  4. Safe decommissioning of mobile nuclear power plant

    International Nuclear Information System (INIS)

    The paper addresses some issues for ensuring radiation safety during the process of decommissioning the 630 kW 'Pamir-630D' mobile nuclear power plant (MNPP). That nuclear power plant consisted of a gas cooled reactor (weight of 76.5t), gas turbine-driven set (76t), two control units (2'20t), and an auxiliary unit (20t). The reactor and turbine-driven set were supposed to be put on transport platforms and carried by tractors. The control and auxiliary units were set on track beds. The 'Pamir-630D' was constructed and tested in an appropriate building. The set-up time was no greater than six hours after all units of the MNPP had reached the site. The 'Pamir-630D' was ready to be moved to another site in 30 hours after the shut down. Service lifetime of 'Pamir-630D' was 10 years: 7 years of storage and 3 years of operation. Operational lifetime was no less than 10000 hours (non-stop operational period was no longer than 2000 hours). Dose rate at the boundary of the restrictive area was no more than 6.5 mR/h at the time of reactor operation and no greater than 300 mR/h on the side surface and 1000 mR/h on the end surface of the biological shielding of the reactor, 24 hours after shut down. (author)

  5. Optimization of Fuel Consumption and Emissions for Auxiliary Power Unit Based on Multi-Objective Optimization Model

    OpenAIRE

    Yongpeng Shen; Zhendong He; Dongqi Liu; Binjie Xu

    2016-01-01

    Auxiliary power units (APUs) are widely used for electric power generation in various types of electric vehicles, improvements in fuel economy and emissions of these vehicles directly depend on the operating point of the APUs. In order to balance the conflicting goals of fuel consumption and emissions reduction in the process of operating point choice, the APU operating point optimization problem is formulated as a constrained multi-objective optimization problem (CMOP) firstly. The four comp...

  6. Power plant process computer

    International Nuclear Information System (INIS)

    The concept of instrumentation and control in nuclear power plants incorporates the use of process computers for tasks which are on-line in respect to real-time requirements but not closed-loop in respect to closed-loop control. The general scope of tasks is: - alarm annunciation on CRT's - data logging - data recording for post trip reviews and plant behaviour analysis - nuclear data computation - graphic displays. Process computers are used additionally for dedicated tasks such as the aeroball measuring system, the turbine stress evaluator. Further applications are personal dose supervision and access monitoring. (orig.)

  7. Ways to Improve Russian Coal-Fired Power Plants

    International Nuclear Information System (INIS)

    Coal is an important fuel for the electric power industry of Russia, especially in Ural and the eastern part of the country. It is fired in boilers of large (200 – 800 MW) condensing power units and in many cogeneration power plants with units rated at 50 – 180 MW. Many coal-fired power plants have been operated for more than 40 – 50 years. Though serviceable, their equipment is obsolete and does not comply with the current efficiency, environmental, staffing, and availability standards. It is urgent to retrofit and upgrade such power plants using advanced equipment, engineering and business ideas. Russian power-plant engineering companies have designed such advanced power units and their equipment such as boilers, turbines, auxiliaries, process and environmental control systems similar to those produced by the world’s leading manufacturers. Their performance and ways of implementation are discussed

  8. Miniature thermoelectric power plant

    OpenAIRE

    Moreira, António H. J.; Freitas, Ricardo; Esteves, João Sena

    2006-01-01

    This paper describes a miniature thermoelectric power plant made with the boiler and the water pump from an old starch iron. It also uses a computer cooling fan, which serves as electric power generator. The boiler vaporizes the water it receives from the water pump. Then, the steam is injected over the turbine of the fan making it twirl. The voltage generated by the fan is enough to lighten a couple of LEDs. A wooden case with a chimney encloses all the referred devices.

  9. Miniature thermoelectric power plant

    OpenAIRE

    Moreira, António, 1957-; Freitas, Ricardo; Sepúlveda, João; Esteves, João Sena

    2010-01-01

    This paper describes a miniature thermoelectric power plant made with the boiler and the water pump from an old starch iron. It also uses a computer cooling fan, which serves as electric power generator. The boiler vaporizes the water it receives from the water pump. Then, the steam is injected on the turbine of the fan, making it twirl. The voltage generated by the fan is enough to lighten a couple of LEDs. A wooden case with a chimney encloses all the referred devices.

  10. Nuclear turbine power plant

    International Nuclear Information System (INIS)

    Purpose : To improve the heat cycle balance in a nuclear turbine power plant or the like equipped with a moisture separating and reheating device, by eliminating undesired overcooling of the drains in the pipes of a heat transmission pipe bundle. Constitution : A high pressure turbine is driven by main steams from a steam generator. The steams after driving the high pressure turbine are removed with moistures by way of a moisture separator and then re-heated. Extracted steams from the steam generator or the high pressure turbine are used as a heating source for the reheating. In the nuclear turbine power plant having such a constitution, a vessel for separating the drains and the steams resulted from the heat exchange is provided at the outlet of the reheating device and the steams in the vessel are introduced to the inlet of the moisture separator. (Aizawa, K.)

  11. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To suppress corrosion at the inner surfaces of equipments and pipeways in nuclear power plants. Constitution: An injection device comprising a chemical injection tank and a plunger type chemical injection pump for injecting hydrazine as an oxygen remover and ammonia as a pH controller is disposed to the downstream of a condensate desalter column for primary coolant circuits. Since dessolved oxygen in circuit water injected with these chemicals is substantially reduced to zero and pH is adjuted to about 10 - 11, occurrence of stress corrosion cracks in carbon steels and stainless steels as main constituent materials for the nuclear power plant and corrosion products are inhibited in high temperature water, and of corrosion products are inhibited from being introduced as they are through leakage to the reactor core, by which the operators' exposure does can be decreased significantly. (Sekiya, K.)

  12. Nuclear power plants

    International Nuclear Information System (INIS)

    Before the economical adaptability of nuclear power plants was achieved, many ways were tried to technically use nuclear fission. In the course of a selection process, of numerous types of reactors, only a few have remained which are now taking part in the competition. The most important physical fundamentals, the occurence of various reactor concepts and the most important reactor types are the explained. (orig./TK)

  13. Power plant emissions reduction

    Science.gov (United States)

    Anand, Ashok Kumar; Nagarjuna Reddy, Thirumala Reddy

    2015-10-20

    A system for improved emissions performance of a power plant generally includes an exhaust gas recirculation system having an exhaust gas compressor disposed downstream from the combustor, a condensation collection system at least partially disposed upstream from the exhaust gas compressor, and a mixing chamber in fluid communication with the exhaust gas compressor and the condensation collection system, where the mixing chamber is in fluid communication with the combustor.

  14. Novel high power impulse magnetron sputtering enhanced by an auxiliary electrical field

    Science.gov (United States)

    Li, Chunwei; Tian, Xiubo

    2016-08-01

    The high power impulse magnetron sputtering (HIPIMS) technique is a novel highly ionized physical vapor deposition method with a high application potential. However, the electron utilization efficiency during sputtering is rather low and the metal particle ionization rate needs to be considerably improved to allow for a large-scale industrial application. Therefore, we enhanced the HIPIMS technique by simultaneously applying an electric field (EF-HIPIMS). The effect of the electric field on the discharge process was studied using a current sensor and an optical emission spectrometer. Furthermore, the spatial distribution of the electric potential and electric field during the EF-HIPIMS process was simulated using the ANSYS software. The results indicate that a higher electron utilization efficiency and a higher particle ionization rate could be achieved. The auxiliary anode obviously changed the distribution of the electric potential and the electric field in the discharge region, which increased the plasma density and enhanced the degree of ionization of the vanadium and argon gas. Vanadium films were deposited to further compare both techniques, and the morphology of the prepared films was investigated by scanning electron microscopy. The films showed a smaller crystal grain size and a denser growth structure when the electric field was applied during the discharge process.

  15. Novel high power impulse magnetron sputtering enhanced by an auxiliary electrical field.

    Science.gov (United States)

    Li, Chunwei; Tian, Xiubo

    2016-08-01

    The high power impulse magnetron sputtering (HIPIMS) technique is a novel highly ionized physical vapor deposition method with a high application potential. However, the electron utilization efficiency during sputtering is rather low and the metal particle ionization rate needs to be considerably improved to allow for a large-scale industrial application. Therefore, we enhanced the HIPIMS technique by simultaneously applying an electric field (EF-HIPIMS). The effect of the electric field on the discharge process was studied using a current sensor and an optical emission spectrometer. Furthermore, the spatial distribution of the electric potential and electric field during the EF-HIPIMS process was simulated using the ANSYS software. The results indicate that a higher electron utilization efficiency and a higher particle ionization rate could be achieved. The auxiliary anode obviously changed the distribution of the electric potential and the electric field in the discharge region, which increased the plasma density and enhanced the degree of ionization of the vanadium and argon gas. Vanadium films were deposited to further compare both techniques, and the morphology of the prepared films was investigated by scanning electron microscopy. The films showed a smaller crystal grain size and a denser growth structure when the electric field was applied during the discharge process. PMID:27587123

  16. Power plant design model

    International Nuclear Information System (INIS)

    This paper reports on the Power Plant Design Model (PPDM) which is an interactive FORTRAN/2020 program with over 15,000 lines of code that allows a user to create an engineering model of a grass roots solid fuel-fired facility capable of generating steam for electrical power generation and/or sale. Capital, operating, and maintenance cost estimates of the modeled plant are also generated. The model's technical output contains complete material and energy balances of all major streams, parasitic power calculations, boiler operating data and a major equipment list. The economic output consists of a capital cost estimate for the plant in a spreadsheet format detailing the material, labor and indirect costs associated with each piece of equipment. The model was intended for use as a marketing tool to replace engineering feasibility studies which are needed to determine the viability of a project. The model provides preliminary economics at a fraction of time and manpower effort normally associated with this task

  17. Development of 8 MW Power Supply Based on Pulse Step Modulation Technique for Auxiliary Heating System on HL-2A

    Science.gov (United States)

    Xu, Weidong; Xuan, Weimin; Yao, Lieying; Wang, Yingqiao

    2012-03-01

    The high voltage power supply (HVPS) based on pulse step modulation (PSM) has already been developed for the auxiliary heating system on HL-2A. This power supply consists of many switch power supplies, and its output voltage can be obtained by modulating their delay time and pulse widths. The PSM topology and control principle are presented in this paper. The simple algorithms for the control system are explained clearly. The switch power supply (SPS) module has been built and the test results show it can meet the requirements of the auxiliary heating system. Now, 112 SPS modules and the whole system have already been developed. Its maximum output is about 72 kV/93 A. The protection time is less than 5 μs. The different outputs of this power supply are used for the electron cyclotron resonant heating (ECRH) system with different duty ratios. The experimental results of the entire system are presented. The results indicate that the whole system can meet the requirements of the auxiliary heating system on HL-2A.

  18. Study of nuclear power plant stability. Trip criteria

    International Nuclear Information System (INIS)

    The influence that nuclear power plants and high voltage power systems have on each other when confronted by disturbances in the offsite network may lead, due to dynamic effects, to plant trip. It is therefore necessary to study the disturbances in the network and the effects on plant equipment by means of dynamic simulations which evaluate the unit protection system and the auxiliary services so as to obtain maximum unit availability without jeopardizing its safety. These studies can be conducted since there are models and software tools capable of simulating dynamic behaviour of the electric system, including the excitation systems and specific speed governors obtainment of valid. (author)

  19. Evolution of Onsite and Offsite Power Systems in US Nuclear Power Plants

    International Nuclear Information System (INIS)

    The AC electric power system is the source of power for station auxiliaries during normal operation and for the reactor protection system and emergency safety features during abnormal and accident conditions. Since the construction of early plants in US, the functional adequacy and requirements of the offsite power systems, safety and non safety related onsite electric power systems have changed considerably to ensure that these systems have adequate redundancy, independence, quality, maintenance and testability to support safe shutdown of the nuclear plant. The design of AC systems has evolved from a single train to multiple (up to four) redundant trains in the current evolutionary designs coupled with other auxiliary AC systems. The early plants were designed to cope with a Loss of Offsite Power (LOOP) event through the use of onsite power supplies only. However operating experience has indicated that onsite and offsite power AC power systems can fail due to natural phenomena (earthquakes, lightning strikes, fires, geomagnetic storms, tsunamis, etc.) or operational abnormalities such as loss of a single phase, switching surges or human error. The onsite DC systems may not be adequately sized to support plant safe shutdown over an extended period if AC power cannot be restored within a reasonable time. This paper will discuss the requirements to improve availability and reliability of offsite and onsite alternating current (AC) power sources to U.S. Nuclear Power Plants. In addition, the paper will discuss the requirements and guidance beyond design basis events. (author)

  20. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    In 1973 the 345 MW pressurized water nuclear power plant at Obrigheim operated on base load, generating approximately 2.63 TWh, approximately 2.5 TWh of which was supplied to the KWO members. The plant availability for the year was 89.9%. Of the 10.1% non-availability, 6.4% (23 d) was caused by refuelling, including inspection, overhaul and repair operations and routine tests carried out in September 1973. 3.3% was due to stoppages for repairs to a steam generator and the two main cooling pumps, while 0.4% resulted from failures in the electrical section of the plant. The plant was shut down seven times in all, including three scrams. The average core burnup at the end of the fourth cycle (1 September 1973) was 18900 MWd/tU, representing an average burnup of approximately 37500 MWd/tU for a fuel element used in all four cycles. The operating performance of the steam generators and the result of the steam generator inspection carried out during refuelling in 1973 suggest no progressive damage. The quantities of radioactive materials released to the environment in 1973 were well below the officially permitted levels. The availability of the plant from the beginning of pilot operation in 1969 to the end of 1973 was 83.7 %

  1. Initiative against nuclear power plants

    International Nuclear Information System (INIS)

    This publication of the Initiative of Austrian Nuclear Power Plant Opponents contains articles on radiactive waste dispoasal in Austria and and discusses safety issues of the nuclear power plant 'Zwentendorf'. (kancsar)

  2. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    The gross output of the 345MWe pressurized water nuclear power station at Obrigheim, operation on base load, amounted to about 2.57TWh in 1974, the net power fed to the grid being about 2.44TWh. The core was used to its full capacity until 10 May 1974. Thereafter, the reactor was on stretch-out operation with steadily decreasing load until refuelled in August 1974. Plant availability in 1974 amounted to 92.1%. Of the 7.9% non-availability, 7.87% was attributable to the refuelling operation carried out from 16 August to 14 September and to the inspection, overhaul and repair work and the routine tests performed during this period. The plant was in good condition. Only two brief shutdowns occurred in 1974, the total outage time being 21/2 hours. From the beginning of trial operation in March 1969 to the end of 1974, the plant achieved an availability factor of 85.2%. The mean core burnup at the end of the fifth cycle was 19600 MWd/tonne U, with one fuel element that had been used for four cycles achieving a mean burnup of 39000 MWd/tonne U. The sipping test on the fuel elements revealed defective fuel-rods in a prototype plutonium fuel element, a high-efficiency uranium fuel element and a uranium fuel element. The quantities of radioactive substances released to the environment in 1974 were far below the officially permitted values. In july 1974, a reference preparation made up in the nuclear power station in October 1973 was discovered by outsiders on the Obrigheim municipality rubbish tip. The investigations revealed that this reference preparation had very probably been abstracted from the plant in October 1973 and arrived at the rubbish tip in a most irregular manner shortly before its discovery

  3. Safety requirements for a nuclear power plant electric power system

    International Nuclear Information System (INIS)

    This work aims at identifying the safety requirements for the electric power system in a typical nuclear power plant, in view of the UNSRC and the IAEA. Description of a typical system is provided, followed by a presentation of the scope of the information required for safety evaluation of the system design and performance. The acceptance and design criteria that must be met as being specified by both regulatory systems, are compared. Means of implementation of such criteria as being described in the USNRC regulatory guides and branch technical positions on one hand and in the IAEA safety guides on the other hand are investigated. It is concluded that the IAEA regulations address the problems that may be faced with in countries having varying grid sizes ranging from large stable to small potentially unstable ones; and that they put emphasis on the onsite standby power supply. Also, in this respect the Americans identify the grid as the preferred power supply to the plant auxiliaries, while the IAEA leaves the possibility that the preferred power supply could be either the grid or the unit main generator depending on the reliability of each. Therefore, it is found that it is particularly necessary in this area of electric power supplies to deal with the IAEA and the American sets of regulations as if each complements and not supplements the other. (author)

  4. Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Analia Bonelli

    2012-01-01

    Full Text Available A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

  5. Assessment of occupational radiation protection conditions during power enhancement of the Angra-2 nuclear power plant

    International Nuclear Information System (INIS)

    This paper intend to analyse the occupational radioprotection conditions of the Angra-2 nuclear power plant, from the startup up to reach 100% of the nominal power. To perform this work a group of dose rates measures was made including beta/gamma and neutron radiation, particulates and iodine monitoring, and surface contamination, during the whole process. These measures were made inside of the three main buildings: the reactor buildings (UJA - reactor core and UJB) and the Reactor Auxiliary Building (UKA). (author)

  6. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

    During the period under review, the Garigliano power station produced 1,028,77 million kWh with a utilization factor of 73,41% and an availability factor of 85,64%. The disparity between the utilization and availability factors was mainly due to a shutdown of about one and half months owing to lack of staff at the plant. The reasons for nonavailability (14.36%) break down as follows: nuclear reasons 11,49%; conventional reasons 2,81%; other reasons 0,06%. During the period under review, no fuel replacements took place. The plant functioned throughout with a single reactor reticulation pump and resulting maximum available capacity of 150 MWe gross. After the month of August, the plant was operated at levels slightly below the maximum available capacity in order to lengthen the fuel cycle. The total number of outages during the period under review was 11. Since the plant was brought into commercial operation, it has produced 9.226 million kWh

  7. Floating nuclear power plants

    International Nuclear Information System (INIS)

    This article examines the legal regime for floating nuclear power plants (FNPs), in view of the absence of specific US legislation and the very limited references to artificial islands in the Law of the Sea Convention. The environmental impacts of FNPs are examined and changes in US regulation following the Three Mile Island accident and recent US court decisions are described. References in the Law of the Sea Convention relevant to FNPs are outlined and the current status of international law on the subject is analysed. (author)

  8. Demonstration tokamak power plant

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.; Baker, C.; Brooks, J.; Ehst, D.; Mattas, R.; Smith, D.L.; DeFreece, D.; Morgan, G.D.; Trachsel, C.

    1983-01-01

    A conceptual design for a tokamak demonstration power plant (DEMO) was developed. A large part of the study focused on examining the key issues and identifying the R and D needs for: (1) current drive for steady-state operation, (2) impurity control and exhaust, (3) tritium breeding blanket, and (4) reactor configuration and maintenance. Impurity control and exhaust will not be covered in this paper but is discussed in another paper in these proceedings, entitled Key Issues of FED/INTOR Impurity Control System.

  9. Solid Oxide Fuel Cell Development for Auxiliary Power in Heavy Duty Vehicle Applications

    Energy Technology Data Exchange (ETDEWEB)

    Daniel T. Hennessy

    2010-06-15

    Changing economic and environmental needs of the trucking industry is driving the use of auxiliary power unit (APU) technology for over the road haul trucks. The trucking industry in the United States remains the key to the economy of the nation and one of the major changes affecting the trucking industry is the reduction of engine idling. Delphi Automotive Systems, LLC (Delphi) teamed with heavy-duty truck Original Equipment Manufacturers (OEMs) PACCAR Incorporated (PACCAR), and Volvo Trucks North America (VTNA) to define system level requirements and develop an SOFC based APU. The project defines system level requirements, and subsequently designs and implements an optimized system architecture using an SOFC APU to demonstrate and validate that the APU will meet system level goals. The primary focus is on APUs in the range of 3-5 kW for truck idling reduction. Fuels utilized were derived from low-sulfur diesel fuel. Key areas of study and development included sulfur remediation with reformer operation; stack sensitivity testing; testing of catalyst carbon plugging and combustion start plugging; system pre-combustion; and overall system and electrical integration. This development, once fully implemented and commercialized, has the potential to significantly reduce the fuel idling Class 7/8 trucks consume. In addition, the significant amounts of NOx, CO2 and PM that are produced under these engine idling conditions will be virtually eliminated, inclusive of the noise pollution. The environmental impact will be significant with the added benefit of fuel savings and payback for the vehicle operators / owners.

  10. Techno-economic analysis of fuel cell auxiliary power units as alternative to idling

    Science.gov (United States)

    Jain, Semant; Chen, Hsieh-Yeh; Schwank, Johannes

    This paper presents a techno-economic analysis of fuel-cell-based auxiliary power units (APUs), with emphasis on applications in the trucking industry and the military. The APU system is intended to reduce the need for discretionary idling of diesel engines or gas turbines. The analysis considers the options for on-board fuel processing of diesel and compares the two leading fuel cell contenders for automotive APU applications: proton exchange membrane fuel cell and solid oxide fuel cell. As options for on-board diesel reforming, partial oxidation and auto-thermal reforming are considered. Finally, using estimated and projected efficiency data, fuel consumption patterns, capital investment, and operating costs of fuel-cell APUs, an economic evaluation of diesel-based APUs is presented, with emphasis on break-even periods as a function of fuel cost, investment cost, idling time, and idling efficiency. The analysis shows that within the range of parameters studied, there are many conditions where deployment of an SOFC-based APU is economically viable. Our analysis indicates that at an APU system cost of 100 kW -1, the economic break-even period is within 1 year for almost the entire range of conditions. At 500 kW -1 investment cost, a 2-year break-even period is possible except for the lowest end of the fuel consumption range considered. However, if the APU investment cost is 3000 kW -1, break-even would only be possible at the highest fuel consumption scenarios. For Abram tanks, even at typical land delivered fuel costs, a 2-year break-even period is possible for APU investment costs as high as 1100 kW -1.

  11. Civil engineering for power plants

    International Nuclear Information System (INIS)

    Power plant structures are conspicuously visible and have an impact on our landscape. In the opinion of a critical public, a successful external design can greatly enhance acceptance of an undertaking and its plants. This paper considers the subjects - utilization of by-products, aggregation of series experience in the construction of nuclear power plants, architecture in power plant construction, water works for adequate cooling water supply and also quality assurance in civil engineering and optimum application of electronic data processing. (orig.)

  12. Energy balances for power plants

    International Nuclear Information System (INIS)

    An important aspect of a power plant is its energy balance, i.e. the electrical energy produced by the plant over its overall operation period, compared to the amount of non-renewable energy used to create and build the plant. Tense discussions took place in the past between criticizers and promotors of a given technology, some technologies even being accused of having a negative energy balance. Mostly based on built examples the present study aims at giving objective data for the represented technologies, as follows: a 64 MW hydro power plant in the Alps, with seasonal water storage in a lake; a 60 MW run-of-river high-head hydro power plant in the Alps; two run-of-river low-head hydro power plants in the Swiss Midlands (14 MW and 25 MW respectively); a small 30 kW wind power generator located near the Simplon Pass at 2000 m over sea level, in the Alps; a 3 kW photovoltaic generator in the roof of a single-family house; a 500 kW photovoltaic power plant in the Jura, at 1000 m over sea level; a 0.9 MWel/8.8 MWtherm fossil-fuel co-generation plant near Zuerich; a 200 MW natural-gas-fired gas/vapour turbine power plant; a 300 MW heavy-fuel-fired power plant; a 500 MW coal-fired power plant; and the Leibstadt 990 MW nuclear power plant. The best energy balances are obtained for the hydro power plants, the worst for the Leibstadt nuclear power plant. In between the photovoltaic plants and the fossil-fuel-fired plants are found. The figures differ by more than two orders of magnitude

  13. Nuclear Power Plant 1996

    International Nuclear Information System (INIS)

    Again this year, our magazine presents the details of the conference on Spanish nuclear power plant operation held in February and that was devoted to 1996 operating results. The Protocol for Establishment of a New Electrical Sector Regulation that was signed last December will undoubtedly represent a new challenge for the nuclear industry. By clearing stating that current standards of quality and safety should be maintained or even increased if possible, the Protocol will force the Sector to improve its productivity, which is already high as demonstrated by the results of the last few years described during this conference and by recent sectorial economic studies. Generation of a nuclear kWh that can compete with other types of power plants is the new challenge for the Sector's professionals, who do not fear the new liberalization policies and approaching competition. Lower inflation and the resulting lower interest rates, apart from being representative indices of our economy's marked improvement, will be very helpful in facing this challenge. (Author)

  14. Health protection and industrial safety. Nuclear power plants

    International Nuclear Information System (INIS)

    The standard applies to components of the primary circuit including its auxiliary facilities, and of the secondary circuit of nuclear power plants with pressurized water reactors; to lifting gear and load take-ups for the transport of nuclear fuel and primary circuit components; to elevators within the containment, electrical installations, and piping and valves of radiation protection monitoring equipment. Part 1 defines the terms and specifies engineered safety requirements

  15. Power Plant- A Scientific Disaster

    Directory of Open Access Journals (Sweden)

    Dharmateja Bandlamudi, Sahithi Avirneni

    2013-05-01

    Full Text Available The present paper emphasisesthe society’s movement towards improvement of power sector as a pavement of luxury and on the benighted dark side of it. This produces the reasons for enchanting power plant as a scientific disaster. This paper gives the detailed list of effects caused by the power plants mainly on coal fired, nuclear and hydroelectric power plants, their adverse effects on environment and in turn human life.

  16. Combined cycle power plant Skopje

    International Nuclear Information System (INIS)

    Regarding the new directions in constructing combined cycle power plants, in this work an idea of such plant in Skopje with power of 190 MW has been elaborated. This plant will be constructed on the site of the existing TPP 'Energetika', AD ESM. The rates of efficiency for different condition of operation has been estimated. (Author)

  17. Hybrid combined cycle power plant

    International Nuclear Information System (INIS)

    In case of re-powering the existing pressurised water nuclear power plants by the proposed HCCPP solution, we can increase the electricity output and efficiency significantly. If we convert a traditional nuclear power plant unit to a HCCPP solution, we can achieve a 3.2-5.5 times increase in electricity output and the achievable gross efficiency falls between 46.8-52% and above, depending on the applied solution. These figures emphasise that we should rethink our power plant technologies and we have to explore a great variety of HCCPP solutions. This may give a new direction in the development of nuclear reactors and power plants as well.(author)

  18. Hydrogen embrittlement in power plant steels

    Indian Academy of Sciences (India)

    R K Dayal; N Parvathavarthini

    2003-06-01

    In power plants, several major components such as steam generator tubes, boilers, steam/water pipe lines, water box of condensers and the other auxiliary components like bolts, nuts, screws fasteners and supporting assemblies are commonly fabricated from plain carbon steels, as well as low and high alloy steels. These components often fail catastrophically due to hydrogen embrittlement. A brief overview of our current understanding of the phenomenon of such hydrogen damage in steels is presented in this paper. Case histories of failures of steel components due to hydrogen embrittlement, which are reported in literature, are briefly discussed. A phenomenological assessment of overall process of hydrogen embrittlement and classification of the various damage modes are summarized. Influence of several physical and metallurgical variables on the susceptibility of steels to hydrogen embrittlement, mechanisms of hydrogen embrittlement and current approaches to combat this problem are also presented.

  19. Power plant removal costs

    International Nuclear Information System (INIS)

    The financial, regulatory and political significance of the estimated high removal costs of nuclear power plants has generated considerable interest in recent years, and the political significance has resulted in the Nuclear Regulatory Commission (NRC) eliminating the use of conventional depreciation accounting for the decontamination portion of the removal (decommissioning). While nuclear plant licensees are not precluded from utilizing conventional depreciation accounting for the demolition of non-radioactive structures and site restoration, state and federal utility regulators have not been favorably inclined to requests for this distinction. The realization that steam-generating units will be more expensive to remove, relative to their original cost, predates the realization that nuclear units will be expensive. However, the nuclear issues have overshadowed this realization, but are unlikely to continue to do so. Numerous utilities have prepared cost estimates for steam generating units, and this presentation discusses the implications of a number of such estimates that are a matter of public record. The estimates cover nearly 400 gas, oil, coal and lignite generating units. The earliest estimate was made in 1978, and for analysis purposes the author has segregated them between gas and oil units, and coal and lignite units

  20. Power Plant Replacement Study

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self-funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois University’s aging and failing circa 1925 central steam production plant. Twenty-three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  1. Power Plant Replacement Study

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self-funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois University's aging and failing circa 1925 central steam production plant. Twenty-three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  2. Nuclear power plant

    International Nuclear Information System (INIS)

    The present invention provides a nuclear power plant which generates thermoelectric power by utilizing heat generated by fission reaction. Namely, a fuel/thermoelectric material is made of a semiconductor material containing fission products or a semimetal material containing fission products. A reactor container contains the fuel/thermoelectric material and a reactor core constituted by the fuel/thermoelectric material. The reactor container comprises coolants for removing heat generated by nuclear reaction of fission products from the reactor core and a high temperature side electrode connected to a central portion of the fuel/thermoelectric material and a low temperature side electrode connected to the outside of the fuel/thermoelectric material. Electromotive force is caused in the fuel/thermoelectric material by temperature difference upon combustion caused at the central portion and the outer surface of the fuel/thermoelectric material. The electromotive force is taken out of the high temperature side electrode and the low temperature side electrode. (I.S.)

  3. Increase of power plant efficiency

    International Nuclear Information System (INIS)

    The increase of power plant efficiency has always been the aim of power plant manufacturers and operators. Today, after the re-orientation of the worldwide market situation, it is necessary to newly assess the power plant efficiency in the field of competition and environment. The average efficiency of power plants presently ranges worldwide at about 30%, yet the status of available technology in the year 2000 permits efficiencies between 45 an 58% depending on the fuels used. VGB PowerTech has been monitoring the technical development of power generation for 80 years up to now. From our point of view, power plant technology still has a great development potential at its disposal. (orig.)

  4. Brighter for small power plants

    International Nuclear Information System (INIS)

    The article presents a small tunnel drilling machine aimed at using for the construction of small hydroelectric power plants and mentions briefly some advantages economically and environmentally of both the machine and the power production solution

  5. Internal active power reserve management in Large scale PV Power Plants

    DEFF Research Database (Denmark)

    Craciun, Bogdan-Ionut; Spataru, Sergiu; Kerekes, Tamas;

    Active Power Reserves (APRs) provided through curtailment (iAPRs) or through auxiliary storage systems (aAPR) with Large scale PV Power Plants (LPVPPs) becomes a reality in the near future with high penetration levels of Photovoltaic (PV) power into the grid. Therefore, this paper analyses the...... solutions for iAPR fulfilment in central inverter based - LPVPPs in terms of their layout, configuration and control architecture. During iAPR supply, the LPVPP has to operate under its Maximum Power Point (MPP), which means that the MPP algorithm has to undergo several changes. For this purpose, the paper...

  6. Are atomic power plants saver than nuclear power plants

    International Nuclear Information System (INIS)

    It is rather impossible to establish nuclear power plants against the resistance of the population. To prevail over this resistance, a clarification of the citizens-initiatives motives which led to it will be necessary. This is to say: It is quite impossible for our population to understand what really heappens in nuclear power plants. They cannot identify themselves with nuclear power plants and thus feel very uncomfortable. As the total population feels the same way it is prepared for solidarity with the citizens-initiatives even if they believe in the necessity of nuclear power plants. Only an information-policy making transparent the social-psychological reasons of the population for being against nuclear power plants could be able to prevail over the resistance. More information about the technical procedures is not sufficient at all. (orig.)

  7. Owners of nuclear power plants

    International Nuclear Information System (INIS)

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

  8. Holistic Modeling, Design & Analysis of Integrated Stirling and Auxiliary Clean Energy Systems for Combined Heat and Power Applications

    Science.gov (United States)

    Nayak, Amrit Om

    The research revolves around the development of a model to design and analyze Stirling systems. Lack of a standard approach to study Stirling systems and difficulty in generalizing existing approaches pose stiff challenges. A stable mathematical model (integrated second order adiabatic and dynamic model) is devised and validated for general use. The research attempts to design compact combined heat and power (CHP) system to run on multiple biomass fuels and solar energy. Analysis is also carried out regarding the design of suitable auxiliary systems like thermal energy storage system, biomass moisture removal system and Fresnel solar collector for the CHP Stirling system.

  9. Producing Electricity in Power Plant

    OpenAIRE

    Khabrana, Ahmed; Ageeli, Jaber

    2015-01-01

    Abstract This Bachelor thesis has been written at the Blekinge Institute of Technology. The thesis describes electricity production in Shoaiba Steam Power plant in Saudi Arabia. Shoaiba Power Plant is located 100 km South of Jeddah city in Saudi Arabia. Total power production ability reaches 4400 MW. Shoaiba Power Plant has two stages and is constructed with 11 units, each unit produces 400 MW at line voltage 24 kV and line current 16 kA. Main pieces of equipment and their function in the sta...

  10. A review of high-temperature polymer electrolyte membrane fuel-cell (HT-PEMFC)-based auxiliary power units for diesel-powered road vehicles

    Science.gov (United States)

    Liu, Yongfeng; Lehnert, Werner; Janßen, Holger; Samsun, Remzi Can; Stolten, Detlef

    2016-04-01

    This paper presents an extensive review of research on the development of auxiliary power units with enhanced reformate tolerance for high temperature polymer electrolyte membrane fuel cells (HT-PEMFCs). Developments in diesel reforming for fuel cells as auxiliary power units (APUs), single fuel cells and stacks and systems are outlined in detail and key findings are presented. Summaries of HT-PEMFC APU applications and start-up times for HT-PEMFC systems are then given. A summary of cooling HT-PEMFC stacks using a classic schematic diagram of a 24-cell HT-PEMFC stack, with a cooling plate for every third cell, is also presented as part of a stack analysis. Finally, a summary of CO tolerances for fuel cells is given, along with the effects of different CO volume fractions on polarization curves, the fraction of CO coverage, hydrogen coverage, anode overpotential and cell potential.

  11. AND THERMAL POWER PLANTS

    Directory of Open Access Journals (Sweden)

    Alduhov Oleg Aleksandrovich

    2012-10-01

    Full Text Available Investigation of the atmospheric dispersion as part of the process of selection of sites to accommodate nuclear and thermal power plants is performed to identify concentration fields of emissions and to assess the anthropogenic impact produced on the landscape components and human beings. Scattering properties of the atmospheric boundary layer are mainly determined by the turbulence intensity and the wind field. In its turn, the turbulence intensity is associated with the thermal stratification of the boundary layer. Therefore, research of the atmospheric dispersion is reduced to the study of temperature and wind patterns of the boundary layer. Statistical processing and analysis of the upper-air data involves the input of the data collected by upper-air stations. Until recently, the upper-air data covering the standard period between 1961 and 1970 were applied for these purposes, although these data cannot assure sufficient reliability of assessments in terms of the properties of the atmospheric dispersion. However, recent scientific and technological developments make it possible to substantially increase the data coverage by adding the upper-air data collected within the period between 1964 and 2010. The article has a brief overview of BL_PROGS, a specialized software package designated for the processing of the above data. The software package analyzes the principal properties of the atmospheric dispersion. The use of the proposed software package requires preliminary development of a database that has the information collected by an upper-air station. The software package is noteworthy for the absence of any substantial limitations imposed onto the amount of the input data that may go up in proportion to the amount of the upper-air data collected by upper-air stations.

  12. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    This Guide applies to nuclear power plants for which the total power supply comprises normal power supply (which is electric) and emergency power supply (which may be electric or a combination of electric and non-electric). In its present form the Guide provides general guidance for all types of emergency power systems (EPS) - electric and non-electric, and specific guidance (see Appendix A) on the design principles and the features of the emergency electric power system (EEPS). Future editions will include a second appendix giving specific guidance on non-electric power systems. Section 3 of this Safety Guide covers information on considerations that should be taken into account relative to the electric grid, the transmission lines, the on-site electrical supply system, and other alternative power sources, in order to provide high overall reliability of the power supply to the EPS. Since the nuclear power plant operator does not usually control off-site facilities, the discussion of methods of improving off-site reliability does not include requirements for facilities not under the operator's control. Sections 4 to 11 of this Guide provide information, recommendations and requirements that would apply to any emergency power system, be it electric or non-electric

  13. Gas turbine installations in nuclear power plants in Sweden

    International Nuclear Information System (INIS)

    At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

  14. Conceptual design and selection of a biodiesel fuel processor for a vehicle fuel cell auxiliary power unit

    Science.gov (United States)

    Specchia, S.; Tillemans, F. W. A.; van den Oosterkamp, P. F.; Saracco, G.

    Within the European project BIOFEAT (biodiesel fuel processor for a fuel cell auxiliary power unit for a vehicle), a complete modular 10 kW e biodiesel fuel processor capable of feeding a PEMFC will be developed, built and tested to generate electricity for a vehicle auxiliary power unit (APU). Tail pipe emissions reduction, increased use of renewable fuels, increase of hydrogen-fuel economy and efficient supply of present and future APU for road vehicles are the main project goals. Biodiesel is the chosen feedstock because it is a completely natural and thus renewable fuel. Three fuel processing options were taken into account at a conceptual design level and compared for hydrogen production: (i) autothermal reformer (ATR) with high and low temperature shift (HTS/LTS) reactors; (ii) autothermal reformer (ATR) with a single medium temperature shift (MTS) reactor; (iii) thermal cracker (TC) with high and low temperature shift (HTS/LTS) reactors. Based on a number of simulations (with the AspenPlus® software), the best operating conditions were determined (steam-to-carbon and O 2/C ratios, operating temperatures and pressures) for each process alternative. The selection of the preferential fuel processing option was consequently carried out, based on a number of criteria (efficiency, complexity, compactness, safety, controllability, emissions, etc.); the ATR with both HTS and LTS reactors shows the most promising results, with a net electrical efficiency of 29% (LHV).

  15. Next Generation Geothermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Brugman, John; Hattar, Mai; Nichols, Kenneth; Esaki, Yuri

    1995-09-01

    A number of current and prospective power plant concepts were investigated to evaluate their potential to serve as the basis of the next generation geothermal power plant (NGGPP). The NGGPP has been envisaged as a power plant that would be more cost competitive (than current geothermal power plants) with fossil fuel power plants, would efficiently use resources and mitigate the risk of reservoir under-performance, and minimize or eliminate emission of pollutants and consumption of surface and ground water. Power plant concepts were analyzed using resource characteristics at ten different geothermal sites located in the western United States. Concepts were developed into viable power plant processes, capital costs were estimated and levelized busbar costs determined. Thus, the study results should be considered as useful indicators of the commercial viability of the various power plants concepts that were investigated. Broadly, the different power plant concepts that were analyzed in this study fall into the following categories: commercial binary and flash plants, advanced binary plants, advanced flash plants, flash/binary hybrid plants, and fossil/geothed hybrid plants. Commercial binary plants were evaluated using commercial isobutane as a working fluid; both air-cooling and water-cooling were considered. Advanced binary concepts included cycles using synchronous turbine-generators, cycles with metastable expansion, and cycles utilizing mixtures as working fluids. Dual flash steam plants were used as the model for the commercial flash cycle. The following advanced flash concepts were examined: dual flash with rotary separator turbine, dual flash with steam reheater, dual flash with hot water turbine, and subatmospheric flash. Both dual flash and binary cycles were combined with other cycles to develop a number of hybrid cycles: dual flash binary bottoming cycle, dual flash backpressure turbine binary cycle, dual flash gas turbine cycle, and binary gas turbine

  16. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    The listing indicates percentage ownership of commercial nuclear power plants by utility companies as of August 15, 1977. The list includes all plants operating, under construction, docketed for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally cancelled. In many cases, ownership may be in the process of changing as a result of antitrust license conditions and hearings, altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants and percentage ownership. Part II lists applicants alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses

  17. The Mecca Biomass Power Plant

    International Nuclear Information System (INIS)

    Colmac Energy, Inc. is constructing a 47 MW biomass-fired, electrical power generating plant in Mecca, California. Commercial operation is scheduled for April, 1992. Electrical power will be sold to Southern California Edison Company. The plant is unusual in its fuel choice and utilization. The fuel includes both wood chips and a variety of waste agricultural materials. These are processed and blended to provide a stable fuel product for the boiler. a recirculating fluidized bed boiler is used. The use of agricultural waste for fuel provides several benefits. Local truckers benefit by an added need for services. The plant itself, of course, provides employment opportunities and locally-generated electrical power

  18. Marine nuclear power plant simulator

    International Nuclear Information System (INIS)

    In this paper, a real time simulator of nuclear power plant for ship propulsion is described. The simulator is composed of a hybrid computer and an operating console. Simulated power plant is a 36 MWt PWR plant. Reactor kinetics, fuel temperature, primary coolant temperature, primary pressure, temperature and pressure of steam in the steam generator, steam flow, rotating speed of the propeller shaft, and various controlling system are simulated. Using this simulator, frequency response functions of the reactor power to the variation of reactivity and load were measured. (author)

  19. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of December 1, 1979. The list includes all plants licensed to operate, under construction, docketed for NRC safety and envionmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally cancelled. In many cases, ownership may be in the process of changing as a result of antitrust license conditions and hearings, altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified

  20. Owners of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-11-01

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

  1. Owners of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Reid, R.L.

    2000-01-12

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

  2. Site-specific analysis of hybrid geothermal/fossil power plants

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

    A preliminary economic analysis of a hybrid geothermal/coal power plant has been completed for four geothermal Resource areas: Roosevelt Hot Springs, Coso Hot Springs, East Mesa and Long Valley. A hybrid plant would be economically viable at Roosevelt Hot Springs and somewhat less so at Coso Hot Springs. East Mesa and Long Valley show no economic promise. A well-designed hybrid plant could use geothermal energy for boiler feedwater heating, auxiliary power, auxiliary heating, and cooling water. Construction and operation of a hybrid plant at either Roosevelt Hot Springs or Coso Hot Springs is recommended. Brown University provided the theoretical basis for the hybrid study. A modified version of the Lawrence Berkeley Livermore GEOTHM Program is the major analytical tool used in the analysis. The Intermountain Power Project is the reference all coal-fired plant. Costing methods followed recommendations issued by the Energy research and Development Administration.

  3. Engineering aspects and hardware verification of a volume producable solid oxide fuel cell stack design for diesel auxiliary power units

    Science.gov (United States)

    Stelter, Michael; Reinert, Andreas; Mai, Björn Erik; Kuznecov, Mihail

    A solid oxide fuel cell (SOFC) stack module is presented that is designed for operation on diesel reformate in an auxiliary power unit (APU). The stack was designed using a top-down approach, based on a specification of an APU system that is installed on board of vehicles. The stack design is planar, modular and scalable with stamped sheet metal interconnectors. It features thin membrane electrode assemblies (MEAs), such as electrolyte supported cells (ESC) and operates at elevated temperatures around 800 °C. The stack has a low pressure drop in both the anode and the cathode to facilitate a simple system layout. An overview of the technical targets met so far is given. A stack power density of 0.2 kW l -1 has been demonstrated in a fully integrated, thermally self-sustaining APU prototype running with diesel and without an external water supply.

  4. Space nuclear reactor power plants

    International Nuclear Information System (INIS)

    Requirements for electrical and propulsion power for space are expected to increase dramatically in the 1980s. Nuclear power is probably the only source for some deep space missions and a major competitor for many orbital missions, especially those at geosynchronous orbit. Because of the potential requirements, a technology program on space nuclear power plant components has been initiated by the Department of Energy. The missions that are foreseen, the current power plant concept, the technology program plan, and early key results are described

  5. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 refs.)

  6. Nuclear Power Plant Simulation Game.

    Science.gov (United States)

    Weiss, Fran

    1979-01-01

    Presents a nuclear power plant simulation game which is designed to involve a class of 30 junior or senior high school students. Scientific, ecological, and social issues covered in the game are also presented. (HM)

  7. Power Oscillation Damping Controller for Wind Power Plant Utilizing Wind Turbine Inertia as Energy Storage

    DEFF Research Database (Denmark)

    Knüppel, Thyge; Nielsen, Jørgen Nygård; Jensen, Kim Høj;

    2011-01-01

    utilizes the stored kinetic energy in the wind turbine (WT) mechanical system as energy storage from which damping power can be exchanged. This eliminates the need for curtailed active power production. Results are presented using modal analysis and induced torque coefficients (ITC) to depict the torques......For a wind power plant (WPP) the upper limit for active power output is bounded by the instantaneous wind conditions and therefore a WPP must curtail its power output when system services with active power are delivered. Here, a power oscillation damping controller (POD) for WPPs is presented that...... induced on the synchronous generators from the POD. These are supplemented with nonlinear time domain simulations with and without an auxiliary POD for the WPP. The work is based on a nonlinear, dynamic model of the 3.6 MW Siemens Wind Power wind turbine....

  8. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

  9. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics. (author)

  10. Nuclear power plant

    International Nuclear Information System (INIS)

    The present invention provides reduction of volumes of buildings and the area of the buildings having a plurality of plants. Namely, a plurality of reactor building areas corresponding to a plurality of plants are disposed in a reactor building. In each of the reactor building areas, apparatuses including reactors of the plants are disposed. In addition, a plurality of reactor wells, spent fuel pools, pools for temporary storing facilities are arranged on an identical line. With such a constitution, since various kinds of facilities in the reactor buildings can be used in common, the volume of buildings and areas for the buildings in the plants as a whole can be reduced. In addition, turbine buildings can be used in common by the same idea. As a result, the number of buildings, the volume of the buildings and the area of the buildings of the plants can be reduced as a whole thereby enabling to reduce the steps, costs and materials required for building construction. (I.S.)

  11. Operate a Nuclear Power Plant.

    Science.gov (United States)

    Frimpter, Bonnie J.; And Others

    1983-01-01

    Describes classroom use of a computer program originally published in Creative Computing magazine. "The Nuclear Power Plant" (runs on Apple II with 48K memory) simulates the operating of a nuclear generating station, requiring students to make decisions as they assume the task of managing the plant. (JN)

  12. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides detailed guidance on the provisions of the Code on the Safety in Nuclear Power Plants: Operation, IAEA Safety Series No. 50-C-O(Rev.1) on the maintenance of structures, systems and components. Like the Code, the Guide forms part of the IAEA's programme, referred to as the NUSS programme, for establishing Codes and Safety Guides relating to nuclear power plants. Effective maintenance is essential for safe operation of a nuclear power plant. It not only ensures that the level of reliability and effectiveness of all plant structures, systems and components having a bearing on safety remains in accordance with design assumptions and intent, but also that the safety status of the plant is not adversely affected after commencement of operation. Nuclear power plant maintenance requires special attention because of: Limitations set by requirements that a minimum number of components remain operable even when the plant is shut down in order to ensure that all necessary safety functions are guaranteed; Difficulty of access to some plant items even when the plant is shut down, due to radiation protection constraints; Potential radiological hazards to site personnel and the public. This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, selecting and training maintenance personnel, providing maintenance facilities and equipment, procuring stores and spare parts, reviewing, controlling and carrying out plant modifications, and generating, collecting and retaining maintenance records for establishing and

  13. Wind power plant system services

    DEFF Research Database (Denmark)

    Basit, Abdul; Altin, Müfit

    modern power system with large scale integration wind power. This study presents the investigation of the real-time balance control in a modern Danish power system, where WPPs can actively contribute to active power balance control. New solutions for the automatic generation control (AGC) dealing with...... WPPs are developed and analysed. The main results of this research work show that the WPPs can actively contribute to power balance control through primary and secondary response. The integration of WPPs control into the AGC is of high relevance, particularly in situations when wind power is...... beat risk unless the wind power plants (WPPs) are able to support and participate in power balancing services. The objective of this PhD project is to develop and analyse control strategies which can increase the WPPs capability to provide system services, such as active power balancing control, in a...

  14. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide was prepared as part of the Nuclear Safety Standards programme for establishing Codes and Safety Guides relating to nuclear power plants (NPPs). The first edition of the present Safety Guide was developed in the early 1980s. The text has now been brought up-to-date, refined in several details and amended to include non-electrical diverse and independent power sources. This Guide applies to NPP for which the total power supply comprises a normal power supply and an emergency power supply (EPS), which may be electrical or a combination of electrical and non-electrical. The Guide provides general guidance for all types of EPS and specific guidance on the design safety requirements and the features of the electrical and non-electrical portions of the EPS. 9 figs, 2 tabs

  15. Energy sources and power plants

    International Nuclear Information System (INIS)

    Energy is obtained from various energy sources (coal, petroleum, natural gas, nuclear fuels, wind energy, solar energy, hydro power, biomass, geothermal energy). These differ in each case with respect to their availability, methods of their production and the required power plant technologies. As technologies of the future fuel cells and nuclear fusion are traded.

  16. TVA's nuclear power plant experience

    International Nuclear Information System (INIS)

    This paper reviews TVA's nuclear power plant design and construction experience in terms of schedule and capital costs. The completed plant in commercial operation at Browns Ferry and six additional plants currently under construction represent the nation's largest single commitment to nuclear power and an ultimate investment of $12 billion by 1986. The presentation is made in three separate phases. Phase one will recapitulate the status of the nuclear power industry in 1966 and set forth the assumptions used for estimating capital costs and projecting project schedules for the first TVA units. Phase two describes what happened to the program in the hectic early 1979's in terms of expansion of scope (particularly for safety features), the dramatic increase in regulatory requirements, vendor problems, stretchout of project schedules, and unprecedented inflation. Phase three addresses the assumptions used today in estimating schedules and plant costs for the next ten-year period

  17. Nuclear power plant

    International Nuclear Information System (INIS)

    A modular design for an internal heat exchanger for a power reactor with separate primary and secondary cooling circuits, eg. a PWR, is described. The purpose of the design is to reduce the thermal stresses in the feed water system by a special arrangement of this. (JIW)

  18. Baseline for coal powered plants

    International Nuclear Information System (INIS)

    Frequently, the cost performance of a specific power plant is measured by comparing the cost with the statistical average cost of plants through the industry. Unless all of the variables have been considered, this comparison may draw a misleading conclusion. The capital cost of a power plant varies with time (year of commercial operation and construction duration) due to the effect of inflation. Examine these cost data in detail revels that the variation in the cost is very wide. For example, published data shows that the ratio between the highest to the lowest cost per KW is more than 4 to 1 for the plants that commenced operation in 1984. The wide variation of the capital costs is explained below in relation to various influencing factors, differing conditions, and scope of work. This paper provides a defined baseline coal-fired plant, an analysis of its capital costs, and a discussion of the reasons for such wide variation

  19. Providing emergency supply of nuclear power plants

    OpenAIRE

    ROZMILER, Jiří

    2013-01-01

    Work "Providing emergency power nuclear power plant" describes how solving their own consumption nuclear power plant, as emergency power supply is designed and how it should be a solution of known states of emergency, having an immediate impact on the power consumption of their own nuclear power plants. The aim of this thesis is to propose options to strengthen its own emergency power consumption of nuclear power plants, one might say-more resistant to harsh extremes, which could lead to loss...

  20. Calculation of Efficiencies of a Ship Power Plant Operating with Waste Heat Recovery through Combined Heat and Power Production

    OpenAIRE

    Mirko Grljušić; Vladimir Medica; Gojmir Radica

    2015-01-01

    The aim of this research was to investigate the possibility of a combined heat & power (CHP) plant, using the waste heat from a Suezmax-size oil tanker’s main engine, to meet all heating and electricity requirements during navigation. After considering various configurations, a standard propulsion engine operating at maximum efficiency, combined with a supercritical Organic Rankine cycle (ORC) system, was selected to supply the auxiliary power, using R245fa or R123 as the working fluid. ...

  1. Auxiliary systems

    International Nuclear Information System (INIS)

    For a undisturbed reactor operation, the various Auxiliary and Ancillary Systems must function perfectly with the Reactor Coolant System together. While the Auxiliary Systems are directly connected to the Reactor Coolant System and therefore have contact with the Reactor Coolant, the Ancillary Systems perform tasks which do not directly influence reactor operation and in part are necessary exclusively for environment protection. The design criteria of the individual systems are a result of these tasks, especially in relation to availability, operational readiness and probability of failure. (orig.)

  2. Submarine nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To provide a ballast tank, and nuclear power facilities within the containment shell of a pressure resistance structure and a maintenance operator's entrance and a transmission cable cut-off device at the outer part of the containment shell, whereby after the construction, the shell is towed, and installed by self-submerging, and it can be refloated for repairs by its own strength. Constitution: Within a containment shell having a ballast tank and a pressure resisting structure, there are provided nuclear power facilities including a nuclear power generating chamber, a maintenance operator's living room and the like. Furthermore, a maintenance operator's entrance and exit device and a transmission cable cut-off device are provided within the shell, whereby when it is towed to a predetermined a area after the construction, it submerges by its own strength and when any repair inspection is necessary, it can float up by its own strength, and can be towed to a repair dock or the like. (Yoshihara, H.)

  3. Chemistry in power plants 2011

    International Nuclear Information System (INIS)

    Within the VGB Powertech conference from 25th to 27th October, 2011, in Munich (Federal Republic of Germany), the following lectures and poster contributions were presented: (1) The revised VGB standard for water-steam-cycle Chemistry; (2) Switchover from neutral operation to oxygen treatment at the power station Stuttgart-Muenster of EnBW Kraftwerke AG; (3) Steam contamination with degradation products of organic matters present in the feedwater of the Lanxess-Rubber cogeneration plant; (4) Laboratory scale on-line noble metal deposition experiments simulating BWR plant conditions; (5) Building a new demin installation for the power plant EPZ in Borssele; (6) Replacement of the cooling tower installations in the nuclear power plant Goesgen-Daenien AG; (7) Aging of IEX resins in demin plants - Cost optimisation by adaptation of regenerants; (8) The largest DOW trademark EDI System at a combined cycled plant in Europe; (9) Upgrading river Main water to boiler feed water - Experiences with ultrafiltration; (10) Experiences with treatment of the water-steam-cycle in the RDF power plant Nehlsen Stavenhagen with film-forming amines; (11) Comparative modelling of the bubbles thermal collapse and cavitations for estimation of bubbles collapse influence; (12) Overcoming the steam quality - issues from an HRSG for the production of process steam; (13) Legionella - new requirements for power plant operation; (14) How the right chemistry in the FGD helps to improve the removal in the waste water treatment plant; (15) High efficiency filtration in dry/semi-dry FGD plants; (16) Expanding the variety of renewable fuels in the biomass power plant Timelkam using the chemical input control; (17) Corrosion, operating experiences and process improvements to increase the availability and operating time of the biomass power plant Timelkam; (18) The influence of temperature on the measurement of the conductivity of highly diluted solutions; (19) A multiparameter instrumentation approach

  4. Nuclear power plant

    International Nuclear Information System (INIS)

    The plant of the present invention can suppress the amount of clad in feedwater when drains of a moisture content separation heater or a high pressure feedwater heater are recovered. That is, the moisture content separation heater has ferrite or austenite type stainless steel heat transfer pipes. A chromium-enriched layer is formed on the surface of the heat transfer pipe by chromizing treatment or flame spraying. Then, a stainless steel heat transfer pipe having chromium-enriched layer is incorporated to at least one of the moisture content separation heater or the high pressure feedwater heater. During plant operation, the temperature of heated steams is as high as 235 to 282degC. Accordingly, this is a severe corrosion region for ferrite or austenite stainless steel. However, the chromium-enriched layer of excellent corrosion resistance is formed on the surface of the heat transfer pipe. Accordingly, metal ingredients are less leached. As a result, even if the drains are recovered to feedwater, increase of concentration of the clads in the feedwater can be prevented. (I.S.)

  5. The dynamic responses of the soil-auxiliary buildings structure interaction system

    International Nuclear Information System (INIS)

    The dynamic responses of the soil-auxiliary buildings structure interaction system in the nuclear power plant are concerned. The main distinguished feature of this study is that the extreme un-symmetry of the auxiliary buildings and reactor containment are considered. A Synthetical mechanical model for study is established. Finally, the analysis of the dynamic response of the Qinshan Nuclear Power Plant structure is taken as a simple example of applying this method and the numerical results are given

  6. Thermal Power Plant Performance Analysis

    CERN Document Server

    2012-01-01

    The analysis of the reliability and availability of power plants is frequently based on simple indexes that do not take into account the criticality of some failures used for availability analysis. This criticality should be evaluated based on concepts of reliability which consider the effect of a component failure on the performance of the entire plant. System reliability analysis tools provide a root-cause analysis leading to the improvement of the plant maintenance plan.   Taking in view that the power plant performance can be evaluated not only based on  thermodynamic related indexes, such as heat-rate, Thermal Power Plant Performance Analysis focuses on the presentation of reliability-based tools used to define performance of complex systems and introduces the basic concepts of reliability, maintainability and risk analysis aiming at their application as tools for power plant performance improvement, including: ·         selection of critical equipment and components, ·         defini...

  7. Financing solar thermal power plants

    International Nuclear Information System (INIS)

    The commercialization of concentrating solar power technology took a major step forward in the mid 1980s and early 1990s with the development of the SEGS plants in California. Over the years they have proven that parabolic trough power technologies are the most cost-effective approach for commercial scale solar power generation in the sunbelt countries of the world. However, the question must be asked why no additional solar power plants have been built following the bankruptcy of the developer of the SEGS projects, LUZ International Limited. Although many believe the SEGS projects were a success as a result of parabolic trough technology they employ, in truth, the SEGS projects were developed simply because they represented an attractive opportunity for investors. Simply states, no additional projects have been developed because no one has been able to put together a similarly attractive financial package to potential investors. More than $1.2 billion in private capital was raised in debt and equity financing for the nine SEGS plants. Investors and bankers who make these investments are the real clients for solar power technologies. They are not interested in annual solar to electric efficiencies, but in risk, return on investments, and coverage ratios. This paper will take a look at solar power projects form the financier's perspective. The challenge in moving forward is to attract private investors, commercial lenders, and international development agencies and to find innovative solutions to the difficult issues that investment in the global power market poses for solar power technologies

  8. Financing Solar Thermal Power Plants

    International Nuclear Information System (INIS)

    The commercialization of concentrating solar power technology took a major step forward in the mid 1980s and early 1990s with the development of the SEGS plants in California. Over the years they have proven that parabolic trough power technologies are the most cost-effective approach for commercial scale solar power generation in the sunbelt countries of the world. However, the question must be asked why no additional solar power plants have been build following the bankruptcy of the developer of the SEGS projects, LUZ International Limited. Although many believe the SEGS projects were a success as a result of parabolic trough technology they employ, in truth, the SEGS projects were developed simply because they represented an attractive opportunity for investors. Simply stated, no additional projects have been developed because no one has been able to put together a similarly attractive financial package to potential investors. More than $1.2 billion in private capital was raised in debt and equity financing for the nine SEGS plants. Investors and bankers who make these investments are the real clients for solar power technologies. They are not interested in annual solar to electric efficiencies, but in risk, return on investments, and coverage ratios. This paper will take a look at solar power projects from the financier's perspective. The challenge in moving forward is to attract private investors, commercial lenders, and international development agencies and to find innovative solutions to the difficult issues that investment in the global power market poses for solar power technologies

  9. Pressurised fluidised bed power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jansson, S.A.; Anderson, L. [ABB Carbon AB, Finspong (Sweden)

    1997-12-31

    The combined experience from almost 75,000 hours of operation on widely different coals in Pressurised Fluidised bed Combined-cycle (PFBC) plants in Sweden, Spain, the US and Japan have demonstrated the viability of ABB`s PFBC technology and the general simplicity of the concept, as well as plant control principles and serviceability. This technology is now commercially offered world-wide and PFBC is being recognized as a competitive solution for power and for combined heat and power applications. The combined-cycle feature makes PFBC highly efficient for power generation. When compared with conventional power plants, and for the same steam conditions, a PFBC plant typically produces at least 10% more electricity from the same amount of coal. There is potential for future additional efficiency increases. The coals used so far in the existing PFBC power plants include bituminous coals with a wide range of sulphur and ash contents, and a sub-bituminous Spanish `black lignite` with extremely high and variable levels of sulphur, ash, and moisture. Brown coal from the eastern parts of Germany will be used as the fuel in a newly ordered PFBC plant in Cottbus, Germany. Oil shale, petcoke, anthracite, and different types of biomass mixed with coal are presently being considered for other PFBC projects under discussion. PFBC is suitable for greenfield plants, but a market also exists for PFBC repowering of older steam plants. Repowering provides an opportunity to convert older, low capacity factor units into assets that lower the system`s production costs as well as improving environmental performance. Ash utilisation also holds promise, elevating the ash from a disposable waste to a valuable resource. 6 refs., 3 figs., 1 tab.

  10. Completion of a delayed nuclear power plant

    International Nuclear Information System (INIS)

    The Bushehr Nuclear Power Plant was designed and constructed up to nearly 80% by KWU in mid 1970s. The initial design was according to latest safety standards available at that time. In 1979, the German contractor, KWU, stopped the work on BNPP. In January 1994 the Contract for completion of Bushehr Nuclear Power Plant Unit-1 was signed by the AEOI and the Russian firm 'ZAES', an affiliated company of the Russian Ministry of Atomic Energy later on renamed to ASE (Atomstroyexport). In January 1996, based on this new Contract of reconstruction and completion BNPP-1 project was resumed. With Addendum No.1 to the Contract almost all responsibilities with respect to design, construction, erection, procurement, commissioning, and training of the Iranian personnel for operation of the BNPP-1 were given to the Russian firm ASE. The AEOI personnel were assigned the roles and responsibilities for review and approval of the overall completion project. The plant has undergone more than 20 years of suspension. Harsh climatic condition of Bushehr and especially high level of humidity has been a major threat to the maintenance of quality of stored and installed equipment. Due to lack of sufficient funds during 8-year Iran-Iraq war, the preservation of the plant required extensive management efforts. The plant was attacked by Iraq and some damage was made to concrete and steel containment and polar crane of BNPP-1. In order to continue the projects talking into account the current safety standards, the Iranian Nuclear Regulatory Authority (INRA), in co-operation with the IAEA and GAN, has developed the necessary safety documents. A program for integration of existing KWU equipment, buildings and structures is started. The cumulative progress of the completion has reached 62% ny September 2003. It includes: design and engineering progress - 85%, including licenses; Repair works of buildings and structures are completed and required certificates are issued and as-built design

  11. Preliminary design of the Carrisa Plains solar central receiver power plant. Volume III, Book 3. Appendices. Part 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. K.

    1983-12-31

    The auxiliary heat transport systems of the Carrisa Plains Solar Power Plant (CPSPP) comprise facilities which are used to support plant operation and provide plant safety and maintenance. The facilities are the sodium purification system, argon cover gas system, sodium receiving and filling system, sodium-water reaction product receiving system, and safety and maintenance equipment. The functions of the facilities of the auxiliary system are described. Design requirements are established based on plant operating parameters. Descriptions are given on the system which will be adequate to perform the function and satisfy the requirements. Valve and equipment lists are included in the appendix.

  12. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To prevent liquid wastes from being discharged out of the system by processing to recover them in the nuclear reactor and reusing them. Constitution: Discharge of liquid wastes to the surrounding atmosphere are completely eliminated by collecting floor drains, a part of processing water for the regeneration of liquid wastes, non-radioactive steam drains and laundry drains conventionally discharged so far out of the system, processing them in a concentrator, a desalter or the like into water of a high purity and extremely low radioactive concentration, storing the water in an exclusive storage tank and supplying it as a steam or supplementing water to each portion in the plant that requires water of such high purity and extremely low radioactivity. (Yoshihara, H.)

  13. Thermal power plants and environment

    International Nuclear Information System (INIS)

    Recent versions of the air quality models which are reviewed and approved from the Environmental Protection Agency (EPA) are analysed in favour of their application in simple and complex terrain, different meteorological conditions and modifications in the sources of pollutant emissions. Improvement of the standard methods for analysis of the risks affecting the environment from different energy sources has been carried out. The application of the newly introduced model enabled (lead to performing) risk analysis of the coal power plants compared to other types of energy sources. Detailed investigation of the risk assessment and perception from coal power plants, has been performed and applied to the Macedonian coal power plants. Introducing the concept of 'psychological pollution', a modification of the standard models and programs for risk assessment from various energy sources has been suggested (proposed). The model has been applied to REK Bitola, where statistically relevant differences in relation to the control groups have been obtained. (Original)

  14. Ocean power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dembicki, E.

    1982-01-01

    In the fall of 1980 on the shores of the Hawaiian Islands, a floating laboratory of the United States was successfully introduced for testing a heat exchanger and pipes for collecting cold water of the OTES with power of 1 MW. The first American OTES N=10-40 MW should start operation in 1985. By the year 2000, ..sigma..N of the U.S. OTES should reach 10 GW. The Japanese OTES N=10-25 MW should start up in 1989. The experimental OTES N=100 KW has been in operation since October 1981 on the Nauru Island. An OTES of 2 MW is under construction. The concern Empain-Schneider is involved in planning the OTES of closed cycle in France, and the concern CGE is planning the OTES of open cycle.

  15. Temperature Effect to Solar Power Plant

    OpenAIRE

    Modestas Pikutis

    2015-01-01

    There are a lot of different efficiency photovoltaic cells, which are used in solar power plants. All of these different photovoltaic cells are affected by different environment conditions. Maximum power point tracking is the main way to increase solar power plant efficiency. Mostly systems of maximum power point tracking are slow or inaccurate, that means the system cannot stay in maximum power point in solar power plant. This is the main reason why mostly of solar power plants are working n...

  16. Nuclear power plant

    International Nuclear Information System (INIS)

    In a condensate cleanup system and a reactor water cleanup system of a BWR-type reactor, in which primary coolants flow, there is disposed a filtering and desalting device using hollow thread membrane filter and ion exchange resin for a condensate cleanup system, and using a high temperature filter made of a metal, a metal oxide or ceramics as a filtering material and a precoat filter made of a powdery ion exchange resin as a filtering material for a reactor water cleanup system. This can completely remove cruds generated in the condensate system. Since the reactor water cleanup system comprises the powdery resin precoat-type filtering and desalting device and the high temperature filter using ceramics, ionic impurities such as radioactive materials can be removed. Accordingly, cruds are not carried into the inside of the reactor, and since the radioactive concentration in the reactor water is reduced, radiation exposure upon periodical inspection can be minimized almost to zero, to attain a clean plant. (T.M.)

  17. The Norochcholai power plant project (Sri Lanka): an example of sustainable economic development by utilisation of seawater for power island and emission control

    Energy Technology Data Exchange (ETDEWEB)

    Carrea, E.; Zimmermann, H. [Poeyry Energy, Zuerich (Switzerland)

    2008-07-01

    The paper describes how the Norochcholai project will meet Sri Lanka's energy expansion programme by realising a 3 3 300 MW coal-fired power island using solely seawater for the power plant processes and auxiliary needs. The strategic project development approach towards a coal-fired power plant is outlined, followed by an overview of the core processes utilising seawater: desalination, demineralisation, on-site hypochlorite production and chlorination, seawater flue gas desulphurisation (FGD) and waste water management. (orig.)

  18. A techno-economic comparison of fuel processors utilizing diesel for solid oxide fuel cell auxiliary power units

    Science.gov (United States)

    Nehter, Pedro; Hansen, John Bøgild; Larsen, Peter Koch

    Ultra-low sulphur diesel (ULSD) is the preferred fuel for mobile auxiliary power units (APU). The commercial available technologies in the kW-range are combustion engine based gensets, achieving system efficiencies about 20%. Solid oxide fuel cells (SOFC) promise improvements with respect to efficiency and emission, particularly for the low power range. Fuel processing methods i.e., catalytic partial oxidation, autothermal reforming and steam reforming have been demonstrated to operate on diesel with various sulphur contents. The choice of fuel processing method strongly affects the SOFC's system efficiency and power density. This paper investigates the impact of fuel processing methods on the economical potential in SOFC APUs, taking variable and capital cost into account. Autonomous concepts without any external water supply are compared with anode recycle configurations. The cost of electricity is very sensitive on the choice of the O/C ratio and the temperature conditions of the fuel processor. A sensitivity analysis is applied to identify the most cost effective concept for different economic boundary conditions. The favourite concepts are discussed with respect to technical challenges and requirements operating in the presence of sulphur.

  19. Study on Use of Fuel-Cell Auxiliary Power Units in Refrigerator Cars Employed for Delivery to Convenience Store

    Science.gov (United States)

    Katayama, Noboru; Kamiyama, Hideyuki; Kogoshi, Sumio; Kudo, Yusuke; Fukada, Takafumi; Ogawa, Makoto

    The use of fuel-cell auxiliary power units (FC-APU) in refrigerator cars employed delivery to for convenience store delivery has been studied. The delivery pattern is assumed to be a typical pattern that includes driving between convenience stores or between a delivery center and a convenience store, unloading, driver's lunch break. The M15 driving mode, which simulates the driving condition in urban areas, is used as the driving mode in the delivery pattern. The FC-APU system includes a proton-exchange membrane fuel cell (PEFC) module, an inverter, and DC/DC converter. Bench tests of the FC-APU are performed to determine the hydrogen fuel consumption rate and the energy efficiency; these values depend on the output power of the PEFC module. The calculated relationship between the output power and fuel consumption rate of a current used system, which consists of an alternator and a secondary battery, are used to estimate the energy efficiency of the current used system. On the basis of the measurement data in this study and the results for the model proposed by Brodric et al. [C. J. Brodrick et al., Trans. Res. D, vol 7, pp. 303 (2002)], the payback period is calculated. The results indicate that the payback period would be 2.1 years when the FC-APU operates at a load of 70%.

  20. Operating experience from Swedish nuclear power plants 2008

    International Nuclear Information System (INIS)

    The overall safety level of the Swedish nuclear power plants during 2008 has been high, despite disturbances that caused longer shutdowns in some plants. A number of improvements have been made in order further to improve the safety of the plants. Electricity production from the power plants amounted to 61.3 TWh, which represents 43 % of Sweden's total electricity production during the year. The total average energy availability was lower than in previous years. For the BWR reactors, it amounted to 78 %, as against an average value of about 84 % for the last five years. For the PWRs, the energy availability was about 87 % in 2008, which is about the same as the five-year average. Oskarshamn 3 and Forsmark 3 suffered from long shutdowns due to cracks in the reactor control rods, which was a contributory reason for the poor performance figures for the BWR reactors. On the PWR side, it was Ringhals 2's problems with auxiliary feed water system capacity that caused a longer shutdown. During the year, KSU started its courses for the maintenance staff of all Swedish power plants at the shut-down Barsebaeck site. This provides training for electrical and mechanical maintenance personnel under authentic conditions, working on real components and systems before doing the same under live conditions at their home power plants

  1. Packing solutions for power plants

    International Nuclear Information System (INIS)

    Asbestos packings are being replaced in more and more countries with alternative products. This paper discusses modern packing solutions for valves and pumps in power plants. Die-moulded packing rings made of expanded graphite foil are described m detail, with recommendations for correct installation. Application examples for spring-loaded valves and cover lid seals are given. As an alternative for repair and service use, a braided expanded graphite packing reinforced with Inconel wire is described. Proposals for sealing various pump applications in power plants are also made. (Author)

  2. Loviisa nuclear power plant analyzer

    International Nuclear Information System (INIS)

    The APROS Simulation Environment has been developed since 1986 by Imatran Voima Oy (IVO) and the Technical Research Centre of Finland (VTT). It provides tools, solution algorithms and process components for use in different simulation systems for design, analysis and training purposes. One of its main nuclear applications is the Loviisa Nuclear Power Plant Analyzer (LPA). The Loviisa Plant Analyzer includes all the important plant components both in the primary and in the secondary circuits. In addition, all the main control systems, the protection system and the high voltage electrical systems are included. (orig.)

  3. Nuclear power plant life extension

    International Nuclear Information System (INIS)

    Current licensing emphasis is different from that existing when older nuclear power plants received their operating licenses. Today, there is increased regulatory focus on utility performance measured through new inspections such as the safety system functional inspection and the safety systems outage modifications inspection; and the use of performance indicators. These programs are intended to identify poorer performing plants and concentrate on improving overall plant performance. This paper discusses how, in an attempt to improve the maintenance performance of the nuclear industry, the U.S. Nuclear Regulatory Commission recently began work on a maintenance rule. In addition, the NRC will require partial probabilistic risk evaluations for each plant that will provide new insights as to a plant's risk. Risk information is being used to prioritize inspections

  4. Plant power supply device in an atomic power plant

    International Nuclear Information System (INIS)

    Object: To avoid tripping of a 6.9 kV class bus line and to decrease a large electric current momentarily flown into a start transformer, in despite of the fact that the bus line is not changed over resulted from actuation of a generator lock-out relay. Structure: An atomic power plant comprising a bus line for a two-system plant power supply and a start transformer receiving power from an exterior system, characterized by the provision of a breaker for effecting the change-over of only one system bus line simultaneously with the reactor scrum and a breaker for effecting the change-over of the other bus line before a generator is tripped as a result of actuation of a generator lock-out relay in a predetermined period of time after the reactor scrum, to thereby reduce the momentary large current to the start transformer. (Kamimura, M.)

  5. Engine Auxiliary System Guideline: Cooling Systems

    OpenAIRE

    Kela, Suvi

    2015-01-01

    The thesis was done for Wärtsilä Technical Services organization. The assignment was to consolidate a guideline for cooling systems as an engine auxiliary system covering the Wärtsilä 4-stroke engines currently in production. The guideline was to include information considering both marine and power plants installations. The sources of information were internal documentation from Wärtsilä, literature review and discussions with Wärtsilä cooling system experts. The guideline includes informati...

  6. Investigations in the modelling and control of a medium voltage hybrid inverter system that uses a low voltage /low power rated auxiliary current source inverter

    OpenAIRE

    Papadopoulos, Savvas; Rashed, Mohamed; Klumpner, Christian; Wheeler, Patrick

    2016-01-01

    Hybrid converters consist of a main inverter processing the bulk of the power with poor waveform performance and a fast and versatile auxiliary inverter to correct the distortion. In this paper, the main converter is a medium voltage NPC inverter and the auxiliary inverter is a low-voltage and low-current rated current source inverter (CSI), with series capacitor being used to minimize the CSI voltage stress. The result is a high output current quality which is obtained with a very low switch...

  7. CAREM-25. Auxiliary systems

    International Nuclear Information System (INIS)

    CAREM is an innovative PWR reactor whose prototype will be of small power generation capacity (100 M Wt, about 25 M We). CAREM design is based on light water integrated reactor with slightly enriched uranium. In this work, a summary of the functions and most relevant design characteristics of main auxiliary systems associated to the chain of heat removal and physicochemical - radiological treatment of the cooling fluids of the CAREM-25 prototype is presented. Even though these auxiliary systems of the reactor are not safety system, they fulfill functions related with the nuclear safety at different operative modes of the reactor. (author)

  8. CAREM-25. Auxiliary systems

    International Nuclear Information System (INIS)

    CAREM is an innovative PWR reactor whose prototype will be of small power generation capacity (100MWt, about 25MWe).CAREM design is based on light water integrated reactor with slightly enriched uranium.In this work, a summary of the functions and most relevant design characteristics of main auxiliary systems associated to the chain of heat removal and physicochemical - radiological treatment of the cooling fluids of the CAREM-25 prototype is presented.Even though these auxiliary systems of the reactor are not safety system, they fulfill functions related with the nuclear safety at different operative modes of the reactor

  9. Solar thermionic power plant. II

    Science.gov (United States)

    Abou-Elfotouh, F.; Almassary, M.; Fatmi, H.

    It has been shown that the geometric configuration of a central receiver solar electric power plant SEPP can be optimized for the high power density and concentration required for the operation of a thermionic converter. The working period of a TDC constructed on the top of a SEPP in Riyadh area is 5 to 6 hours per day in winter and 6 to 8 hours in summer. At the 25 percent conversion efficiency achieved by a laboratory test model, a reduction in the cost per unit power of 8-12 per cent is expected. The spectral behavior and work functions of the working surface of the thermionic electrodes were investigated

  10. Noise from wind power plants

    International Nuclear Information System (INIS)

    First, the generation of noise at wind power plants and the character of the sound is described. The propagation of the sound and its dependence on the structure of the ground and on wind and temperature is treated next. Models for calculation of the noise emission are reviewed and examples of applications are given. Different means for reducing the disturbances are described

  11. Fire protection in power plants

    International Nuclear Information System (INIS)

    Graphex-CK 23 is a unique sodium fire extinction product. Minimum amounts of powder are required for very fast action. The sodium can be put to use again, when the fire has been extinguished. It can be applied in other industrial branches and with other metals, e.g. sodium/potassium circuits or lithium coolant in power plants.

  12. Docommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The German utilities operating nuclear power plants have long concerned themselves with aspects of decommissioning and for this purpose an engineering company was given a contract to study the entire spectrum of decommissioning. The results of this study have been available in autumn 1980 and it is possible to discuss all the aspects of decommissioning on a new basis. Following these results no change in the design concept of LWR nuclear power plants in operation or under construction is necessary because the techniques, necessary for decommissioning, are fully available today. The technical feasibility of decommissioning for power plants of Biblis A and KRB type has been shown in detail. The calculations of the quantity of waste produced during removal of a nuclear power plant could be confirmed and it could be determined with high procedure. The radiation dose to the decommissioning personnel is in the range of the radiation protection regulations and is in the same range as the radiation dose to the personnel within a yearly inservice inspection. (AF)

  13. World nuclear power plant capacity

    International Nuclear Information System (INIS)

    This report provides the background information for statistics and analysis developed by NUKEM in its monthly Market Report on the Nuclear Fuel Cycle. The assessments in this Special Report are based on the continuous review of individual nuclear power plant projects. This Special Report begins with tables summarizing a variety of nuclear power generating capacity statistics for 1990. It continues with a brief review of the year's major events regarding each country's nuclear power program. The standard NUKEM Market Report tables on nuclear plant capacity are given on pages 24 and 25. Owing to space limitations, the first year shown is 1988. Please refer to previous Special Reports for data covering earlier years. Detailed tables for each country list all existing plants as well as those expected by NUKEM to be in commercial operation by the end of 2005. An Appendix containing a list of abbreviations can be found starting on page 56. Only nuclear power plants intended for civilian use are included in this Special Report. Reactor lifetimes are assumed to be 35 years for all light water reactors and 30 years for all other reactor types, unless other data or definite decommissioning dates have been published by the operators. (orig./UA)

  14. Improvement of fire protection measures for nuclear power plants

    International Nuclear Information System (INIS)

    Improvements of fire protection measures for nuclear power plants were performed as following items: Collection of necessary data and evaluation of parameters, Walk down in the typical BWR and PWR plants, Application of developed analysis method to actual plants, Development of fire hazard analysis manual. With regard to fire tests for the fire data acquisition, the test plan was made about cable fire, oil fire and electric cabinet fire in the concrete test facilities. Implementation of fire hazard analysis model and simulation were performed as following items: Fire analysis codes FDS, CFAST were implemented in order to analyze the fire progression phenomena, Trial calculation of fire hazard for typical NPP by FDS were performed for the Auxiliary feed water pump room (PWR) and the High pressure coolant flooder pump room (BWR). (author)

  15. Sensitivity of Power Station Auxiliary Network to the Possibility of Ferroresonance Occurrence

    Directory of Open Access Journals (Sweden)

    Józef Wiśniewski

    2014-12-01

    Full Text Available Implementation of the new class of 1000 MW power units to a power system creates new problems associated with the operation of its individual components and circuits. One such issue is the phenomenon of ferroresonance in the internal load network. This is not a new problem but it requires examination due to the higher level of supply voltage (10 kV. This paper examines the possibility of ferroresonance occurrence and its character depending on the extent of the network, voltage transformers’ load, the effect of grounding resistors in the star point of the power transformer and the presence of varistor surge arresters. The results are presented in the form of ferroresonance maps. They allow assessing the impact of various parameters on the phenomenon, explaining the reasons for possible failure and properly programming the network conditions in order to avoid the risk of ferroresonance.

  16. Electrical start-up for diesel fuel processing in a fuel-cell-based auxiliary power unit

    Science.gov (United States)

    Samsun, Remzi Can; Krupp, Carsten; Tschauder, Andreas; Peters, Ralf; Stolten, Detlef

    2016-01-01

    As auxiliary power units in trucks and aircraft, fuel cell systems with a diesel and kerosene reforming capacity offer the dual benefit of reduced emissions and fuel consumption. In order to be commercially viable, these systems require a quick start-up time with low energy input. In pursuit of this end, this paper reports an electrical start-up strategy for diesel fuel processing. A transient computational fluid dynamics model is developed to optimize the start-up procedure of the fuel processor in the 28 kWth power class. The temperature trend observed in the experiments is reproducible to a high degree of accuracy using a dual-cell approach in ANSYS Fluent. Starting from a basic strategy, different options are considered for accelerating system start-up. The start-up time is reduced from 22 min in the basic case to 9.5 min, at an energy consumption of 0.4 kW h. Furthermore, an electrical wire is installed in the reformer to test the steam generation during start-up. The experimental results reveal that the generation of steam at 450 °C is possible within seconds after water addition to the reformer. As a result, the fuel processor can be started in autothermal reformer mode using the electrical concept developed in this work.

  17. Optimization of Fuel Consumption and Emissions for Auxiliary Power Unit Based on Multi-Objective Optimization Model

    Directory of Open Access Journals (Sweden)

    Yongpeng Shen

    2016-02-01

    Full Text Available Auxiliary power units (APUs are widely used for electric power generation in various types of electric vehicles, improvements in fuel economy and emissions of these vehicles directly depend on the operating point of the APUs. In order to balance the conflicting goals of fuel consumption and emissions reduction in the process of operating point choice, the APU operating point optimization problem is formulated as a constrained multi-objective optimization problem (CMOP firstly. The four competing objectives of this CMOP are fuel-electricity conversion cost, hydrocarbon (HC emissions, carbon monoxide (CO emissions and nitric oxide (NO x emissions. Then, the multi-objective particle swarm optimization (MOPSO algorithm and weighted metric decision making method are employed to solve the APU operating point multi-objective optimization model. Finally, bench experiments under New European driving cycle (NEDC, Federal test procedure (FTP and high way fuel economy test (HWFET driving cycles show that, compared with the results of the traditional fuel consumption single-objective optimization approach, the proposed multi-objective optimization approach shows significant improvements in emissions performance, at the expense of a slight drop in fuel efficiency.

  18. Dynamic evaluation of low-temperature metal-supported solid oxide fuel cell oriented to auxiliary power units

    Science.gov (United States)

    Wang, Zhenwei; Berghaus, Jörg Oberste; Yick, Sing; Decès-Petit, Cyrille; Qu, Wei; Hui, Rob; Maric, Radenka; Ghosh, Dave

    A metal-supported solid oxide fuel cell (SOFC) composed of a Ni-Ce 0.8Sm 0.2O 2- δ (Ni-SDC) cermet anode and an SDC electrolyte was fabricated by suspension plasma spraying on a Hastelloy X substrate. The cathode, an Sm 0.5Sr 0.5CoO 3 (SSCo)-SDC composite, was screen-printed and fired in situ. The dynamic behaviour of the cell was measured while subjected to complete fuel shutoff and rapid start-up cycles, as typically encountered in auxiliary power units (APU) applications. A promising performance - with a maximum power density (MPD) of 0.176 W cm -2 at 600 °C - was achieved using humidified hydrogen as fuel and air as the oxidant. The cell also showed excellent resistance to oxidation at 600 °C during fuel shutoff, with only a slight drop in performance after reintroduction of the fuel. The Cr and Mn species in the Hastelloy X alloy appeared to be preferentially oxidized while the oxidation of nickel in the metallic substrate was temporarily alleviated. In rapid start-up cycles with a heating rate of 60 °C min -1, noticeable performance deterioration took place in the first two thermal cycles, and then continued at a much slower rate in subsequent cycles. A postmortem analysis of the cell suggested that the degradation was mainly due to the mismatch of the thermal expansion coefficient across the cathode/electrolyte interface.

  19. Financing Solar Thermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Price, H. W.; Kistner, R.

    1999-11-01

    The commercialization of concentrating solar power technology took a major step forward in the mid 1980s and early 1990s with the development of the SEGS plants in California. Over the years they have proven that parabolic trough power technologies are the most cost-effective approach for commercial scale solar power generation in the sunbelt countries of the world. However, the question must be asked why no additional solar power plants have been build following the bankruptcy of the developer of the SEGS projects, LUZ International Limited. Although many believe the SEGS projects were a success as a result of parabolic trough technology they employ, in truth, the SEGS projects were developed simply because they represented an attractive opportunity for investors. Simply stated, no additional projects have been developed because no one has been able to put together a similarly attractive financial package to potential investors. More than $1.2 billion in private capital was raised i n debt and equity financing for the nine SEGS plants. Investors and bankers who make these investments are the real clients for solar power technologies. They are not interested in annual solar to electric efficiencies, but in risk, return on investments, and coverage ratios. This paper will take a look at solar power projects from the financier's perspective. The challenge in moving forward is to attract private investors, commercial lenders, and international development agencies and to find innovative solutions to the difficult issues that investment in the global power market poses for solar power technologies.

  20. Conception and design of steam power plants

    International Nuclear Information System (INIS)

    The manual presents the fundamentals of thermodynamics and fluid mechanics, the main components of steam power plants, and the power generation process. The following concepts and subjects are discussed at length: steam generator; steam turbines; turbogenerators; condensers; cooling technology; water/steam cycle and water treatment; design data of fossil-fuelled power plants; design and optimisation of nuclear power plant thermodynamics; pipelines and fittings; control systems in steam power plants; connection to the electricity grid and self-supply of thermal power plants; power plant transformer concepts and definitions. (HAG)

  1. Energy Efficiency of Thermal Power Station Auxiliary Power Consumption and Cost Savings in Carbon Footprint in India

    OpenAIRE

    K. Thirumavalavan; Mathi Ramalingam; Jayalalitha Subbaiahan

    2014-01-01

    This study discusses about the energy conservation and carbon credits in Thermal Power Stations in India. Indian power scenario, accounts for 66.4% (1,36,436 MW) of Thermal Power Generation. The Thermal Power Stations have the problem of consuming 8.5% of power it produces. Also it has the drawback of emission factors which leaves the carbon footprint, which has to be controlled as per the Clean Development Mechanism (CDM). The United Nations Framework watches ...

  2. The Expert System Application For Inspection Of The Power Plants

    International Nuclear Information System (INIS)

    This paper describes the application of expert system to evaluate and consider the problem encountered in this fields are complex and time consuming. As as example several factors affecting system voltage selections are load magnitude, distance from the main power supply, safety, standards, cost of utilization and service system equipment, and future load growth. The inspection deal with interactions between alternatives, uncertainties, and important non financial parameter. Several complex problems are multiple objective functions, multiple constraints, complex system interactions, the need for accuracy, the need for trade off, optimization, and coordination of the decision making process. ASDEP is one of the expert system for electric power plant design that describe the application of the artificial intelligence to design of a power plan's electrical auxiliary system. In this circumstance this paper will elaborate another aspect for using the expert system in the inspection

  3. Safety for nuclear power plants

    International Nuclear Information System (INIS)

    The September 11, 2001 terrorist attacks on the World Trade Center in New York have reopened the debate in Germany abut the safety of existing nuclear power plants. On the one hand, it culminated in the demand, made from a prominent political position, to disconnect from the grid prematurely five of the older nuclear power plants because they offered no sufficient protection from terrorist attacks carried out by means of commercial airliners. On the other hand, the competent German Federal Ministry of the Interior to this day has not been able to detect a hazardous situation for Germany which would require nuclear power plants (or other facilities) to be shut down - temporarily -so as to reduce their hazard potential. The legal situation is discussed in detail. It is evident that the debate about the safety of any kind of industrial plants will go on and will be revived by any kind of event. Despite the growing need for public safety, it must not be overlooked in the public debate that an absolute exclusion of risk is impossible and that, consequently, there can be no absolute protection of any legal object. (orig.)

  4. Loss of main and auxiliary feedwater event at the Davis-Besse Plant on June 9, 1985

    International Nuclear Information System (INIS)

    On June 9, 1985, Toledo Edison Company's Davis-Besse Nuclear Power Plant, located in Ottawa County, Ohio, experienced a partial loss of feedwater while the plant was operating at 90% power. Following a reactor trip, a loss of all feedwater occurred. The event involved a number of equipment malfunctions and extensive operator actions, including operator actions outside the control room. Several operator errors also occurred during the event. This report documents the findings of an NRC Team sent to Davis-Besse by the NRC Executive Director for Operations in conformance with the staff-proposed Incident Investigation Program

  5. Evaluation of Fuel Cell Auxiliary Power Units for Heavy-Duty Diesel Trucks

    OpenAIRE

    Brodrick, Christie-Joy; Lipman, Timothy; Farshchi, Mohammad; Lutsey, Nicholas; Dwyer, Harry; Sperling, Daniel; Gouse, S. William; King, Foy

    2002-01-01

    A large number of heavy-duty trucks idle a significant amount. Heavy-duty line-haul engines idle about 20-40% of the time the engine is running, depending on season and operation. Drivers idle engines to power climate control devices (e.g., heaters and air conditioners) and sleeper compartment accessories (e.g., refrigerators, microwave ovens, and televisions) and to avoid start-up problems in cold weather. Idling increases air pollution and energy use, as well as wear and tear on engines. Ef...

  6. Evaluation of Fuel Cell Auxiliary Power Units for Heavy-Duty Diesel Trucks

    OpenAIRE

    Brodrick, Christie-Joy; Lipman, Timothy; Farshchi, Mohammad; Lutsey, Nicholas P.; Dwyer, Harry A.; Sperling, Dan; Gouse, Bill; Harris, D Bruce; King, Foy G

    2002-01-01

    A large number of heavy-duty trucks idle a significant amount. Heavy-duty line-haul truck engines idle about 20-40% of the time the engine is running, depending on season and operation. Drivers idle engines to power climate control devices (e.g., heaters and air conditioners) and sleeper compartment accessories (e.g., refrigerators, microwave ovens, and televisions) and to avoid start-up problems in cold weather. Idling increases air pollution and energy use, as well as wear and tear on engin...

  7. Evaluation of Fuel Cell Auxiliary Power Units for Heavy-Duty Diesel Trucks

    OpenAIRE

    Brodrick, Christie-Joy; Lipman, Timothy; Farshchi, Mohammad; Lutsey, Nicholas; Dwyer, Harry; Sperling, Daniel; Gouse, S. William; King, Foy

    2002-01-01

    A large number of heavy-duty trucks idle a significant amount. Heavy-duty line-haul engines idle about 20-40% of the time the engine is running, depending on season and operation. Drivers idle engines to power climate control devices (e.g., heaters and air conditioners) and sleeper compartment accessories (e.g., refrigerators, microwave ovens, and televisions) and to avoid start-up problems in cold weather. Idling increases air pollution and energy use, as well as wear and tear on engines....

  8. BIOFEAT: Biodiesel fuel processor for a vehicle fuel cell auxiliary power unit. Study of the feed system

    Science.gov (United States)

    Sgroi, M.; Bollito, G.; Saracco, G.; Specchia, S.

    An integrated auxiliary power unit (APU) based on a 10 kW e integrated biodiesel fuel processor has been designed and is being developed. Auto-thermal reforming (ATR) and thermal cracking (TC) were considered for converting the fuel into a hydrogen-rich gas suitable for PEM fuel cells. The fuel processor includes also a gas clean-up system that will reduce the carbon monoxide in the primary processor exit gas to below 10 ppm via a new heat-integrated CO clean-up unit, based on the assembly of catalytic heat exchange plates, so as to meet the operational requirements of a PEMFC stack. This article is devoted to the study and selection of the proper feed strategy for the primary fuel processor. Different pre-treatment and feed alternatives (e.g. based on nozzles or simple coils) were devised and tested for the ATR processors, which turned out to be the preferred primary processing route. A nozzle-based strategy was finally selected along with special recommendations about the constituent materials and the operating procedures to be adopted to avoid coking and nozzle corrosion as well as to allow a wide turn down ratio.

  9. Optimization of Maputo Power Plant

    OpenAIRE

    Abacar, Armando

    2013-01-01

    The Electricidade de Moçambique, E.P. (EDM) is the power utility in Mozambique, responsible to generate, transport and distribute electricity all over the country. The company has three gas turbines installed at Maputo Power Plant. All units burn diesel oil and are used only for back up. Currently only the unit #2 is available for operation. The main constraint that EDM faces is the high operation costs due to diesel price. Hence the company is considering converting units #2 and #3 to burn n...

  10. Nuclear power plants and environment

    International Nuclear Information System (INIS)

    The question of nuclear power plants is analysed in details. The fundamental principles of reactors are described as well as the problems of safety involved with the reactor operation and the quantity and type of radioactive released to the environment. It shows that the amount of radioactive is very long. The reactor accidents has occurred, as three mile island, are also analysed. (M.I.A.)

  11. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

  12. Tidal Power Plant Energy Estimation

    Directory of Open Access Journals (Sweden)

    Silva–Casarín R.

    2010-04-01

    Full Text Available In this paper a methodology is presented which allows a quick and simple means of estimating the potential energy that can be obtained from a tidal power plant. The evaluation is made using a normalised nomograph, which is a function of the area of the tidal basin against the electricity installed capacity to thus obtain the potential energy for any location. The results describe two means of operation, one of "flow tide" and the other "flow–ebb tides", with two tidal basin systems operating: single and double reservoir systems. To obtain the normalised nomograph the numerical results for simulations of several tidal power plants under differing operational conditions over a period of one year. These conditions were established by varying the electricity installed capacity, the hydraulic conditions in "flow tide", "ebb tides" or both and with single or double reservoir systems and using sea level information taken every 15 minutes. To validate the model information from the tidal power plant at Rance, France, was used, which includes data concerning production, electricity installed capacity, turbine characteristics and tidal ranges. A very good correlation was found between the results of the numerical model and those reported in various technical reports.

  13. STARFIRE: a commercial tokamak fusion power plant study

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    STARFIRE is a 1200 MWe central station fusion electric power plant that utilizes a deuterium-tritium fueled tokamak reactor as a heat source. Emphasis has been placed on developing design features which will provide for simpler assembly and maintenance, and improved safety and environmental characteristics. The major features of STARFIRE include a steady-state operating mode based on continuous rf lower-hybrid current drive and auxiliary heating, solid tritium breeder material, pressurized water cooling, limiter/vacuum system for impurity control and exhaust, high tritium burnup and low vulnerable tritium inventories, superconducting EF coils outside the superconducting TF coils, fully remote maintenance, and a low-activation shield. A comprehensive conceptual design has been developed including reactor features, support facilities and a complete balance of plant. A construction schedule and cost estimate are presented, as well as study conclusions and recommendations.

  14. Method of waste management for a nuclear power plant

    International Nuclear Information System (INIS)

    The invention deals with decentralized management of radioactive waste from nuclear power plants. For this purpose a method is proposed by which the volume of activated and/or contaminated parts is first of all reduced to an extent permitting the use of safety and auxiliary systems already existing in the plant and the installation of additional systems for treatment at low cost. The volume reduction consists in fragmentation of the parts in portions by means of cutting, flame-cutting, and machining at the point of dismounting or in the storage pool. Further treatment like pressing, melting down, deep-freezing with subsequent crushing, or chemical treatment of the contaminated material will follow before it will be packed and transported away. The inventions further provide for decontamination of the parts before or after volume reduction. (HR)

  15. STARFIRE: a commercial tokamak fusion power plant study

    International Nuclear Information System (INIS)

    STARFIRE is a 1200 MWe central station fusion electric power plant that utilizes a deuterium-tritium fueled tokamak reactor as a heat source. Emphasis has been placed on developing design features which will provide for simpler assembly and maintenance, and improved safety and environmental characteristics. The major features of STARFIRE include a steady-state operating mode based on continuous rf lower-hybrid current drive and auxiliary heating, solid tritium breeder material, pressurized water cooling, limiter/vacuum system for impurity control and exhaust, high tritium burnup and low vulnerable tritium inventories, superconducting EF coils outside the superconducting TF coils, fully remote maintenance, and a low-activation shield. A comprehensive conceptual design has been developed including reactor features, support facilities and a complete balance of plant. A construction schedule and cost estimate are presented, as well as study conclusions and recommendations

  16. Decommissioning Experience: Trojan Nuclear Power Plant, United States of America

    International Nuclear Information System (INIS)

    At the Trojan nuclear power plant, it was found that operation of the existing spent fuel pool cleanup systems after shutdown was costly during the period that the fuel was waiting to be sent to an ISFSI. The existing system was interlinked with other systems on the site. It was found to be less expensive to provide an independent cooling and cleanup service for the pool. This allowed other decommissioning activities to be continued. The EPRI report provides a guide to establishing an independent fuel pool auxiliary system. This was needed for the period prior to transferring fuel to dry storage in an ISFSI. In June 2002, EPRI published another report summarizing the experience and changes that had been made at a number of plants in providing an independent spent fuel pool cooling and cleanup system

  17. Financing nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Much is at stake in developing a financial strategy for decommissioning nuclear power plants. Since decommissioning experience is limited to relatively small reactors, will the costs associated with larger reactors be significantly higher. Certainly the decommissioning issue intersects with other critical issues that will help to determine the future of commercial nuclear power in the US. The author examines briefly the basic concepts and terms related to decommissioning expenses, namely: (1) segregated fund; (2) non-segregated fund; (3) external method; and (4) internal method. He concludes that state regulatory commissions have turned increasingly to the external funding method because of increasing costs and related problems associated with nuclear power, changing conditions and uncertainties concerned with utility restructuring, and recent changes in federal tax laws related to decommissioning. Further, this trend is likely to continue if financial assurance remains a primary concern of regulators to protect this public interest

  18. Nuclear power plant computer replacement

    International Nuclear Information System (INIS)

    Consumers Power Company (CPCo) has recently completed an ambitious project to replace the non-safety-related plant process computer for the Palisades Nuclear Plant. The replacement computer retains the functions of the old plant computer system with minor exceptions. However, the architecture of the new computer system is vastly improved from the old plant computer. The hardware and software components of the new computer system are the state of the art. The old system consisted of five stand-alone computers, each performing their intended function separately. The new architecture employs a number of computing and data acquisition nodes networked together to gather, share, process, present, and store data more efficiently. For cost efficiency, some of the old hardware, such as the Critical Functions Monitoring System multiplexer, has been retained. The new computer system has a significantly higher availability, and lower maintenance cost. It performs certain functions that were not possible with the old system, such as real-time validation of rod position monitored by the Plant Information Processor and the Secondary Position Indicator. While the new computer system is more capable, more reliable, more user friendly, and easier to maintain, taking it to operability status presented CPCo with some new and challenging issues

  19. Robots for nuclear power plants

    International Nuclear Information System (INIS)

    In many industrial applications of robots, the objective is to replace human workers with machines that are more productive, efficient, and accurate. But for nuclear applications, the objective is not so much to replace workers as it is to extend their presence - for example, to project their reach into areas of a nuclear plant where the thermal or radiation environment prohibits or limits a human presence. The economic motivation to use robots for nuclear plant inspection and maintenance is centered on their potential for improving plant availability; a by-product is the potential for reducing the occupational radiation exposure of plant personnel. Robotic equipment in nuclear applications may be divided into two broad categories: single-purpose devices with limited ability to perform different operations, and reprogrammable, multi-purpose robots with some degree of computer-based artificial intelligence. Preliminary assessments of the potential for applying robotics in nuclear power plants - mainly at surveillance and inspection tasks - have been carried out. Future developments are considered

  20. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  1. Atucha I nuclear power plant transients analysis

    International Nuclear Information System (INIS)

    A program for the transients simulation thermohydraulic calculation without loss of coolant (KWU-ENACE development) to evaluate Atucha I nuclear power plant behaviour is used. The program includes systems simulation and nuclear power plants control bonds with real parameters. The calculation results show a good agreement with the output 'protocol' of various transients of the nuclear power plant, keeping the error, in general, lesser than ± 10% from the variation of the nuclear power plant's state variables. (Author)

  2. The application of composite structures in nuclear power plant construction

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Jun Young [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

    2003-04-01

    With the initiation of commercial operations of Kori Nuclear Power Plant Unit 1 in 1978, Korea became the 21{sup st} country to utilize nuclear power. As of the end of 2002, eighteen units are in operation and two units are under construction. A further eight units are to be built by the year 2015. The construction time of each floor of the KSNP Auxiliary Building has taken about 120 days; the installation and removal of shoring represents over 30% of this construction time. An additional problem with this was that no other work could proceed during the concrete curing. In order to reduce the capital costs of nuclear power plants and minimize uncertainty of investors, it is important to develop a method of plant construction which can increase productivity and quality. For Shin Kori NPP Unit 1 and 2, KHNP determined that composite structures (with a non-shoring method) should be used for the entire Auxiliary Building and Compound Building. With composite structures (including the non-shoring method), the requirements of a framework system, shoring installation and removal activities are not necessary. In addition, temporary shoring materials will be reduced and more construction space, useful for lay-down of material and equipment, will be available. Furthermore, the steel beams which will support the deck-plate are used as substitutes for embedded plates. The current ACI design codes do not provide a consistent design method for composite frame structures. At the present, AISC-LRFD is the single applicable code, although it is the concrete which governs the structural behavior.

  3. Investigation of the Start-up Strategy for a Solid Oxide Fuel Cell Based Auxiliary Power Unit under Transient Conditions

    Directory of Open Access Journals (Sweden)

    Michael R. von Spakovsky

    2005-06-01

    Full Text Available

    A typical approach to the synthesis/design optimization of energy systems is to only use steady state operation and high efficiency (or low total life cycle cost at full load as the basis for the synthesis/design. Transient operation as reflected by changes in power demand, shut-down, and start-up are left as secondary tasks to be solved by system and control engineers once the synthesis/design is fixed. However, start-up and shut-down may be events that happen quite often and, thus, may be quite important in the creative process of developing the system. This is especially true for small power units used in transportation applications or for domestic energy supplies, where the load demand changes frequently and peaks in load of short duration are common. The duration of start-up is, of course, a major factor which must be considered since rapid system response is an important factor in determining the feasibility of solid oxide fuel cell (SOFC based auxiliary power units (APUs. Start-up and shut-down may also significantly affect the life span of the system due to thermal stresses on all system components. Therefore, a proper balance must be struck between a fast response and the costs of owning and operating the system so that start-up or any other transient process can be accomplished in as short a time as possible yet with a minimum in fuel consumption.

    In this research work we have been studying the effects of control laws and strategies and transients on system performance. The results presented in this paper are based on a set of transient models developed and implemented for the components of a 5 kWe net power SOFC based APU and for the high-fidelity system which results from their integration. The simulation results given below are for two different start-up approaches: one with steam recirculation and component pre-heating and the second without either. These start-up simulations were performed for fixed values of a number of

  4. Advanced Coordinating Control System for Power Plant

    Institute of Scientific and Technical Information of China (English)

    WU Peng; WEI Shuangying

    2006-01-01

    The coordinating control system is popular used in power plant. This paper describes the advanced coordinating control by control methods and optimal operation, introduces their principals and features by using the examples of power plant operation. It is wealthy for automation application in optimal power plant operation.

  5. New hydro power plant Dobsina III

    International Nuclear Information System (INIS)

    Another power plant will be added to the hydroelectric power plant Dobsina. Preparations for the construction of a small hydro power plant have started on the streams Hnilec and Dobsinsky Brook. Dobsina III will extend the portfolio of renewable sources of Slovenske elektrarne. (author)

  6. Occupational dose control in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Reduction in occupational exposure at nuclear power plants is desirable not only in the interest of the health and safety of plant personnel, but also because it enhances the safety and reliability of the plants. This report summarises the current trends of doses to workers at nuclear power plants and the achievements and developments regarding methods for their reduction

  7. Nuclear power plant operating experience, 1976

    International Nuclear Information System (INIS)

    This report is the third in a series of reports issued annually that summarize the operating experience of U.S. nuclear power plants in commercial operation. Power generation statistics, plant outages, reportable occurrences, fuel element performance, occupational radiation exposure and radioactive effluents for each plant are presented. Summary highlights of these areas are discussed. The report includes 1976 data from 55 plants--23 boiling water reactor plants and 32 pressurized water reactor plants

  8. Wind Power Plant Control - An Overview

    OpenAIRE

    Altin, Müfit; Teodorescu, Remus; Bak-Jensen, Birgitte; RODRIGUEZ, Pedro; Iov, Florin; Kjær, Philip C.

    2010-01-01

    Recent developments in wind turbine technology go towards installation of larger Wind Power Plants (WPPs). Therefore, power system operators have been challenged by the WPP penetration impacts in order to maintain reliabillity and stability of the power system. The revised grid codes have concentrated on the WPP connection point and as a result a WPP is considered as a single power plant. Nevertheless, compared to conventional power plants, WPPs have different inherent features such as conver...

  9. Performance Based Logistics (PBL) for the FA-18/S-3/P-3/C-2 auxiliary power unit (APU) at Honeywell: an applied analysis

    OpenAIRE

    Landreth, Clifford J.; Corporon, Laura L.; Wilhelm, Richard H.

    2005-01-01

    The purpose of this MBA project is to evaluate and assess the metrics, incentives and other terms and conditions of the Performance Based Logistics (PBL) contract between Naval Aviation Inventory Control Point (NAVICP) and Honeywell in support of FA-18/S-3/P-3/C-2 Auxiliary Power Unit (APU) to determine if the contractual terms and conditions established are effective in facilitating and encouraging the full potential of PBL savings and improved performance. PBL is an acquisition reform initi...

  10. Small, moveable nuclear power plant

    International Nuclear Information System (INIS)

    Most reliable projections indicate that by the year 2000 approximately 25% of the world's electrical energy and possibly 10% of its process heat for industry will be provided by nuclear power plants. Whilst much of this will come from large nuclear steam raising units-in excess of 900 M.W.(e)-an increasing proportion will be provided from small modular plant, designed for portabiity or mobility. The technical, environmental and economic parameters of such a plant which will usually be of a size around 600 M.W.(e) or less and which in general terms derives its basic design features from nuclear marine propulsion units is reviewed. If suitably standardised, such a nuclear plant, mounted on barges, installed in ships or even airlifted into difficult locations, could provide an attractive solution to the energy problems of developing countries or remote communities. Apart from electrical energy production, the units could operate in a duplex mode to supply steam for central heating, sea-water or bore water distillation or industrial process heat. (Author)

  11. Performance of a direct steam generation solar thermal power plant for electricity production as a function of the solar multiple

    OpenAIRE

    Montes Pita, María José; Abánades Velasco, Alberto; Martínez-Val Peñalosa, Jose Maria

    2009-01-01

    This paper describes the influence of the solar multiple on the annual performance of parabolic trough solar thermal power plants with direct steam generation (DSG). The reference system selected is a 50 M We DSG power plant, with thermal storage and auxiliary natural gas-fired boiler. It is considered that both systems are necessary for an optimum coupling to the electricity grid. Although thermal storage is an opening issue for DSG technology, it gives an additional degree of freedom for pl...

  12. Power plant intake entrainment analysis

    International Nuclear Information System (INIS)

    Power plant condenser cooling water intake entrainment of fish eggs and larvae is becoming an issue in evaluating environmental impacts around the plants. Methods are required to evaluate intake entrainment on different types of water bodies. Presented in this paper is a derivation of the basic relationships for evaluating entrainment from the standing crop of fish eggs and larvae for different regions of a water body, and evaluating the rate of entrainment from the standing crop. These relationships are coupled with a 3D hydrodynamic and transport model that provides the currents and flows required to complete the entrainment evaluation. Case examples are presented for a simple river system, and for the more complex Delaware River Estuary with multiple intakes. Example evaluations are made for individual intakes, and for the cumulative impacts of multiple intakes

  13. Determination of the emissions from an aircraft auxiliary power unit (APU) during the Alternative Aviation Fuel Experiment (AAFEX).

    Science.gov (United States)

    Kinsey, John S; Timko, Michael T; Herndon, Scott C; Wood, Ezra C; Yu, Zhenhong; Miake-Lye, Richard C; Lobo, Prem; Whitefield, Philip; Hagen, Donald; Wey, Changlie; Anderson, Bruce E; Beyersdorf, Andreas J; Hudgins, Charles H; Thornhill, K Lee; Winstead, Edward; Howard, Robert; Bulzan, Dan I; Tacina, Kathleen B; Knighton, W Berk

    2012-04-01

    The emissions from a Garrett-AiResearch (now Honeywell) Model GTCP85-98CK auxiliary power unit (APU) were determined as part of the National Aeronautics and Space Administration's (NASA's) Alternative Aviation Fuel Experiment (AAFEX) using both JP-8 and a coal-derived Fischer Tropsch fuel (FT-2). Measurements were conducted by multiple research organizations for sulfur dioxide (SO2, total hydrocarbons (THC), carbon monoxide (CO), carbon dioxide (CO2), nitrogen oxides (NOx), speciated gas-phase emissions, particulate matter (PM) mass and number, black carbon, and speciated PM. In addition, particle size distribution (PSD), number-based geometric mean particle diameter (GMD), and smoke number were also determined from the data collected. The results of the research showed PM mass emission indices (EIs) in the range of 20 to 700 mg/kg fuel and PM number EIs ranging from 0.5 x 10(15) to 5 x 10(15) particles/kg fuel depending on engine load and fuel type. In addition, significant reductions in both the SO2 and PM EIs were observed for the use of the FT fuel. These reductions were on the order of approximately 90% for SO2 and particle mass EIs and approximately 60% for the particle number EI, with similar decreases observed for black carbon. Also, the size of the particles generated by JP-8 combustion are noticeably larger than those emitted by the APU burning the FT fuel with the geometric mean diameters ranging from 20 to 50 nm depending on engine load and fuel type. Finally, both particle-bound sulfate and organics were reduced during FT-2 combustion. The PM sulfate was reduced by nearly 100% due to lack of sulfur in the fuel, with the PM organics reduced by a factor of approximately 5 as compared with JP-8. PMID:22616284

  14. System Study: Auxiliary Feedwater 1998–2013

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, John Alton [Idaho National Lab. (INL), Idaho Falls, ID (United States). Risk Assessment and Management Services Dept.

    2014-12-31

    This report presents an unreliability evaluation of the auxiliary feedwater (AFW) system at 69 U.S. commercial nuclear power plants. Demand, run hours, and failure data from fiscal year 1998 through 2013 for selected components were obtained from the Institute of Nuclear Power Operations (INPO) Consolidated Events Database (ICES). The unreliability results are trended for the most recent 10-year period while yearly estimates for system unreliability are provided for the entire active period. No statistically significant increasing or decreasing trends were identified in the AFW results.

  15. System Study: Auxiliary Feedwater 1998-2014

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, John Alton [Idaho National Lab. (INL), Idaho Falls, ID (United States). Risk Assessment and Management Services Dept.

    2015-12-01

    This report presents an unreliability evaluation of the auxiliary feedwater (AFW) system at 69 U.S. commercial nuclear power plants. Demand, run hours, and failure data from fiscal year 1998 through 2014 for selected components were obtained from the Institute of Nuclear Power Operations (INPO) Consolidated Events Database (ICES). The unreliability results are trended for the most recent 10 year period while yearly estimates for system unreliability are provided for the entire active period. No statistically significant increasing or decreasing trends were identified in the AFW results.

  16. Design of nuclear power plants

    International Nuclear Information System (INIS)

    The criteria of design and safety, applied internationally to systems and components of PWR type reactors, are described. The main criteria of the design analysed are: thermohydraulic optimization; optimized arrangement of buildings and components; low costs of energy generation; high level of standardization; application of specific safety criteria for nuclear power plants. The safety criteria aim to: assure the safe reactor shutdown; remove the residual heat and; avoid the release of radioactive elements for environment. Some exemples of safety criteria are given for Angra-2 and Angra-3 reactors. (M.C.K.)

  17. Nuclear power plant simulator software

    International Nuclear Information System (INIS)

    The development is described of software for the simulator of technological equipment of a WWER-440 nuclear power plant unit, using an SM 4-20 computer operating under DOS RV V2 and using a FORTRAN translator. An asynchronous interrupt system is used for kayboard control. All utilities for I/0 operations are written in the macroassembler. The basic concept of the software is shown schematically as are the relations between the program modules and the instructor and student environment. (J.B.). 1 fig

  18. Modelling of nuclear power plant decommissioning financing

    International Nuclear Information System (INIS)

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. (authors)

  19. The atlas of large photovoltaic power plants

    International Nuclear Information System (INIS)

    This document reports all the photovoltaic power plants whose installed power is over 1 MWc and that are operating in France or in project. 446 power plants have been reviewed and their cumulated power reaches 2822 MWc. For each plant the following information is listed: the name of the municipality, the operator, the power capacity, the manufacturer of the photovoltaic panels and the type of technology used, the type of installation (on the ground, on the roof, on the facade, as sun protection,...), the yearly power output (kWh), and the date of commissioning. This review shows that 86% of these plants are ground-based. (A.C.)

  20. Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

    2000-12-15

    The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

  1. Sabotage at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Purvis, James W.

    1999-07-21

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

  2. Sabotage at Nuclear Power Plants

    International Nuclear Information System (INIS)

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

  3. Determination of power and power descriptions at walking with auxiliary facilities of pushing (by sticks away from lower support

    Directory of Open Access Journals (Sweden)

    Adashevskiy V.M.

    2012-04-01

    Full Text Available A purpose of work is a design of motions in Nordic walking, and analysis of power and power descriptions of motion. The basic aspects of walking with sticks and their influence on quality of life of people of different age are considered. Directions of the use of physical exercises for the people of senior age are selected. Possibilities of the use of walking in the physical rehabilitation of patients and people with a hyposthenic health is shown. It is set that, walking extend the use of models of Nordic possibility of leadthrough of researches and theoretical ground for more deep study of features of such type of movements. It is marked that the model of motion is expedient to utillize in combination with cinegram walking and by the indexes of dynamometry. It is recommended at lowering to observe the rules of technique of motion and safety.

  4. Optimization of relay protection for a auxiliary power system%厂用电系统继电保护优化

    Institute of Scientific and Technical Information of China (English)

    李子峰

    2015-01-01

    基于对厂用电系统继电保护中存在的配置不完整、后备保护动作时间过长等问题的分析,提出了配置6 kV 母线专用主保护、在低压厂用电系统变压器高压侧增加限时电流速断保护装置、优化后备保护之间配合的方案,并以此对厂用电系统的继电保护配置进行了优化,以600 MW机组为例,进行了保护整定计算,结果表明,优化后的厂用电系统继电保护配置完整,保护范围合理,后备保护动作时间显著缩短。从而,提高了厂用电系统继电保护动作的快速性和厂用电系统运行安全性。%On the basis of analysis on some questions of relay protection in auxiliary power systems,like the imperfection in configuration and the actuation time is too long,a scheme was proposed for relay protection design,such as configuring a specialized main protection for 6 kV busbar,adding a time limited current fast-trip protection on the high-voltage side of low-voltage transformers in auxiliary power system,optimizing the cooperation of reserve protections and then designing the configuration of relay protection in auxiliary power system according to the optimizing rule.Taking a 600 MW unit as the example,settings calculation was carried out.The results proved that the configuration of relay protection in auxiliary power system is integrated perfectly due to the optimization,the coverage of protection is reasonable and the actuation time of reserve protection has been remarkably shortened.Thus,the actuation speed and security of the auxiliary power system are promoted.

  5. The Kralovopolska Strojirna engineering works, supplier of nuclear power plant equipment

    International Nuclear Information System (INIS)

    The Kralovopolska Strojirna has been supplying equipment for all Czech and Slovak nuclear power plants. The company supplies auxiliary equipment for the primary coolant circuit, active and passive safety systems, radioactive water purification systems, storage tanks, heat exchange equipment, some types of piping, mechanical filters, evaporators, calciners, and special cranes. Individual quality assurance programmes are applied to equipment which is relevant to nuclear safety, and in-service inspections are made. (M.D.). 2 figs

  6. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2007 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2007/01/01; Worldwide status of nuclear power plants (12/31/2007); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2007; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2007; Performance indicator of French PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2007; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2007; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2007; Long term shutdown units at 12/31/2007; COL (combined licences) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

  7. Profitability of small-scale power plants

    International Nuclear Information System (INIS)

    Several small-scale power plants have been constructed in Finland during the last few years. Fuel oil and natural gas has been used as a fuel in diesel plants, natural gas in gas-turbine plants, and peat and industrial waste wood in solid fuel fired plants. Larger towns have already acquired combined power and heat generation either in their own power plants or in cooperation with industry. A usual mean of cooperation has been buying of district heat from industrial back-pressure power plants. Numerous small district heat loads still rely on separate heat production. The cheap price of electric power, caused by the good water and nuclear power conditions and long-term delivery contracts, has rendered the construction of small-scale power plants. The fuel prices have been stable for the last few years. The most significant changes have been caused by changing of exchange rate of the Finnish mark and the fuel taxation. Two power plant are reviewed in detail: 6/17 MW peat fired steam power plant and 6/6 MW oil fueled diesel power plant. The electricity prices of these two have been compared with coal condensing power and the electricity tariffs. The price comparisons have been made using the present price level. Energia-Ekono has compiled a new simulation program ELMO, operating in PC-WINDOWS environment, for simulation of cogeneration

  8. steam power plants re powering with gas turbine review

    International Nuclear Information System (INIS)

    Re powering faith gas turbine means integration of new gas turbine in existing power plant. Such integration yield higher efficiencies lower operating and maintenance costs and reduction in pollution emission. This paper summarizes the results of a feasibility study that inquired the possibilities of such integration in Israel Electric Corporation - IEC's existing steam power plants (oil fired)

  9. Nuclear power plants and the environment

    International Nuclear Information System (INIS)

    The environmental impacts are compared of conventional coal-fired and oil-fired power plants and of nuclear power plants. The values are compared of SO2, NO2, ash and soot emmisions with 133Xe and 85Kr fission products release and the requirement for air for diluting these emissions in the atmosphere is assessed. Also compared are thermal pollution from an oil-fired power plant and from PWR and fast reactor power plants. The conclusion is arrived at that nuclear energy can solve the problem of increasing demand for electric and heat power while reducing negative environmental impacts. (O.K.)

  10. Thermal power plant design and operation

    CERN Document Server

    Sarkar, Dipak

    2015-01-01

    Thermal Power Plant: Design and Operation deals with various aspects of a thermal power plant, providing a new dimension to the subject, with focus on operating practices and troubleshooting, as well as technology and design. Its author has a 40-long association with thermal power plants in design as well as field engineering, sharing his experience with professional engineers under various training capacities, such as training programs for graduate engineers and operating personnel. Thermal Power Plant presents practical content on coal-, gas-, oil-, peat- and biomass-fueled thermal power

  11. Design of an Operator Support System for Online Maintenance at Nuclear Power Plant

    International Nuclear Information System (INIS)

    Online maintenance based on reliability centered management is very important for the safe and economic operation of Nuclear Power Plant (NPP). This paper presents an operator support system by which the operators can manage plant configuration and identify the weakness in plant operation effectively. The proposed operator support system is based on GO-FLOW which a success-oriented reliability analysis methodology and can be used for evaluating phased missions. In this paper, the design of the proposed operator support system is introduced through a case study of the Auxiliary Feed Water System (AFWS)

  12. A snubber removal program for ASME Class 1 piping of an operating nuclear power plant

    International Nuclear Information System (INIS)

    In the past few years, significant development has been made by regulatory bodies, national laboratories and industrial organizations in new criteria and methodologies. Specifically, the approval of PVRC damping, the availability of automated support optimization computer codes, and other technical relaxations on analysis methods have qualified piping systems with fewer snubbers than previously required with resulting benefits in plant maintenance, inspection and reliability. Taking advantage of these developments, the Maanshan Nuclear Power Plant engaged in a snubber reduction program on all of the ASME Class 1 auxiliary lines. The results of this snubber reduction program, which emphasized minimal interference with plant maintenance schedules and minimal hardware changes, are presented in this paper

  13. Design of an operator support system for online maintenance at nuclear power plant

    International Nuclear Information System (INIS)

    Online maintenance based on reliability centered management is pivotal for the safe and economical operation of Nuclear Power Plant (NPP). This paper presents an operator support system through which the operators can effectively manage plant configuration and identify the weaknesses in plant operation. The proposed operator support system is based on the GO-FLOW, which is a success-oriented availability analysis methodology and can be used for evaluating phased missions. In this paper, the design of the proposed operator support system is introduced through a case study of the Auxiliary Feed Water System (AFWS). (author)

  14. Electric power generation in large-scale power plants

    International Nuclear Information System (INIS)

    Future electric power consumption will be depending on the economic development of the Federal Republic of Germany. Thermal power plants are fueled with non-renewable energy sources, i.e. coal, petroleum, natural gas or nuclear power. It is therefore important to assess the global coverage of these energy sources and to take stock of the reserves of the Federal Republic of Germany. If the waste heat left from electric power generation was made use of in dual-purpose power plants total energy consumption could be considerably reduced. Large-scale power plants do have to face and cope with the lack of distribution networks to supply the consumer. (DG)

  15. Exergoeconomic Evaluation of a Modern Ultra-Supercritical Power Plant

    Directory of Open Access Journals (Sweden)

    Lingnan Wu

    2012-09-01

    Full Text Available In this paper, the exergoeconomic analysis was conducted to an existing ultra-supercritical coal-fired power plant in China to understand the cost-formation process, to evaluate the economic performance of each component and to find possible solutions for more cost-effective designs. The total revenue requirement (TRR and the specific exergy costing (SPECO methods were applied for economic analysis and exergy costing, respectively. Quantitative balances of exergy and exergetic costs as well as necessary auxiliary equations for both individual component and the overall system were established. The results show that the exergoeconomic factors of the furnace and heat exchangers at low temperature levels, including air preheater and low-pressure feedwater preheaters, are rather small; while those of other components are relatively large. Moving more heat absorption into furnace to use the effective radiation heat transfer, increasing the air preheating temperature and adding more low pressure feedwater preheaters can be promising solutions for future design.

  16. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

  17. Nuclear power plant control system

    International Nuclear Information System (INIS)

    Purpose: To effectively transfer the operation of a nuclear power plant including a bwr type reactor to single load operation in the station with no increase in the neutron flux and water level in the reactor by the combined use of recycle pump trip and feedwater pump trip. Method: Upon rapid load decrease in a turbine generator, at least one of usually operated feedwater pumps and a recycle pump are tripped and the starting for a stand-by feedwater pump is inhibited. This rapidly decreases the recycling flow rate to thereby lower the neutron flux before generation of pressure increase and also decreases the feedwater flow rate to thereby suppress the increase in the water level due to increase in voids, whereby the operation is smoothly transferred to the single load operation in the station. (Horiuchi, T.)

  18. A landscape simulation system for power plants

    International Nuclear Information System (INIS)

    As scenes of power plants give many influences to environments, the plants that harmonized with the environments are demanded. We developed a landscape simulation system for the plants by using computer graphics technologies. This system has functions to generate realistic images about plant buildings and environments. Since the system contains information of ridge lines in addition to usual terrain data, the terrain shapes are expressed more precisely. Because the system enables users to visualize plant construction plans, the advance evaluations of plant scenes become possible. We regard this system as useful for environmental assessment of power plants. (author)

  19. Financing of nuclear power plant using resources of power generation

    International Nuclear Information System (INIS)

    It is proved that during the lifetime of a power plant, financial resources are produced from depreciation and from the profit for the delivered electrical power in an amount allowing to meet the cost of construction, interests of credits, the corporation taxes, and the means usable by the utility for simple reproduction of the power plant, additional investment, or for the ultimate decommissioning of the nuclear power plant. The considerations are simplified to 1 MW of installed capacity of a WWER-440 nuclear power plant. The breakdown is shown of the profit and the depreciation over the power plant lifetime, the resources of regular payments of credit instalments for the construction and the method of its calculation, and the income for the state budget and for the utility during the plant liofetime. (J.B.). 5 tabs., 5 refs

  20. Simulators predict power plant operation

    Energy Technology Data Exchange (ETDEWEB)

    Peltier, R.

    2002-07-01

    Mix the complexity of a new construction or major retrofit project with today's 'do more with less', a pinch of 'personnel inexperience,' and a dash of 'unintended consequences', and you have got a recipe for insomnia. Advanced simulation tools, however, can help you wring out your design train your operators before the first wire is terminated and just may be get a good night's rest. The article describes several examples of uses of simulation tools. Esscor recently completed a simulation project for a major US utility exploring the potential for furnace/duct implosion that could result from adding higher volumetric flow induced-draft fans and selective catalytic reduction to a 650-MW coal-fired plant. CAF Electronics Inc. provided a full-scope simulator for Alstom's KA24-1 combined-cycle power plant in Paris, France. Computational fluid dynamics (CFD) tools are being used by the Gas Technology Institute to simulate the performance of the next generation of pulverized coal combustors. 5 figs.

  1. Economics of hybrid photovoltaic power plants

    Energy Technology Data Exchange (ETDEWEB)

    Breyer, Christian

    2012-08-16

    The global power supply stability is faced to several severe and fundamental threats, in particular steadily increasing power demand, diminishing and degrading fossil and nuclear energy resources, very harmful greenhouse gas emissions, significant energy injustice and a structurally misbalanced ecological footprint. Photovoltaic (PV) power systems are analysed in various aspects focusing on economic and technical considerations of supplemental and substitutional power supply to the constraint conventional power system. To infer the most relevant system approach for PV power plants several solar resources available for PV systems are compared. By combining the different solar resources and respective economics, two major PV systems are identified to be very competitive in almost all regions in the world. The experience curve concept is used as a key technique for the development of scenario assumptions on economic projections for the decade of the 2010s. Main drivers for cost reductions in PV systems are learning and production growth rate, thus several relevant aspects are discussed such as research and development investments, technical PV market potential, different PV technologies and the energetic sustainability of PV. Three major market segments for PV systems are identified: off-grid PV solutions, decentralised small scale on-grid PV systems (several kWp) and large scale PV power plants (tens of MWp). Mainly by application of 'grid-parity' and 'fuel-parity' concepts per country, local market and conventional power plant basis, the global economic market potential for all major PV system segments is derived. PV power plant hybridization potential of all relevant power technologies and the global power plant structure are analyzed regarding technical, economical and geographical feasibility. Key success criteria for hybrid PV power plants are discussed and comprehensively analysed for all adequate power plant technologies, i.e. oil, gas and

  2. Dynamic Frequency Response of Wind Power Plants

    DEFF Research Database (Denmark)

    Altin, Müfit

    method has less impact of the power system frequency compared to existing control concepts. Another advantage of the proposed inertial response control has the tuning methodology which can be utilized as a generic approach for any power system with high wind power penetration levels. Additionally, an...... maintain sustainable and reliable operation of the power system for these targets, transmission system operators (TSOs) have revised the grid code requirements. Also, the TSOs are planning the future development of the power system with various wind penetration scenarios to integrate more wind power...... according to their grid codes. In these scenarios particularly with high wind power penetration cases, conventional power plants (CPPs) such as old thermal power plants are planned to be replaced with wind power plants (WPPs). Consequently, the power system stability will be affected and the control...

  3. TOSHIBA CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

  4. Fusion power plant availability study

    International Nuclear Information System (INIS)

    The consideration of fusion as an alternative energy source will need to demonstrate that Fusion Power Plant (FPP) design, operating and maintenance characteristics meet the electrical market requirements forecast for the second half of this century. Until now, fusion has been developed in the framework of research and development programmes following natural technological trends. To bring a greater sense of realism to commercial viability and to guarantee that technology-driven fusion development responds to the demands of the market, a conceptual study of future commercial FPPs has been performed with a Power Plant Availability (PPA) study aimed at identifying the aspects affecting the availability and generating costs of FPPs. EFET, who has also been involved in the study, can visualise it from two different points of view; that of the industry (ANSALDO, IBERTEF, SIEMENS, NNC) and that of the utilities (BELGATOM, FRAMATOME, FORTUM). The work carried out covered the following points: socio-economic forecasting; safety and licensing; operation and maintenance; waste and decommissioning; availability and reliability. The following are the most relevant findings, conclusions and recommendations for all these aspects: Demonstrate definitively that the physical principles of nuclear fusion have been validated by means of experiments; Establish a European Industrial Group to support the demonstration phases; Create the financial and contracting framework required to construct these installations. Secure the necessary budgets for the European Union's 5th and 6th Research Programmes. Look for supplementary long term financing sources; The existing Regulatory Bodies should combine to form a single Working Group with responsibility for fusion reactor safety and licensing activities, working on the harmonisation of the regulatory processes, developing FPP safety criteria and guidelines and reviewing industry standards; To be competitive, FPPs should have high availability

  5. Cost analysis of a coal-fired power plant using the NPV method

    Science.gov (United States)

    Kumar, Ravinder; Sharma, Avdhesh Kr.; Tewari, P. C.

    2015-06-01

    The present study investigates the impact of various factors affecting coal-fired power plant economics of 210 MW subcritical unit situated in north India for electricity generation. In this paper, the cost data of various units of thermal power plant in terms of power output capacity have been fitted using power law with the help of the data collected from a literature search. To have a realistic estimate of primary components or equipment, it is necessary to include the latest cost of these components. The cost analysis of the plant was carried out on the basis of total capital investment, operating cost and revenue. The total capital investment includes the total direct plant cost and total indirect plant cost. Total direct plant cost involves the cost of equipment (i.e. boiler, steam turbine, condenser, generator and auxiliary equipment including condensate extraction pump, feed water pump, etc.) and other costs associated with piping, electrical, civil works, direct installation cost, auxiliary services, instrumentation and controls, and site preparation. The total indirect plant cost includes the cost of engineering and set-up. The net present value method was adopted for the present study. The work presented in this paper is an endeavour to study the influence of some of the important parameters on the lifetime costs of a coal-fired power plant. For this purpose, parametric study with and without escalation rates for a period of 35 years plant life was evaluated. The results predicted that plant life, interest rate and the escalation rate were observed to be very sensitive on plant economics in comparison to other factors under study.

  6. Applications of power from Temelin nuclear power plant

    International Nuclear Information System (INIS)

    The proceedings contain 10 papers of which 9 fall under the INIS scope. They all concern the intentions and possibilities of using heat from nuclear power plants, especially from the Temelin power plant. Waste heat will be used for district heating of adjacent conurbations and for agricultural purposes. Various projects are presented using heat from nuclear power plants, such as greenhouse heating, soil heating, cultivation of algae and fish in warmed-up water. The existing experience is described with the use of heat from the Bohunice nuclear power plant. (M.D.). 15 figs., 6 tabs., 17 refs

  7. World power plant industry in recession

    International Nuclear Information System (INIS)

    Two scenarios of power plant ordering required to meet demand in 2000, based on reasonable assumptions of demand growth, plant lifetimes, and construction lead times, are presented. They result in a high and low of 191 and 75GWe per annum respectively. The scenarios are broken down into regions; Europe, North America, Japan, and less developed countries. It is thought that nuclear power is unlikely to gain a substantial share of the total power plant market. (U.K.)

  8. Investigation toward laser driven IFE power plant

    International Nuclear Information System (INIS)

    Inertial fusion energy (IFE) is becoming feasible due to the increasing understanding of implosion physics. Reactor technology issues have begun to be developed. Based on the conceptual design of Laser Driven IFE Power Plant, the technical and physical issues have been examined. R and D on key issues that affect the feasibility of power plant have been proceeded taking into account the collaboration in the field of laser driver, fuel pellet, reaction chamber and system design. It is concluded that the technical feasibility of IFE power plant seems to be reasonably high. Coordination and collaboration scheme of reactor technology experts in Japan on Laser Driven IFE Power Plant is being proceeded. (author)

  9. Methodology for Scaling Fusion Power Plant Availability

    Energy Technology Data Exchange (ETDEWEB)

    Lester M. Waganer

    2011-01-04

    Normally in the U.S. fusion power plant conceptual design studies, the development of the plant availability and the plant capital and operating costs makes the implicit assumption that the plant is a 10th of a kind fusion power plant. This is in keeping with the DOE guidelines published in the 1970s, the PNL report1, "Fusion Reactor Design Studies - Standard Accounts for Cost Estimates. This assumption specifically defines the level of the industry and technology maturity and eliminates the need to define the necessary research and development efforts and costs to construct a one of a kind or the first of a kind power plant. It also assumes all the "teething" problems have been solved and the plant can operate in the manner intended. The plant availability analysis assumes all maintenance actions have been refined and optimized by the operation of the prior nine or so plants. The actions are defined to be as quick and efficient as possible. This study will present a methodology to enable estimation of the availability of the one of a kind (one OAK) plant or first of a kind (1st OAK) plant. To clarify, one of the OAK facilities might be the pilot plant or the demo plant that is prototypical of the next generation power plant, but it is not a full-scale fusion power plant with all fully validated "mature" subsystems. The first OAK facility is truly the first commercial plant of a common design that represents the next generation plant design. However, its subsystems, maintenance equipment and procedures will continue to be refined to achieve the goals for the 10th OAK power plant.

  10. Methodology for Scaling Fusion Power Plant Availability

    International Nuclear Information System (INIS)

    Normally in the U.S. fusion power plant conceptual design studies, the development of the plant availability and the plant capital and operating costs makes the implicit assumption that the plant is a 10th of a kind fusion power plant. This is in keeping with the DOE guidelines published in the 1970s, the PNL report1, 'Fusion Reactor Design Studies - Standard Accounts for Cost Estimates. This assumption specifically defines the level of the industry and technology maturity and eliminates the need to define the necessary research and development efforts and costs to construct a one of a kind or the first of a kind power plant. It also assumes all the 'teething' problems have been solved and the plant can operate in the manner intended. The plant availability analysis assumes all maintenance actions have been refined and optimized by the operation of the prior nine or so plants. The actions are defined to be as quick and efficient as possible. This study will present a methodology to enable estimation of the availability of the one of a kind (one OAK) plant or first of a kind (1st OAK) plant. To clarify, one of the OAK facilities might be the pilot plant or the demo plant that is prototypical of the next generation power plant, but it is not a full-scale fusion power plant with all fully validated 'mature' subsystems. The first OAK facility is truly the first commercial plant of a common design that represents the next generation plant design. However, its subsystems, maintenance equipment and procedures will continue to be refined to achieve the goals for the 10th OAK power plant.

  11. IAEA programme on water chemistry in nuclear power plants

    International Nuclear Information System (INIS)

    The paper reviews the past future efforts of the IAEA, directed to ensure optimal water chemistry regimes in nuclear power plants. Corrosion of structural materials resulting from the interaction of the coolant with the internal surfaces comprising the primary heat transfer and auxiliary circuits of water reactors, creates two main problems. The first is an operational problem resulting in an increase in the core pressure drop or overheating of the fuel elements induced by crud buildup on the fuel cladding. The second problem is related to occupational radiation exposures arising from contamination of out-of-flux surfaces by corrosion products activated in the reactor core. These are the problems of reliability and safety which together with economics could be considered as the 'three whales' of nuclear power. The main goals of international cooperation in reactor water chemistry are: (1) to create a balanced and well-grounded methodological basis for corresponding regulatory and engineering solutions on a national level and (2) to improve 'the models and predictive capability of specialists for conditions that are different from or perhaps just beyond the realm of experience'. Continuing efforts are required to guarantee the highest reliability and safety standards under favorable economic indices of nuclear power plants, and to obtain understanding of such significant potential for solving the remaining problems. (Nogami, K.)

  12. Review of emergency diesel generator performance at nuclear power plants

    International Nuclear Information System (INIS)

    This study was performed by BNL for the NRC's Vendor Program Branch, Office of Inspection and Enforcement, in order to evaluate recent Diesel Generator (DG) and DG vendor performance. All DG vendors were reviewed with the exception of Transamerica Delaval, Inc. (TDI), due to the emphasis already being given to TDI diesels. For the time period 1980 through 1983 inclusive, BNL reviewed and evaluated DG failure data, DG vendor inspection reports, the TDI lessons learned as they related to the other vendors, and pertinent studies that had previously been completed. BNL also contacted DG vendors currently in the business to determine their present and projected work scope. An overall conclusion is that non-TDI DG performance has been reasonably good. Considering the complexity of the DG, the overall number of failures is not excessively high in terms of failures per DG year when compared to other equipment in a power plant. Also, the DG reliability figures are generally good. Additionally, losses of offsite power have been decreasing. Hence, it is not felt that an immediate, intensive inspection program of all DGs is required. Nonetheless, important areas were identified for inspection followup at DG vendors, subvendors, and nuclear power plants. The most significant areas requiring followup are: auxiliary systems components, failure analyses and corrective actions, DG maintenance, DG design modifications, and spare parts

  13. Power source facility inside of nuclear power plant

    International Nuclear Information System (INIS)

    The present invention simplifies power source facilities inside of a nuclear power plant and enables to provide countermeasures for troubles and inspection of one main transformer during plant operation. Namely, power in the plant is supplied to bus in ordinary use from a main power generator by way of a directly-coupled transformer in the plant during plant operation. Simultaneously, the power inside of the plant is supplied to a bus in non-ordinary use by way of a first communication bus. In this case, an onload tap changer of the direct transformer in the plant controls the voltage on the secondary side of the directly-coupled transformer to a lower level. On the other hand, when a load switcher of the power generator is opened under a predetermined condition, and the main power generator is disconnected from the main transformer and the directly-coupled transformer in the plant, power inside of the plant is supplied to the bus in ordinary use from the secondary side of the main transformer. In this case, the onload tap changer of the main transformer controls the voltage of the secondary side of the main transformer to a higher level. (I.S.)

  14. Control of power plants and power systems. Proceedings

    International Nuclear Information System (INIS)

    The 88 papers in this volume constitute the proceedings of the International Federation of Automatic Control Symposium held in Mexico in 1995. The broad areas which they cover are: self tuning control; power plant operations; dynamic stability; fuzzy logic applications; power plants modelling; artificial intelligence applications; power plants simulation; voltage control; control of hydro electric units; state estimation; fault diagnosis and monitoring systems; system expansion and operation planning; security assessment; economic dispatch and optimal load flow; adaptive control; distribution; transient stability and preventive control; modelling and control of nuclear plant; knowledge data bases for automatic learning methods applied to power system dynamic security assessment; control of combined cycle units; power control centres. Separate abstracts have been prepared for the three papers relating to nuclear power plants. (UK)

  15. Control of renewable distributed power plants

    OpenAIRE

    Bullich Massagué, Eduard

    2015-01-01

    The main objective of this master thesis is to design a power plant controller for a photo- voltaic (PV) power plant. In a first stage, the current situation of the status of the electrical grid is analysed. The electrical network structure is moving from a conventional system (with centralized power generation, unidirectional power ows, easy control) to a smart grid system consisting on distributed generation, renewable energies, smart and complex control architecture and ...

  16. Future requirements for fossil power plants

    Directory of Open Access Journals (Sweden)

    Spliethoff H.

    2013-06-01

    Full Text Available The fast increasing installation of technologies to convert renewable energy into power influences the operation of conventional power plants. New requirements on the technology, on the operation and on the economic have to be considered for already running and future power plants. Currently, first experiences with such a production and market situation are available. Technologies are discussed to store power and to reduce CO2 emissions. New compensation models are necessary to enable economic operation of fossil power plants in base load. This article gives a short review about available technologies and future challenges.

  17. Proven approaches to emission control at 200 MW power plants

    International Nuclear Information System (INIS)

    Due to the tendency fir stricter norms for emission, Eastern European power plants have committed themselves to for low NOx modifications and flu gas desulphurization (FGD) plants for the existing boiler plants. Fortum Engineering has gained experience in low NOx and FGD retrofit projects in Finland, Poland and Czech Republic. The presentation concentrates in two projects: low NOx combustion modifications Jawornzno III Power Plant, Poland and FGD retrofit for Chvaletice Power Station, Czech Republic. The aim of the first contract is to keep NOx emissions of the boilers under 170 mg/MJ after the modification. The project has been successfully completed during the year 1995. Key technology is the application of the newest generation NR-LCC low NOx burners and over firing (OFA) system to the existing boilers with minimum modifications and the auxiliary equipment. As a result during the first half of a year of operation after take-over the NOx emission has been continuously between 120 and 150 mg/MJ and unburned carbon in fly ash has been under 5%. There has been no increased slagging in the furnace. The Chvaltice Power Station burning brown coal had big problems with sulphur oxides in the flue gases. The aim of the project in the station was to reduce SO2 emissions from 7000 mg/m3n. The project has been completed in 1998. Desulphurization in Chvaletice is performed by wet limestone-gypsum method. Flue gases outgoing from electrostatic precipitators are washed in spray absorbers by limestone slurry to remove gaseous sulphur dioxides in flue gases. The process is optimized to achieve the required 94% desulphurization. The aim to decrease SO2 emissions under 400 mg/m3n had been achieved

  18. Economy of small-scale power plants

    International Nuclear Information System (INIS)

    The basic requirement for profitable generation of power and heat is sufficient and even heat load. The investment required by a plant based on cogeneration is always higher than that of a plant producing only heat, and hence the full time operation of the plant should be ensured since the beginning of the plant operational age. The second requirement for profitable operation of a small-scale power plant is the homogenous heat and power consumption profiles. Because the plants always cause remarkable capital costs and other fixed costs it is important to make an economic survey of the costs before the decision making in the preliminary planning phase. The presentation gives a review of the factors effecting on the economy of small-scale power plant, the distribution of the costs, and the methods used for investigation of the economy are reviewed

  19. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Developmental trends on nuclear power plants in the world'. In this report, some data at the end of 1999 was made up on bases of answers on questionnaires from 72 electric companies in 31 nations and regions in the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; location of the plants; the plants in the world; and so forth. And, it also has some survey results on the 'Liberalization of electric power markets and nuclear power generation' such as some 70% of respondents in nuclear power for future option, gas-thermal power seen as power source with most to gain from liberalization, merits on nuclear power generation (environmental considerations and supply stability), most commonly voiced concern about new plant orders in poor economy, and so forth. (G.K.)

  20. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-12-31

    As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

  1. Safety analysis program for steam generators replacement and power uprate at Tihange 2 nuclear power plant

    International Nuclear Information System (INIS)

    The Belgian Tihange 2 nuclear power plant went into commercial operation in 1983 producing a thermal power of 2785 MW. Since the commissioning of the plant the steam generators U-tubes have been affected by primary stress corrosion cracking. In order to avoid further degradation of the performance and an increase in repair costs, Electrabel, the owner of the plant, decided in 1997 to replace the 3 steam generators. This decision was supported by the feasibility study performed by Tractebel Energy Engineering which demonstrated that an increase of 10% of the initial power together with a fuel cycle length of 18 months was achieved. Tractebel Energy Engineering was entrusted by Electrabel as the owner's engineer to manage the project. This paper presents the role of Tractebel Energy Engineering in this project and the safety analysis program necessary to justify the new operation point and the fuel cycle extension to 18 months re-analysis of FSAR chapter 15 accidents and verification of the capacity of the safety and auxiliary systems. The FSAR chapter 15 accidents were reanalyzed jointly by Framatome and Tractebel Energy Engineering while the systems verifications were carried out by Tractebel Energy Engineering. (author)

  2. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  3. Nuclear Power Plant Module, NPP-1: Nuclear Power Cost Analysis.

    Science.gov (United States)

    Whitelaw, Robert L.

    The purpose of the Nuclear Power Plant Modules, NPP-1, is to determine the total cost of electricity from a nuclear power plant in terms of all the components contributing to cost. The plan of analysis is in five parts: (1) general formulation of the cost equation; (2) capital cost and fixed charges thereon; (3) operational cost for labor,…

  4. Maintenance of nuclear power plant

    International Nuclear Information System (INIS)

    Maintenance action of nuclear power plant (NPP) was described. Maintenance of NPP aimed at assurance of required function of NPP's equipment so as to prevent release of radioactive materials into the environment as well as attainment of stable operation of NPP. Philosophy of NPP safety was based on defense-in-depth or multiple barriers requiring specified function for the equipment. Preventive maintenance was essential to NPP's equipment and the scope of maintenance was decided on priority with adequate method and frequency of inspection. Most inspection was conducted during periodic inspection at outage. Repair or improvement works were performed if needed. Periodic inspection period was very long and then capacity factor of NPP was low in Japan compared with foreign data although frequency of unscheduled shutdown was very low. Introduction of reability- centered maintenance was requested based on past experiences of overhaul inspection. Technical evaluation of aged NPP had been conducted on aging phenomena and promotion of advanced maintenance was more needed. (T. Tanaka)

  5. Citizens contra nuclear power plants

    International Nuclear Information System (INIS)

    Is Wyhl the beginning of a new citizens' movement against official policies concerning atomic energy or is it the end of citizens' initiatives of latter years. Did democracy pass its test in Wyhl, or was the state's authority undermined. The danger of atomic energy was not the only concern of the citizens of the Rhine valley who demonstrated against the planned nuclear power plant, but also the quality of industrial and energy planning in which the democratic foundations have to be safeguarded. In the meantime, the doubts increase that this source of energy is of a not dangerous nature, and the myth of supposedly cheap atomic energy has been scattered. The dangers in connection with waste transport and storage were made public beyond the boundaries of the places in question, in particular as a result of the demonstrations. The publication documents the course of the demonstration and the site occupation from the beginning of Febuary 1975 onwards. The occupation still continued when the booklet was published despite the decision of the Administrative Court in Freiburg at the end of March (prohibition of commencement of building until the verdict on the principal suit against the overall project has been reached, the final decision to be made by the Higher Administrative Court in Mannheim). The author aims at describing the new quality of citizens' commitments in this booklet. (orig./LN)

  6. Thermal power plant simulation and control

    CERN Document Server

    Flynn, Damian

    2013-01-01

    Contributors of world-class excellence are brought together in Thermal Power Plant Simulation and Control to illustrate how current areas of research can be applied to power plant operation, leading to enhanced unit performance, asset management andplant competitiveness through intelligent monitoring and control strategies.

  7. Quality assurance in nuclear power plant

    International Nuclear Information System (INIS)

    The factors related to the licensing procedures of a nuclear power plant (quality assurance and safety analysis) are presented and discussed. The consequences of inadequate attitudes towards these factors are shown and suggestions to assure the safety of nuclear power plants in Brazil are presented. (E.G.)

  8. Lessons learned from existing biomass power plants

    Energy Technology Data Exchange (ETDEWEB)

    Wiltsee, G.

    2000-02-24

    This report includes summary information on 20 biomass power plants, which represent some of the leaders in the industry. In each category an effort is made to identify plants that illustrate particular points. The project experiences described capture some important lessons learned that lead in the direction of an improved biomass power industry.

  9. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    In this popular scientific brochure a brief description of construction scheme of Bohunice Nuclear Power Plant is presented. Electricity generation in a nuclear power plant is described. Instrumentation and control system as well as nuclear safety principles applied on the NPP are presented

  10. Working in a virtual power plant

    International Nuclear Information System (INIS)

    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. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    In the third quarter of 1993, all of Finland's four nuclear power plant units were in power operation, with the exception of the annual maintenance outages of the Loviisa units. The load factor average of the plant units was 83.6 %. None of the events which occurred during this annual quarter had any bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

  12. Nuclear power plants for protecting the atmosphere

    International Nuclear Information System (INIS)

    Some figures are presented comparing date on the CO2 emission and oxygen consumption of nuclear, natural gas fired, advanced coal fired and oil fired power plants, for the same amounts of electricity generated. The data were deduced from the Paks Nuclear Power Plant, Hungary. (R.P.)

  13. Nuclear power plant risk management

    International Nuclear Information System (INIS)

    This book collects papers on nuclear plant risk management. Topics include: basic concepts in risk analysis and decision theory; establishing integrated plant models; core and containment response; and site modeling and consequences

  14. The operating staff of nuclear power plants

    International Nuclear Information System (INIS)

    The training of its staff is one of the pillars of the safe and economical operation of a power plant. This is why power plant owners began to systematically train their staff already in the 50s, and why they created central training facilities. Staff members who have undergone this training make an indispensable contribution to the acceptedly high safety and availability of German power plants. The substantial cost of creating training facilities and of schooling plant staff is considered to be an investment for the future. Low labour turnover permits careful observation and development of staff and leads to a high standard of knowledge and experience. (orig./HSCH)

  15. Super-simulator for nuclear power plant

    International Nuclear Information System (INIS)

    The super-simulator is a conceptual name for future innovative simulators of nuclear power plants which surpass, to a large extent, the capabilities and performances of existing nuclear power plant simulators for operator training, plant analyzers for engineering studies or computer codes for dynamics analysis. Such super-simulators will be realized by employing highly advanced methods of mathematical modeling of the physical chemical and other related processes in the nuclear power plants and innovative methods of numerical computation using rapidly evolving high performance computing systems. (author)

  16. Harmonics in a Wind Power Plant: Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Preciado, V.; Madrigal, M.; Muljadi, E.; Gevorgian, V.

    2015-04-02

    Wind power generation has been growing at a very fast pace for the past decade, and its influence and impact on the electric power grid is significant. As in a conventional power plant, a wind power plant (WPP) must ensure that the quality of the power being delivered to the grid is excellent. At the same time, the wind turbine should be able to operate immune to small disturbances coming from the grid. Harmonics are one of the more common power quality issues presented by large WPPs because of the high switching frequency of the power converters and the possible nonlinear behavior from electric machines (generator, transformer, reactors) within a power plant. This paper presents a summary of the most important issues related to harmonics in WPPs and discusses practical experiences with actual Type 1 and Type 3 wind turbines in two WPPs.

  17. Hybrid wind-power-distillation plant

    Directory of Open Access Journals (Sweden)

    Ninić Neven

    2012-01-01

    Full Text Available This paper reports and elaborates on the idea of a solar distiller and an offshore wind power plant operating together. The subject under discussion is a single-stage solar distillation plant with vaporization, using adiabatic expansion in the gravitational field inside a wind power plant supporting column. This scheme divides investment costs for electric power and distillate production. In the region of the Adriatic Sea, all electric power produced could be “converted” to hydrogen using less than 10% of the distillate produced.

  18. Human factors in nuclear power plant operations

    International Nuclear Information System (INIS)

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants

  19. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants. (orig.)

  20. Safety culture in nuclear power plants

    International Nuclear Information System (INIS)

    Experience shows that German nuclear power plants have always been operated reliably and safely. Over the years, the safety level in these plants has been raised considerably so that they can stand any comparison with other countries. This is confirmed by the two reports published by the Federal Ministry for the Environment on the nuclear safety convention. Behind this, there must obviously stand countless appropriate 'good practices' and a safety management system in nuclear power plants. (orig.)

  1. Linguistic control of a nuclear power plant

    International Nuclear Information System (INIS)

    A multivariable linguistic controller based on fuzzy set theory is discussed and its application to a pressurized water nuclear power plant control is illustrated by computer simulation. The nonlinear power plant simulation model has nine states, two control inputs, one disturbance input, and two outputs. Although relatively simple, the model captures the essential coupled nonlinear plant dynamics and is convenient to use for control system studies. The use of an adaptive version of the controller is also demonstrated by computer simulation

  2. Program increasing of nuclear power plant safeness

    International Nuclear Information System (INIS)

    The results achieved within the project of national task 'Program increasing of nuclear power plant safeness' are presented in the document. The project was aimed to extend and deepen activities relating to safety increase of nuclear power units WWER-440 which play significant part in electricity production in the Slovak Republic. The application of advanced foreign calculating programs and calculation of radionuclide spreading in environment and techniques will influence the increase of extent, quality and international acceptance of safety analysis of nuclear power plant blocks WWER-440 and the risk valuation from operating nuclear power plants. Methodic resources for coping in emergency situation in nuclear energetics will be used for support in decision making in real time during radiation emergency on nuclear plant, region and state level. A long-term strategy in dealing with burnt fuel and radioactive substance formatting during nuclear power plant liquidation particularly with waste which is un acceptable in regional dump, has developed into a theoretical and practical preparation of solvable group for operating the converting centre Bohunice and in inactivating the nuclear power plant A-1. The diagnostic activities in nuclear power plants in the Slovak Republic have been elaborated into a project of norm documents in accordance with international norms for diagnostic systems. Presentation of new technologies and materials for repairs and reconstructions of components and nuclear power plant knots qualify increase in their reliability, safety and life. New objective methods and criterions for valuation and monitoring of the residual life and safety of fixed nuclear power plants. Results of problem solving linked with connecting the blocks of nuclear power plants to frequency regulation in electric network in the Slovak Republic are also presented in the document

  3. Plant life management and maintenance technologies for nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power generation occupying an important position for energy source in Japan and supplying about one third of total electric power usage is now required for further upgrading of its economics under regulation relaxation of electric power business. And, under execution retardation of its new planning plant, it becomes important to operate the already established plants for longer term and to secure their stability. Therefore, technical development in response to the plant life elongation is promoted under cooperation of the Ministry of Economics and Industries, electric power companies, literate, and plant manufacturers. Under such conditions, the Hitachi, Ltd. has progressed some technical developments on check inspection, repairs and maintenance for succession of the already established nuclear power plants for longer term under securing of their safety and reliability. And in future, by proposing the check inspection and maintenance program combined with these technologies, it is planned to exert promotion of maintenance program with minimum total cost from a viewpoint of its plant life. Here were described on technologies exerted in the Hitachi, Ltd. such as construction of plant maintenance program in response to plant life elongation agreeing with actual condition of each plant, yearly change mechanism grasping, life evaluation on instruments and materials necessary for maintenance, adequate check inspection, repairs and exchange, and so forth. (G.K.)

  4. 辅助动力装置建模及数值仿真%Model and numerical simulation of auxiliary power unit

    Institute of Scientific and Technical Information of China (English)

    常博博; 苏三买; 刘铁庚; 刘美凤

    2011-01-01

    In order to supporting auxiliary power unit(APU) design,the widely used APU with load compressor in structure was discussed and modeled.Firstly,the structural characteristics and regulation law are introduced and then how the load compressor works on APU was analyzed.Finally the mathematic model of APU was established based on components.Take a kind of APU as the object for numerical simulation and then compare with the actual test data.The results show that the dynamic simulation error is less than 5%.The mathematic model of APU is suitable for engineering usage.%为辅助APU(auxiliary power unit)的研发,以目前广泛应用的带负载压气机结构APU为研究对象,进行建模分析与研究.首先介绍了APU结构特点与调节规律,然后分析了负载压气机对APU共同工作的影响,最后采用部件法建立了该类型APU数学模型并设计仿真软件.以某型APU为对象,数值仿真与实际试车数据比较,结果表明所采用的建模方法是正确的,计算误差小于5%,所建立的模型能够满足工程需求.

  5. Studying heat integration options for steam-gas power plants retrofitted with CO2 post-combustion capture

    International Nuclear Information System (INIS)

    Electricity generation from fossil fuels has become a focal point of energy and climate change policies due to its central role in modern economics and its leading contribution to greenhouse gas emissions. Carbon capture and sequestration (CCS) is regarded by the International Energy Agency as an essential part of the technology portfolio for carbon mitigation, as it can significantly reduce CO2 emissions while ensuring electricity generation from fossil fuel power plants. This paper studies the retrofit of natural gas combined cycles (NGCCs) with an amine-based post-combustion carbon capture system. NGCCs with differently rated capacities were analysed under the assumptions that the heat requirement of the capture system was provided via a steam extraction upstream of the low-pressure steam turbine or by an auxiliary unit that was able to reduce the power plant derating related to the energy needs of the CCS system. Different types of auxiliary units were investigated based on power plant size, including a gas turbine cogeneration plant and a supplementary firing unit or boiler fed by natural gas or biomass. Energy and economic analyses were performed in order to evaluate the impact of type and layout of retrofit option on energy, environmental and economic performance of NGCCs with the CCS system. - Highlights: • Steam-gas power plants with an amine-based CO2 capture unit are examined. • The study concerns three combined cycles with different capacity and plant layout. • Several options to fulfil the heat requirement of the CCS system are explored. • Steam extraction significantly reduces the capacity of steam-gas power plant. • An auxiliary combined heat and power unit allows to reduce power plant derating

  6. Nuclear power plant after Fukushima incident: Lessons from Japan to Thailand for choosing power plant options

    OpenAIRE

    Tatcha Sudtasan; Komsan Suriya

    2012-01-01

    This study evaluates four power plant options in Thailand to suggest whether the country should adopt nuclear power plants. It includes a scenario that nuclear power plants are forced to be shut because of natural disaster like what happened at Fukushima Daiishi nuclear power plant in Japan. The results found that, in terms of net present value both in duration of 30 and 50 years, nuclear power plants is the best choice under certainty of no severe natural disaster that would interrupt the op...

  7. Operating experience with nuclear power plants 2013

    International Nuclear Information System (INIS)

    The VGB Technical Committee 'Nuclear Plant Operation' has been exchanging operating experience about nuclear power plants for more than 30 years. Plant operators from several European countries are participating in the exchange. A report is given on the operating results achieved in 2013, events important to plant safety, special and relevant repair, and retrofit measures from Belgium, Germany, Finland, the Netherlands, Switzerland, and Spain. (orig.)

  8. Experience with drilling and blasting work during construction of Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    The results are discussed of four years of investigating the technical and economic parameters of drilling and blasting equipment employed on the building site of the Mochovce nuclear power plant. The technical and operating characteristics are given of tested breaking and drilling sets manufactured by various foreign companies. The final choice was based on output, hard currency prices, power demand, operating reliability and number of personnel required for operation. The optimal set consists of two Hausherr HBM 70 drilling systems (holes with a diameter of 130 to 150 mm) and two ROC 601-02 Atlas Copco machines (auxiliary work, breaking foundation holes for nuclear reactors). (J.C.)

  9. Reliability of emergency ac power systems at nuclear power plants

    International Nuclear Information System (INIS)

    Reliability of emergency onsite ac power systems at nuclear power plants has been questioned within the Nuclear Regulatory Commission (NRC) because of the number of diesel generator failures reported by nuclear plant licensees and the reactor core damage that could result from diesel failure during an emergency. This report contains the results of a reliability analysis of the onsite ac power system, and it uses the results of a separate analysis of offsite power systems to calculate the expected frequency of station blackout. Included is a design and operating experience review. Eighteen plants representative of typical onsite ac power systems and ten generic designs were selected to be modeled by fault trees. Operating experience data were collected from the NRC files and from nuclear plant licensee responses to a questionnaire sent out for this project

  10. Transient analysis models for nuclear power plants

    International Nuclear Information System (INIS)

    The modelling used for the simulation of the Angra-1 start-up reactor tests, using the RETRAN computer code is presented. Three tests are simulated: a)nuclear power plant trip from 100% of power; b)great power excursions tests and c)'load swing' tests.(E.G.)

  11. Economic evaluation of tokamak power plants

    International Nuclear Information System (INIS)

    This study reports the impact of plasma operating characteristics, engineering options, and technology on the capital cost trends of tokamak power plants. Tokamak power systems are compared to other advanced energy systems and found to be economically competitive. A three-phase strategy for demonstrating commercial feasibility of fusion power, based on a common-site multiple-unit concept, is presented

  12. Angra 1 nuclear power plant full scope simulator development project

    Energy Technology Data Exchange (ETDEWEB)

    Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da, E-mail: edsel@eletronuclear.gov.br, E-mail: lccast@eletronuclear.gov.br, E-mail: nilogar@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (SCO/ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Superintendencia de Coordenacao da Operacao; Zazo, Francisco Javier Lopez; Ruiz, Jose Antonio, E-mail: jlopez@tecnatom.es, E-mail: jaruiz@tecnatom.es [Tecnatom S.A., San Sebastian de los Reyes, Madrid (Spain)

    2015-07-01

    Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

  13. Angra 1 nuclear power plant full scope simulator development project

    International Nuclear Information System (INIS)

    Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

  14. Training program for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Nuclear power generation in Japan reached 24.7% of its electric power supply with its capacity and time availability factors of 76.2% and 77.1%, respectively (in the calendar year 1986 - as of December 31, 1986). One of the reasons for such high performance is attributable to high quality of operating and maintenance personnel in the nuclear power plants. Ministry of International Trade and Industry of the Japanese Government has an overall responsibility with relation to the safety regulations and supervises all scope of training, while the Thermal and Nuclear Power Engineering Society is authorized to conduct licensing activities to qualify the chief shift supervisor of nuclear power plant operation and individual utility companies are required to train their plant operating and maintenance personnel. General status of training for plant personnel is briefly described in this paper, touching the practical education and training systems of utility companies and operation and maintenance training facilities

  15. Biomass-fueled power plants in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Raiko, M. [IVO Power Engineering Ltd., Vantaa (Finland); Hulkkonen, S. [Imatran Voima Oy, Vantaa (Finland)

    1997-07-01

    Combined heat and power production (CHP) from biomass is a commercially viable alternative when district heat or process steam is needed in small towns or in a process industry. The high nominal investment cost of a small power plant that uses local biomass fuels is compensated by the revenues from the heat. The price of the district heat or the steam generated in the CHP-plant can be valued at the same price level as the heat from a mere steam boiler. Also, the price of heat produced by a small-generation-capacity plant is local and higher, whereas electricity has a more general market price. A typical small Finnish CHP-plant consists of a bubbling fluidized bed boiler and a simplified steam turbine cycle generating 4 to 10 MW of electricity and 10 to 30 MW of district heat or process steam. There are about 10 power plants of this type in commercial operation in Finland. As a whole, biomass, which is used in more than 200 plants, provides about 20% of the primary energy consumption in Finland. Roughly half of these produce only heat but the rest are combined heat and power plants. The majority of the plants is in pulp and paper industry applications. Imatran Voima Oy (IVO) is the biggest energy producer in Finland. IVO builds, owns and operates several biomass-fired power plants and carries out active R and D work to further develop the biomass-fueled small power plant. This paper discusses the experiences of the biomass-fueled power plants. (author)

  16. A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant

    International Nuclear Information System (INIS)

    On Tuesday the 25. of July 2006 at around 13:15, Forsmark-1 nuclear power plant experienced a loss of external power event, initiated by a short circuit in the offsite 400 kV switchyard. Due to voltage and frequency fluctuations that followed, together with additional component failures, two of the four auxiliary diesel generators did not start, causing loss of power in 2 of four redundant trains existing in the power plant. The loss of power in trains A,B resulted in reactor shutdown and abnormal intervention of safety systems. After 20 minutes, the water level inside the Reactor Pressure Vessel (RPV) decreased to 1,9 m above the reactor core, and the pressure inside the RPV decreased to 1,5 MPa. The aim of the present study is to evaluate the capabilities of U.S. NRC codes RELAP5 and MELCOR to simulate the Forsmark-1 event, and then to reconstruct the sequence of the event based on the known behavior of the plant systems, such as activation of depressurization valves. To examine the safety margin, it is of interest to address 'what if' questions related to this event, such as i) what if the operator would delay the recovery of the two failing diesel generators, and ii) what if all 4 diesel generators would fail. The results show that both RELAP5 and MELCOR codes are able to reproduce the system thermal-hydraulic behavior during such an event. The intervention of emergency cooling systems and effort of operators to start the remaining two auxiliary generators have prevented the core from becoming uncovered. The analysis also shows that even in case of failure of all 4 auxiliary generators, the timely action of the plan operator, as demonstrated in the action during the event, would prevent a core damage from occurring. (authors)

  17. The spherical tokamak fusion power plant

    International Nuclear Information System (INIS)

    The design of a 1GW(e) steady state fusion power plant, based on the spherical tokamak concept, has been further iterated towards a fully self-consistent solution taking account of plasma physics, engineering and neutronics constraints. In particular a plausible solution to exhaust handling is proposed and the steam cycle refined to further improve efficiency. The physics design takes full account of confinement, MHD stability and steady state current drive. It is proposed that such a design may offer a fusion power plant which is easy to maintain: an attractive feature for the power plants following ITER. (author)

  18. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost all the time in the first quarter of 1992. The load factor average was 99.8%. All events which are classified on the International Nuclear Event Scale were level 0/below scale on the Scale. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure, originating from the nuclear power plants, were detected in samples collected in the vicinity of the nuclear power plants

  19. Advantages of butterfly valves for power plants

    International Nuclear Information System (INIS)

    Butterfly valves are increasingly used in nuclear power plants. They are used in CANDU reactors for class 2 and 3 service, to provide emergency and tight shutoff valves for all inlets and outlets of heat exchangers and all calandria penetrations. Guidelines for meeting nuclear power plant valve specifications are set out in ASME Section 3, Nuclear Power Plant Components. Some details of materials of construction, type of actuator, etc., for various classes of nuclear service are tabulated in the present article. The 'fishtail' butterfly valve is an improved design with reduced drag, as is illustrated and explained. (N.D.H.)

  20. Nuclear power plants in Europe 1989

    International Nuclear Information System (INIS)

    The report covers the situation of the nuclear power plant industry in 18 European countries, seven belonging to the COMECON. There are at present 229 nuclear power plant units in operation, producing 168 087 MWe. Sixty-six units are under construction and will add a capacity of 62 355 MWe, and further planned 33 units are designed to supply 32 872 MWe. This results in a total of 328 nuclear power plant units with a capacity of 263 318 MWe. The number of units in operation in West European countries including Yugoslavia was 153 in April 1989, totalling a capacity of 122 809 MWe. (orig./UA)

  1. Conduit Dynamics in Herand Power Plant

    OpenAIRE

    Sletten, Siri Skyberg

    2015-01-01

    The aim of this master thesis was to conduct a stability analysis of Herand power plant. Herand is a hydropower plant under planning by Herand Kraft, and it is planned to have a generator of 27MVA. The size of the power plant puts it under the requirements in Norway stating that all generators above 10MVA must have frequency regulation and be able to operate in an isolated grid. This paper presents a conducted analysis of Herand that examines whether the plant will be able to meet these requi...

  2. Electromagnetic compatibility of nuclear power plants

    International Nuclear Information System (INIS)

    Lately, there has been a mounting concern about the electromagnetic compatibility of nuclear-power-plant systems mainly because of the effects due to the nuclear electromagnetic pulse, and also because of the introduction of more-sophisticated and, therefore, more-susceptible solid-state devices into the plants. Questions have been raised about the adequacy of solid-state-device protection against plant electromagnetic-interference sources and transients due to the nuclear electromagnetic pulse. In this paper, the author briefly reviews the environment, and the coupling, susceptibility, and vulnerability assessment issues of commercial nuclear power plants

  3. Power plant technology 2014. Strategies, systems engineering and operation

    International Nuclear Information System (INIS)

    The book on power plant technology 2014 (strategies, systems engineering and operation) covers the following issues: Climate, politics and economy; wind power; fossil-fuel power plants, flexible power plants - plant operation, flexible power plants- materials, materials for energy technology, fuel feed and incineration, modeling of the water-vapor-circuit, corrosion, deposits and cleaning, vapor turbines, GUD power plants, fluidized bed combustion, energetic biomass use, combined heat and power generation and decentralized units, storage facilities, emissions - mitigation and measuring techniques.

  4. Turbine generator and its auxiliaries

    International Nuclear Information System (INIS)

    The turbine generator and its auxiliary systems in Tarapur Atomic Power Station (TAPS) have been performing well and further their performance and availability has increased due to timely assessment of the problems anticipated in the systems by a close co-ordination among the concerned staff. Continued efforts are on for further improvements. (author)

  5. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Third Annual Technical Progress report summarizes the period from September 1991 to October 1992. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. His philosophy, is to improve public perception of the safety of nuclear power plants by incorporating a high degree of automation where a greatly simplified operator control console minimizes the possibility of human error in power plant operations. To achieve this goal, a hierarchically distributed control system with automated responses to plant upset conditions was pursued in this research. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 stem plant. Emphasized in this Third Annual Technical Progress Report is the continuing development of the in-plant intelligent control demonstration for the final project milestone and includes: simulation validation and the initial approach to experiment formulation

  6. Avoiding steam bubble collapse-induced water hammer in the auxiliary piping of steam power plants

    International Nuclear Information System (INIS)

    The mechanisms of steam bubble collapse-induced water hammer are identified for nominally horizontal or inclined pipes. On the basis of these observations, two methods of preventing steam bubble collapse-induced water hammer in nominally horizontal pipes are proposed. They are inclining them and injecting the water at a controlled rate at either the lowest point or injecting the water at several locations. The success of these methods is demonstrated for horizontal pipes and for pipes of other orientations. These ways of preventing steam bubble collapse-induced water hammer are then used to test filling strategies for ''L''-shaped pipes oriented in practically every way. Both methods are found to work though the application of multiple injection ports and has complications when applied to a complex piping system. The use of the recommended design guidelines for avoiding steam bubble collapse-induced water hammer is demonstrated in an example problem

  7. Experience with construction of auxiliary hot operations building in V-2 nuclear power plant

    International Nuclear Information System (INIS)

    The massive reinforced concrete structure has walls cladded with austenitic steel sheets, i.e., carbon steel sheets. The cladding was manufactured by a specialized centre in a fitters workshop. The elements are 1000 by 2O00 mm2 in size. The block building panels in the height of the room, i.e. 9.5O m, were made of a combination of corrosion proof and carbon elements. The IS-NOE Universal boarding system was used for the wall cladding. Traditional planking was used for spaces around the sealed doors. The IS-NOE Combi-70 system was used for the walls of the depositories of solid radioactive wastes. Metal blocks weighing 7,500 kg which form a self-supporting structure were assembled using the MB-80A tower crane and the Coles-100 mobile crane. (E.S.)

  8. Support on water chemistry and processes for nuclear power plant auxiliary systems

    International Nuclear Information System (INIS)

    In particular PHWRs have a system devoted to the purification and upgrading of the collected heavy water leaks. The purification train is fed with different degradation ratios (D2O/H2O), activities and impurities. The water is distilled in a packed bed column filled with a mesh type packing. The mesh wire is made of a bronze substrate covered by copper oxides whose current composition has been determined by Moessbauer spectroscopy. With the purpose of minimizing the column stack corrosion, the water is pre-treated in a train consisting of an activated charcoal bed-strong cationic-anionic resin and a final polishing mixed bed resin. Ionic chemicals like acetic acid (whose provenance is suspected to come from the air treatment/D2O recovery system where the regeneration is performed at high temperature) are detected by the conductivity and ion chromatography when they concentrate at the column bottom. Traces of oils are retained by the charcoal bed but some compounds extracted by the aqueous phase are suspected to be responsible for the resins fouling or precursors of potentially aggressive agents inside the distillation column. Those species have been detected and identified by gaseous chromatography-mass spectrometry (GC-MS). In the present work, the identification, evaluation of alternatives for the retention and results compared to the original products present in the water upgrading purification train have been summarized. (authors)

  9. Common cause evaluations in applied risk analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Qualitative and quantitative approaches were developed for the evaluation of common cause failures (CCFs) in nuclear power plants and were applied to the analysis of the auxiliary feedwater systems of several pressurized water reactors (PWRs). Key CCF variables were identified through a survey of experts in the field and a review of failure experience in operating PWRs. These variables were classified into categories of high, medium, and low defense against a CCF. Based on the results, a checklist was developed for analyzing CCFs of systems. Several known techniques for quantifying CCFs were also reviewed. The information provided valuable insights in the development of a new model for estimating CCF probabilities, which is an extension of and improvement over the Beta Factor method. As applied to the analysis of the PWR auxiliary feedwater systems, the method yielded much more realistic values than the original Beta Factor method for a one-out-of-three system

  10. Development of power generation and nuclear power plant siting

    International Nuclear Information System (INIS)

    An overview is presented of Czechoslovak WWER type nuclear power plants in operation, under construction and planned. Regional geological surveying is being performed for nuclear power plant siting, covering an area of about 100 to 200 km in radius, as well as engineering and geological surveying aimed at obtaining data on the bearing capacity and stability of the area, on the subsidence of foundation soil due to construction, on ground water level, etc. The basic engineering and geological properties of suitable nuclear power plant sites are listed. A description is given of the method of seismic subdivision of the site into micro-areas and of the system of automatic earthquake protection used for securing the seismic safety of the power plants. (E.J.). 3 refs

  11. Sustainability in Large Power Plants

    OpenAIRE

    Faria, Roberto Censi; Kniess, Cláudia Terezinha; Maccari, Emerson Antonio

    2012-01-01

    No business activity today can be implemented without take into account the aspects of sustainability. The concept of sustainable development that was born of the years 1970 and 1980 and was enshrined in the concept of the three pillars of John Elkington - economic, social and environmental issues, the "triple bottom line" is a constraint for all types of enterprises, especially for large hydropower plants. Large hydropower plants have been for a while the great enemy of development, because ...

  12. Robust Instrumentation[Water treatment for power plant]; Robust Instrumentering

    Energy Technology Data Exchange (ETDEWEB)

    Wik, Anders [Vattenfall Utveckling AB, Stockholm (Sweden)

    2003-08-01

    Cementa Slite Power Station is a heat recovery steam generator (HRSG) with moderate steam data; 3.0 MPa and 420 deg C. The heat is recovered from Cementa, a cement industry, without any usage of auxiliary fuel. The Power station commenced operation in 2001. The layout of the plant is unusual, there are no similar in Sweden and very few world-wide, so the operational experiences are limited. In connection with the commissioning of the power plant a R and D project was identified with the objective to minimise the manpower needed for chemistry management of the plant. The lean chemistry management is based on robust instrumentation and chemical-free water treatment plant. The concept with robust instrumentation consists of the following components; choice of on-line instrumentation with a minimum of O and M and a chemical-free water treatment. The parameters are specific conductivity, cation conductivity, oxygen and pH. In addition to that, two fairly new on-line instruments were included; corrosion monitors and differential pH calculated from specific and cation conductivity. The chemical-free water treatment plant consists of softening, reverse osmosis and electro-deionisation. The operational experience shows that the cycle chemistry is not within the guidelines due to major problems with the operation of the power plant. These problems have made it impossible to reach steady state and thereby not viable to fully verify and validate the concept with robust instrumentation. From readings on the panel of the online analysers some conclusions may be drawn, e.g. the differential pH measurements have fulfilled the expectations. The other on-line analysers have been working satisfactorily apart from contamination with turbine oil, which has been noticed at least twice. The corrosion monitors seem to be working but the lack of trend curves from the mainframe computer system makes it hard to draw any clear conclusions. The chemical-free water treatment has met all

  13. Environmental effects of electric power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ragozin, D.A.

    1989-04-01

    Argues that the increased concern about environmental damage that has appeared since the advent of reconstruction (perestroika) and other political reform in the USSR must not be allowed to stand in the way of economic development. Identifies an ecological extremism that resists development such as construction of power plants and electrification and that will result in a lowering of living standards. Dismisses idea that alternative power sources such as wind power and solar power are feasible on a large scale and claims that large-scale hydroelectric power plants are no more harmful to the environment than small-scale plants. Dismisses as scientifically unfounded the theories of several eminent scientists who have published works and made films on several environmental aspects including energy and environment in Siberia, claiming that they attack hydroelectric power while ignoring the air, water and ground pollution from coal fired plants such as the KATEhK Kansk Achinsk fuel and power complex and underestimating the difficulty in purifying gaseous emissions. Concludes that the primary subject of protection should be man's health and inheritance and the main way of achieving this aim is to intensify the construction of hydroelectric power plants that do not produce harmful emissions, do not affect the global climate, have an inexhaustible energy resource and will help preserve valuable resources such as coal, oil and gas.

  14. Power plant construction. Plan, build, repair

    International Nuclear Information System (INIS)

    Modern thermal power plants can now convert up to 90 % of the energy input into electricity. This increase in efficiency has been made possible through technological progress, but also through improvements in power plant construction. Despite a distinct rise in the proportion of renewable energies in electricity supplies, traditional power stations are still responsible for guaranteeing a large share of our energy supplies. Air pollution control, noise control, protection of natural waters and soils plus careful use of resources are the key themes in the design, construction and maintenance of power plants. Publishing house Ernst and Sohn provides competent, up-to-date information for civil and structural engineers entrusted with such challenging engineering tasks. The special issue ''Power Plant Construction'' brings together the appropriate articles from the journals ''Bautechnik'', ''Stahlbau'', ''Beton- und Stahlbetonbau'' and ''Geomechanics and Tunnelling''. The themes in this compendium cover a wide range of topics, including analysis and design of power plant installations, power station refurbishment and maintenance, special structures such as cooling towers, chimneys and boiler house frames plus the engineering aspects of coal-fired, nuclear and hydroelectric power stations. Reports on current products and projects complement the technical papers. (orig.)

  15. Availability Improvement of German Nuclear Power Plants

    International Nuclear Information System (INIS)

    High availability is important for the safety and economical performance of Nuclear Power Plants (NPP). The strategy for availability improvement in a typical German PWR shall be discussed here. Key parameters for strategy development are plant design, availability of safety systems, component reliability, preventive maintenance and outage organization. Plant design, availability of safety systems and component reliability are to a greater extent given parameters that can hardly be influenced after the construction of the plant. But they set the frame for maintenance and outage organisation which have shown to have a large influence on the availability of the plant. (author)

  16. Fault simulator trainer for nuclear power plants

    International Nuclear Information System (INIS)

    A new nuclear power plant control simulator, developed at Karlsruhe for training operators, is described, based on an office type minicomputer with visual displays representing the various relevant reactor parameters, commands, controls status and safety arrangements. (S.R.)

  17. EPA Facility Registry Service (FRS): Power Plants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains data on power plants, based on the Energy Information Administration's EIA-860 dataset and supplemented with data from EPA's Facility...

  18. Occupational exposure management at nuclear power plants

    International Nuclear Information System (INIS)

    The Information System on Occupational Exposure (ISOE), a joint initiative of the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA), has become a unique worldwide programme on the protection of workers in nuclear power plants, including a network for the exchange of experience in the area of occupational exposure management, and the world's largest database on occupational exposure from nuclear power plants. Each year, an international workshop or symposium offers a forum for radiation protection professionals from the nuclear industry, operating organisations and regulatory authorities to exchange information on practical experience with occupational radiation exposure issues in nuclear power plants. These proceedings include the presentations made at the Third ISOE European Workshop on Occupational Exposure Management at Nuclear Power Plants, held in April 2002 in Portoroz, Slovenia. (author)

  19. Industrial accidents in nuclear power plants

    International Nuclear Information System (INIS)

    In 12 nuclear power plants in the Federal Republic of Germany with a total of 3678 employees, 25 notifiable company personnel accidents and 46 notifiable outside personnel accidents were reported for an 18-month period. (orig./HP)

  20. Environmental hazards from nuclear power plants

    International Nuclear Information System (INIS)

    The article discusses the radiation exposure due to nuclear power stations in normal operation and after reactor incidents. Also mentioned is the radiation exposure to the emissions from fuel reprocessing plants and radioactive waste facilities. (RW/AK)

  1. Report concerning Zarnowiec nuclear power plant

    International Nuclear Information System (INIS)

    Report of the Team of the President of the National Atomic Energy Agency regarding Zarnowiec nuclear power plant contains the analysis of situation in Poland in June 1990, the assessment of public opinion, as well as the description of ecological, technical and economical problems. The team's conclusions are given together with the general conclusion to stop the construction of Zarnowiec nuclear power plant. 5 appendixes, 6 enclosures, 1 documents list, 1 tab. (A.S.)

  2. Training of nuclear power plant operating personnel

    International Nuclear Information System (INIS)

    Proceedings are presented containing 13 papers on the training of nuclear power plant personnel, especially personnel of WWER type plants. The questions are discussed such as care of personnel, the position of operators and maintenance workers, factors affecting their reliable work, the human factor in reliability and safety of big power facilities, the assurance of a standard system of operators' training with associated social and sociological aspects, the development of psychodiagnostic methodologies for testing and selecting workers for individual jobs. (B.S.)

  3. Nuclear power plants in Germany. Performance 2011

    International Nuclear Information System (INIS)

    The report on the performance nuclear power plants in Germany in 2011 includes the operational results, safety analyses, revisions, quality management, environmental management, status of radioactive waste management, and eventual programs (TACIS, WANO) for the nuclear power plants Biblis A, Biblis B, Brokdorf KBR, Brunsbuettel KKB, Emsland KKE, Grafenrheinfeld KKG, Grohnde KWG, Gundremmingen KRB B, Gundremmingen KRB C, Isa KK1, Isar KK2, Kruemmel KKK, Neckarwestheim GKN I, Neckarwestheim GKN II, Philippsburg KKP 1, Philippsburg KKP 2, and Unterweser KKU.

  4. Reducing imbalances with virtual power plant operation

    OpenAIRE

    Zapata Riveros, Juliana; D'HAESELEER, William; Vandewalle, Jeroen

    2013-01-01

    The penetration of a large amount of distributed generation technologies with intermittent output, such as photovoltaic installations and wind turbines, yields an important challenge to the electric grid. This work illustrates the case of a virtual power plant that consists of several Cogeneration devices (CHP) systems and photovoltaic (PV) installations. The virtual power plant (VPP) operator bids electricity to the day-ahead market using the forecast for solar irradiation. In real time,...

  5. Fire protection at nuclear power plants

    International Nuclear Information System (INIS)

    The guide presents specific requirements for the design and implementation of fire protection arrangements at nuclear power plants and for the documents relating to the fire protection that are to be submitted to STUK (Finnish Radiation and Nuclear Safety Authority). Inspections of the fire protection arrangements to be conducted by STUK during the construction and operation of the power plants are also described in this guide. The guide can also be followed at other nuclear facilities

  6. Academic training for nuclear power plant operators

    International Nuclear Information System (INIS)

    After having briefly outlined the importance of academic training of nuclear power plant operators and the objectives of such a training (quality, addressing industry needs), the author evokes the programs implemented at the Center for Nuclear Studies of the Memphis State university. He notices that an academic degree is necessary for the recognition of the operator's job as a professional, and that such a training program is useful to improve safety and reliability of nuclear power plants

  7. Sensor network for nuclear power plant

    International Nuclear Information System (INIS)

    This study proposes an innovative method for the monitoring the nuclear power plant. In this field, false detection of the trouble, both 'false negative' and 'false positive' will become a serious problem. In the other hand, since its complexity of nuclear power plant, simplicity of monitoring system is strongly required. Here, we propose new method of signal processing and data transmission to realize reliable monitoring system consisted of multiple nodes of sensors. (author)

  8. Quality assurance organization for nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides requirements, recommendations and illustrative examples for structuring, staffing and documenting the organizations that perform activities affecting quality of a nuclear power plant. It also provides guidance on control of organization interfaces, and establishment of lines for direction, communication and co-ordination. The provisions of this Guide are applicable to all organizations participating in any of the constituent areas of activities affecting quality of a nuclear power plant, such as design, manufacture, construction, commissioning and operation

  9. Exergy efficiency graphs for thermal power plants

    International Nuclear Information System (INIS)

    Despite the strong support for exergy in thermodynamics, the industry still relies on energy based power plant efficiencies. The paper exposes errors with energy based efficiencies and improves the graphical representation of plants efficiencies. Among others, energy efficiencies cannot recognised that Combined Heat and Power (CHP) plant may be less efficient than condensing plants or that fossil fuel based plants should always be more efficient than any biomass plants because irreversibilities from biomass spontaneous thermo-chemical reactions are much higher than with coal or natural gas. Profitability equations fail to distinguish the true technical efficiency so exergy must be used, if only to enhance power plants understanding. Two novel graphs are introduced. Graph #1 combines all in a single graph; total, electrical and thermal exergy efficiencies. Graph #2 splits thermal exergy efficiency into two components related to; plant thermal losses and useful heat output quality. Data from 24 existing and design plants is used to support the graphs. Graph #1 shows different rankings of efficiencies than what is typically understood by the industry. Graph #2 shows that achieving further higher thermal energy efficiency barely increases the total exergy efficiency. If possible, it is better to increase the useful heat output quality. - Highlights: • Paper identifies weaknesses of industrial approach for power plant efficiencies. • Two exergy efficiency graphs are introduced to improve graphical representation. • Graph 1 combines electrical, thermal and total exergy efficiencies. • Graph 2 splits thermal exergy efficiency into its energy efficiency and useful heat output quality. • Graphs use typical data from 24 power plants of various technologies and fuels

  10. Intelligent distributed control for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Klevans, E.H.; Edwards, R.M.; Ray, A.; Lee, K.Y.; Garcia, H.E.: Chavez, C.M.; Turso, J.A.; BenAbdennour, A.

    1991-01-01

    In September of 1989 work began on the DOE University Program grant DE-FG07-89ER12889. The grant provides support for a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Second Annual Technical Progress report covers the period from September 1990 to September 1991. It summarizes the second year accomplishments while the appendices provide detailed information presented at conference meetings. These are two primary goals of this research. The first is to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz, a project consultant during the first year of the project. This philosophy, as presented in the first annual technical progress report, is to improve public perception of the safety of nuclear power plants by incorporating a high degree automation where greatly simplified operator control console minimizes the possibility of human error in power plant operations. A hierarchically distributed control system with automated responses to plant upset conditions is the focus of our research to achieve this goal. The second goal is to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-II steam plant.

  11. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    In September of 1989 work began on the DOE University Program grant DE-FG07-89ER12889. The grant provides support for a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Second Annual Technical Progress report covers the period from September 1990 to September 1991. It summarizes the second year accomplishments while the appendices provide detailed information presented at conference meetings. These are two primary goals of this research. The first is to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz, a project consultant during the first year of the project. This philosophy, as presented in the first annual technical progress report, is to improve public perception of the safety of nuclear power plants by incorporating a high degree automation where greatly simplified operator control console minimizes the possibility of human error in power plant operations. A hierarchically distributed control system with automated responses to plant upset conditions is the focus of our research to achieve this goal. The second goal is to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-II steam plant

  12. Market Integration of Virtual Power Plants

    DEFF Research Database (Denmark)

    Petersen, Mette Kirschmeyer

    Global efforts to reduce emissions of carbon dioxide drives the introduction of renewable power production technologies into the existing power system. The real-time balance between production and consumption must, however, still be maintained at all times. Unfortunately, this is becoming...... increasingly challenging due to the intrinsic variability of production technologies such as photovoltaics and wind turbines. In a Smart Grid system the balancing task will therefore be handled by mobilizing flexibility on the consumption side. This Thesis assumes that the Smart Grid should be commercially...... based rather than funded by subsidies. Consequently the Smart Grid provides a business opportunity for so-called Virtual Power Plants. A Virtual Power Plant is an independent commercial operator, which provides Smart Grid capabilities to flexible consumers. This means that the Virtual Power Plant is the...

  13. Simulation model of a PWR power plant

    International Nuclear Information System (INIS)

    A simulation model of a hypothetical PWR power plant is described. A large number of disturbances and failures in plant function can be simulated. The model is written as seven modules to the modular simulation system for continuous processes DYSIM and serves also as a user example of this system. The model runs in Fortran 77 on the IBM-PC-AT. (author)

  14. OUT Success Stories: Solar Trough Power Plants

    Science.gov (United States)

    Jones, J.

    2000-08-01

    The Solar Electric Generating System (SEGS) plants use parabolic-trough solar collectors to capture the sun's energy and convert it to heat. The SEGS plants range in capacity from 13.8 to 80 MW, and they were constructed to meet Southern California Edison Company's periods of peak power demand.

  15. Parabolic Trough Organic Rankine Cycle Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Canada, S.; Cohen, G.; Cable, R.; Brosseau, D.; Price, H.

    2005-01-01

    Arizona Public Service (APS) is required to generate a portion of its electricity from solar resources in order to satisfy its obligation under the Arizona Environmental Portfolio Standard (EPS). In recent years, APS has installed and operates over 4.5 MWe of fixed, tracking, and concentrating photovoltaic systems to help meet the solar portion of this obligation and to develop an understanding of which solar technologies provide the best cost and performance to meet utility needs. During FY04, APS began construction of a 1-MWe parabolic trough concentrating solar power plant. This plant represents the first parabolic trough plant to begin construction since 1991. The plant will also be the first commercial deployment of the Solargenix parabolic trough collector technology developed under contract to the National Renewable Energy Laboratory (NREL). The plant will use an organic Rankine cycle (ORC) power plant, provided by Ormat. The ORC power plant is much simpler than a conventional steam Rankine cycle power plant and allows unattended operation of the facility.

  16. Operations quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    This standard covers the quality assurance of all activities concerned with the operation and maintenance of plant equipment and systems in CANDU-based nuclear power plants during the operations phase, the period between the completion of commissioning and the start of decommissioning

  17. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  18. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  19. An introductory course to power plant operations using a full-function power plant simulator

    International Nuclear Information System (INIS)

    A two-course sequence has been developed to provide a detailed introduction to power plant systems and a meaningful hands-on experience operating a full-function power plant simulator. The first time the course was taught, a Westinghouse facility was used as the reference plant. The course is now designed to use a General Electric boiling water reactor (BWR)/6 facility as the reference plant and has been taught twice using the Perry Nuclear Power Plant Simulator Facility. The overall objective of this course is to provide a vehicle for students to integrate their theoretical course work into a fundamental and practical understanding of the purpose, design, and operation of power plant instrumentation, electrical, hydraulic, pneumatic, and power generation systems. Students are required to be in at least their second year of a graduate program. Students at this level have had most of the course work necessary to perform the operations analyses expected of new nuclear plant engineers

  20. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, providing maintenance facilities and equipment, procuring stores and spare parts, selecting and training maintenance personnel, reviewing and controlling plant modifications arising from maintenance, and for generating, collecting and retaining maintenance records. Maintenance shall be subject to quality assurance in all aspects important to safety. Because quality assurance has been dealt with in detail in other Safety Guides, it is only included here in specific instances where emphasis is required. Maintenance is considered to include functional and performance testing of plant, surveillance and in-service inspection, where these are necessary either to support other maintenance activities or to ensure continuing capability of structures, systems and components important to safety to perform their intended functions

  1. Commissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The basic objective of commissioning programs is to demonstrate that systems will operate as designed. This involves testing under conditions which simulate normal, upset and accident conditions. Experience with commissioning of plants supports the current commissioning practices and suggests improvements that should be made

  2. Advanced nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Full text: Korea Hydro and Nuclear Power Co., Ltd (KHNP) is the largest power company among the six subsidiaries that separated from Korea Electric Power Corporation (KEPCO) in 2001, accounting for approximately 25% of electricity producing facilities, hydro and nuclear combined. KHNP operates 20 nuclear power plants in Kori, Yonggwang, Ulchin and Wolsong site and several hydroelectric power generation facilities, providing approximately 36% of the national power supply. As a major source of electricity generation in Korea, nuclear energy contributes greatly to the stability of national electricity supply and energy security. KHNP's commercial nuclear power plant operation, which started with Kori Unit 1 in 1978, has achieved an average capacity factor more than 90% since 2000 and a high record of 93.4% in 2008. Following the introduction of nuclear power plants in the 1970's, Korea accumulated its nuclear technology in the 1980's, developed OPR 1000(Optimized Power Reactor) and demonstrated advanced level of its nuclear technology capabilities in the 2000's by developing an advanced type reactor, APR 1400(Advanced Power Reactor) which is being constructed at Shin-Kori Unit 3 and 4 for the first time. By 2022, KHNP will construct additional 12 nuclear power plants in order to ensure a stable power supply according to the Government Plan of Long-Term Electricity supply and Demand. 4 units of OPR 1000 reactor model will be commissioned by 2013 and 8 units of APR 1400 are under construction and planned. At the end of 2022, the nuclear capacity will reach 33% share of total generation capacity in Korea and account for 48% of national power generation. (author)

  3. Estimation of environmental external costs between coal fired power plant and nuclear power plant

    International Nuclear Information System (INIS)

    First of all, this study evaluated the impacts on the health and the environment of air pollutants emitted from coal power plant and nuclear power pant, two major electric power generating options in Korea. Then, the environmental external costs of those two options were estimated by transforming the health and environment impact into monetary values. To do this, AIRPACTS and Impacts of Atmospheric Release model developed by IAEA were used. The environmental external cost of Samcheonpo coal power plant was estimated about 25 times as much as that of Younggwang nuclear power plant. This result implies that nuclear power plant is a clean technology compared with coal power plant. This study suggests that the external cost should be reflected in the electric system expansion plan in order to allocate energy resources efficiently and to reduce economic impact stemming from the environmental regulation emerged recently on a global level

  4. Questions and Answers About Nuclear Power Plants.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC.

    This pamphlet is designed to answer many of the questions that have arisen about nuclear power plants and the environment. It is organized into a question and answer format, with the questions taken from those most often asked by the public. Topics include regulation of nuclear power sources, potential dangers to people's health, whether nuclear…

  5. Selection procedures for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Selection procedures in reference to experience in staffing two Wisconsin Electric Power Company nuclear project offices and the Point Beach Nuclear Power Plant are discussed. Wisconsin Electric has had a great deal of experience in the application of psychological tests and evaluation procedures, and it was natural that a major consideration in staffing these facilities was the selection of testing procedures

  6. Informatization of Power Plant and Its Implementation

    Institute of Scientific and Technical Information of China (English)

    Zhang Zhenghai

    2006-01-01

    @@ This paper presents the working procedure of power generating enterprises and explains the framework of an e-power-plant and its information system, puts forward the guideline and the general goal of informatization construction while focusing on the construction goal in the applied system, the implementing strategy, the project management and organization.

  7. Harmonic Resonances in Wind Power Plants

    DEFF Research Database (Denmark)

    Fernandez, Francisco Daniel Freijedo; Chaudhary, Sanjay; Teodorescu, Remus;

    2015-01-01

    This work reviews the state-of-the-art in the field of harmonic resonance problems in Wind Power Plants (WPPs). Firstly, a generic WPP is modeled according to the equivalent circuits of its passive and active components. Main focus is put on modeling active components, i.e. the ones based on power...

  8. Natural Circulation Performance in Nuclear Power Plants

    International Nuclear Information System (INIS)

    The present paper deals with a study of natural circulation in PWR systems, The study consists of two parts: in the first one, natural circulation in experimental facilities simulating PWR plants was analyzed. This made it possible to gather a broad data base which was assumed as a reference for the subsequent part of the research. Seven Nuclear Power Plants nodalizations and additional experimental data from ''non-PWR'' facilities have been considered in the second part of the paper. Conclusions are drawn about natural circulation capabilities derived for the seven Nuclear Power Plants nodalizations and from data base pertinent to three ''non-PWR'' facilities. (author)

  9. Natural circulation performance in nuclear power plants

    International Nuclear Information System (INIS)

    The present paper deals with a study of natural circulation in PWR systems. The study consists of two parts: in the first one, natural circulation in experimental facilities simulating PWR plants was analysed. This made it possible to gather a broad data base which was assumed as a reference for the subsequent part of the research. Seven Nuclear Power Plants nodalization and additional experimental data from 'non-PWR' facilities have been considered in the second part of the paper. Conclusions are drawn about natural circulation capabilities derived for the seven Nuclear Power Plants nodalization and from data base pertinent to three 'non-PWR' facilities. (author)

  10. Methods of assessing nuclear power plant risks

    International Nuclear Information System (INIS)

    The concept of safety evalution is based on safety criteria -standards or set qualitative values of parameters and indices used in designing nuclear power plants, incorporating demands on the quality of equipment and operation of the plant, its siting and technical means for achieving nuclear safety. The concepts are presented of basic and optimal risk values. Factors are summed up indispensable for the evaluation of the nuclear power plant risk and the present world trend of evaluation based on probability is discussed. (J.C.)

  11. Cooling water requirements and nuclear power plants

    International Nuclear Information System (INIS)

    Indian nuclear power programme is poised to scuttle the energy crisis of our time by proposing joint ventures for large power plants. Large fossil/nuclear power plants (NPPs) rely upon water for cooling and are therefore located near coastal areas. The amount of water a power station uses and consumes depends on the cooling technology used. Depending on the cooling technology utilized, per megawatt existing NPPs use and consume more water (by a factor of 1.25) than power stations using other fuel sources. In this context the distinction between 'use' and 'consume' of water is important. All power stations do consume some of the water they use; this is generally lost as evaporation. Cooling systems are basically of two types; Closed cycle and Once-through, of the two systems, the closed cycle uses about 2-3% of the water volumes used by the once-through system. Generally, water used for power plant cooling is chemically altered for purposes of extending the useful life of equipment and to ensure efficient operation. The used chemicals effluent will be added to the cooling water discharge. Thus water quality impacts on power plants vary significantly, from one electricity generating technology to another. In light of massive expansion of nuclear power programme there is a need to develop new ecofriendly cooling water technologies. Seawater cooling towers (SCT) could be a viable option for power plants. SCTs can be utilized with the proper selection of materials, coatings and can achieve long service life. Among the concerns raised about the development of a nuclear power industry, the amount of water consumed by nuclear power plants compared with other power stations is of relevance in light of the warming surface seawater temperatures. A 1000 MW power plant uses per day ∼800 ML/MW in once through cooling system; while SCT use 27 ML/MW. With the advent of new marine materials and concrete compositions SCT can be constructed for efficient operation. However, the

  12. Efficiency improvements for the coal-fired power plant retrofit with CO2 capture plant using chilled ammonia process

    International Nuclear Information System (INIS)

    Highlights: • NH3 has been proposed as a viable solvent to reduce the efficiency penalty. • Retrofit of a coal-fired power plant with a chilled ammonia process was analysed. • A base case scenario showed that efficiency penalty fell between 10.4% and 10.9%. • Alternative process configurations for the efficiency improvement were investigated. • The efficiency penalty was reduced to 8.7%. - Abstract: Development of clean coal technologies for power generation is crucial in meeting the European Union 2050 target to reduce greenhouse gas emissions. CO2 capture technology using chemical solvents currently has the highest potential to decarbonise coal-based power generation. Substitution of amine solvent with NH3 has been proposed as a viable option to reduce the efficiency penalty. In this study, the scenario of a supercritical coal-fired power plant retrofitted with a chilled ammonia process capture plant and CO2 compression unit was modelled in a common simulation environment. To fully assess the integration impact on power plant performance, the pressure loss due to steam extraction has been taken into account by using the Stodola ellipse law. Analysis of a basic integration scenario revealed that the efficiency penalty fell between 10.4% and 10.9% points depending on the stripper pressure. The quality of extracted steam became insufficient to meet the reboiler heat requirement above a stripper pressure of 21.8 bar, and the lowest efficiency penalty was obtained when reboiler condensate was returned to the deaerator in the power plant. In evaluating measures to improve integration, the efficiency penalty was reduced to 8.7–8.8% points through the integration of a single-stage or two-stage auxiliary steam turbine, respectively, and a back-pressure turbine. Nevertheless, the analysis has indicated that the net impact on power plant performance is similar to that of an amine-based post-combustion CO2 capture plant

  13. Safety Assessment - Swedish Nuclear Power Plants

    International Nuclear Information System (INIS)

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs

  14. Safety Assessment - Swedish Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kjellstroem, B. [Luleaa Univ. of Technology (Sweden)

    1996-12-31

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs.

  15. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    In the Quarterly Reports on the operation of the Finnish nuclear power plants such events and observations are described relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The report also includes a summary of the radiation safety of the plants' workers and the environment, as well as tabulated data on the production and load factors of the plants. The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in commercial operation during the whole first quarter of 1991. The load factor average was 99.1 %. Failures have been detected in the uppermost spacing lattices of nuclear fuel bundles removed from the Loviisa nuclear reactors. Further investigations into the significance of the failures have been initiated. In this quarter, renewed cooling systems for the instrumentation area were introduced at Loviisa 1. The modifications made in the systems serve to ensure reliable cooling of the area even during the hottest summer months when the possibility exists that the temperature of the automation equipment could rise too high causing malfunctions which could endanger plant safety. Occupational radiation doses and external releases of radioactivity were below prescribed limits in this quarter. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  16. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear safety and radiation protection which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing modifications at the nuclear power plants and issues relating to the use of nuclear energy which are of general interest are also reported. The reports include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the first quarter of 1993, a primary feedwater system pipe break occurred at Loviisa 2, in a section of piping after a feedwater pump. The break was erosion-corrosion induced. Repairs and inspections interrupted power generation for seven days. On the International Nuclear Event Scale the event is classified as a level 2 incident. Other events in the first quarter of 1993 had no bearing on nuclear safety and radiation protection

  17. Population distribution around Bushehr nuclear power plant

    International Nuclear Information System (INIS)

    Population distribution around the nuclear power plant is one of the most important factors to be considered. For the Bushehr nuclear power plant, information on current population distribution in the external zone up to a 80 kilometer radius in the vicinity of the site is collected. Also a projection of population for the plant lifetime has been made. Finally, the collected data was classified according to the age and sex. For this purpose, the area around the power plant was divided into concentric rings, and the rings were divided into 16 sectors. The population from 366 villages and 5 towns are about 328,000 inhabitants. In this survey, the population for 1985 was prepared on the basis of the 1977 census, and the results are indicated on the figures and tables. The above information will be used in evaluation of the potential radiological impact of normal and accidental releases, planning of emergency measures, and calculation of individual and collective doses

  18. Construction plan of Sendai Nuclear Power Plant

    International Nuclear Information System (INIS)

    In the Sendai nuclear power station, the construction of Unit 1 was started in January, 1979, to start the operation from July, 1984, and that of Unit 2 in May, 1981, to start the operation from March, 1986. Both plants are of PWR type, each with 890 MWe. In the design of the PWR plant, the national improved standard PWR model, as well as the experiences with existing LWR plants are fully incorporated. The purpose is to raise the reliability and safety, to improve the operation and maintenance and to reduce personnel radiation exposure. First, the siting and construction process of the nuclear power station is explained. Then, the features of the reactor power plants are described as follows: aseismic design, condensers, turbines, steam generators, reactor protection, reactor vessels, etc. (J.P.N.)

  19. Th-100 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Steenkampskraal Thorium Limited (STL) is a private company which is designing, marketing, licensing and commercializing a 100MWt thorium fueled pebble bed reactor. The concept plant design has been completed and work on the basic design has started. First site to determine the fuel cycle employed. Strong emphasis is placed on modular construction to reduce costs. STL hopes to start the licensing process within the next 6-8 months

  20. Nuclear power plants: safety management, safety culture

    International Nuclear Information System (INIS)

    The meeting on Nuclear Power Plants: Safety Management, Safety Culture held in Munich on October 30-31, 2002 has made very important contributions to the exchange of ideas and to the analysis of the current situation with respect to this topic. Eighteen technical papers were presented in which the subject was treated and put up for discussion under a variety of aspects raised by nuclear power plant operators, regulatory authorities, expert consultants, experts, scientists, and consultants. The findings elaborated at the event will greatly help to strengthen safety further in electricity generation from nuclear power at its current high level. (orig.)

  1. Market integration of Virtual Power Plants

    DEFF Research Database (Denmark)

    Petersen, Mette Kirschmeyer; Hansen, Lars Henrik; Bendtsen, Jan Dimon;

    2013-01-01

    We consider a direct control Virtual Power Plant, which is given the task of maximizing the profit of a portfolio of flexible consumers by trading flexibility in Energy Markets. Spot price optimization has been quite intensively researched in Smart Grid literature lately. In this work, however, we...... develop a three stage market model, which includes Day-Ahead (Spot), Intra-Day and Regulating Power Markets. This allows us to test the hypothesis that the Virtual Power Plant can generate additional profit by trading across several markets. We find that even though profits do increase as more markets are...

  2. Safety principles for nuclear power plants

    International Nuclear Information System (INIS)

    The role and purpose of safety principles for nuclear power plants are discussed. A brief information is presented on safety objectives as given in the INSAG documents. The possible linkage is discussed between the two mentioned elements of nuclear safety and safety culture. Safety culture is a rather new concept and there is more than one interpretation of the definition given by INSAG. The defence in depth is defined by INSAG as a fundamental principle of safety technology of nuclear power. Discussed is the overall strategy for safety measures, and features of nuclear power plants provided by the defence-in-depth concept. (Z.S.) 7 refs

  3. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Joaquim F. de [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)], E-mail: jfdc35@uol.com.br; Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)], E-mail: illsauer@iee.usp.br

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority.

  4. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    De Carvalho, Joaquim F. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)]|[Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority. (author)

  5. Integration of torrefaction with steam power plant

    Energy Technology Data Exchange (ETDEWEB)

    Zakri, B.; Saari, J.; Sermyagina, E.; Vakkilainen, E.

    2013-09-01

    Torrefaction is one of the pretreatment technologies to enhance the fuel characteristics of biomass. The efficient and continuous operation of a torrefaction reactor, in the commercial scale, demands a secure biomass supply, in addition to adequate source of heat. Biorefinery plants or biomass-fuelled steam power plants have the potential to integrate with the torrefaction reactor to exchange heat and mass, using available infrastructure and energy sources. The technical feasibility of this integration is examined in this study. A new model for the torrefaction process is introduced and verified by the available experimental data. The torrefaction model is then integrated in different steam power plants to simulate possible mass and energy exchange between the reactor and the plants. The performance of the integrated plant is investigated for different configurations and the results are compared. (orig.)

  6. Monitoring Biological Activity at Geothermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Peter Pryfogle

    2005-09-01

    The economic impact of microbial growth in geothermal power plants has been estimated to be as high as $500,000 annually for a 100 MWe plant. Many methods are available to monitor biological activity at these facilities; however, very few plants have any on-line monitoring program in place. Metal coupon, selective culturing (MPN), total organic carbon (TOC), adenosine triphosphate (ATP), respirometry, phospholipid fatty acid (PLFA), and denaturing gradient gel electrophoresis (DGGE) characterizations have been conducted using water samples collected from geothermal plants located in California and Utah. In addition, the on-line performance of a commercial electrochemical monitor, the BIoGEORGE?, has been evaluated during extended deployments at geothermal facilities. This report provides a review of these techniques, presents data on their application from laboratory and field studies, and discusses their value in characterizing and monitoring biological activities at geothermal power plants.

  7. Performance analysis of OTEC power plant

    International Nuclear Information System (INIS)

    The energy is the basis for almost all industrial activities and domestic needs. But recently there are increasing concerns internationally over environmental problems and consequent climate changes caused by the excessive use of fossil fuels. Furthermore the price of crude oil is increasing steadily with unstable supplies. In order to solve these national energy problems, the utilization of ocean energy is introduced as one of the best alternative technologies for the future. OTEC power plant has been installed at the west Inchon power plant site. Temperature differences of 20∼25 deg. C have been utilized for plant operations, where R22 is used as a working fluid. The system is composed of low pressure turbine, plate type heat exchanger, and pumps. In the present investigation the experimental results, such as gross power, net power and objective function, are analysed when temperature differences change from the reference design point

  8. Decentralised electrical distribution network in power plants

    International Nuclear Information System (INIS)

    A centralised network is a dominating network solution in today's power plants. In this study a centralised and a decentralised network were designed in order to compare them economically and technically. The emphasis of this study was on economical aspects, but also the most important technical aspects were included. The decentralised network requires less space and less cabling since there is no switchgear building and distribution transformers are placed close to the consumption in the field of a power plant. MV-motors and distribution transformers build up a ring. Less cabling and an absent switchgear building cause considerable savings. Component costs of both of the networks were estimated by using data from fulfilled power plant projects and turned out to be smaller for the decentralised network. Simulations for the decentralised network were done in order to find a way to carry out earth fault protection and location. It was found out that in high resistance earthed system the fault distance can be estimated by a relatively simple method. The decentralised network uses a field bus, which offers many new features to the automation system of a power plant. Diversified information can be collected from the protection devices in order to schedule only the needed maintenance duties at the right time. Through the field bus it is also possible to control remotely a power plant. The decentralised network is built up from ready-to-install modules. These modules are tested by the module manufacturer decreasing the need for field testing dramatically. The work contribution needed in the electrification and the management of a power plant project reduces also due the modules. During the lifetime of a power plant, maintenance is easier and more economical. (orig.)

  9. Intelligent operation system for nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power plants consist of many systems and are operated by skillful operators with plenty of knowledge and experience of nuclear plants. Recently, plant automation or computerized operator support systems have come to be utilized, but the synthetic judgment of plant operation and management remains as human roles. Toshiba is of the opinion that the activities (planning, operation and maintenance) should be integrated, and man-machine interface should be human-friendly. We have begun to develop the intelligent operation system aiming at reducing the operator's role within the fundamental judgment through the use of artificial intelligence. (author)

  10. Nuclear power plants in Europe 1990

    International Nuclear Information System (INIS)

    In 1989 the nuclear power plants in operation in the twelve countries of the European Community produced 589.8 TWh, which is 35.6% of the total net electricity generation of 1655.8 TWh. Of the European countries, France has the highest share of nuclear power in (net) electricity generation, i.e., 74.6% and 288.7 TWh. The nuclear power plants in Belgium produced 39 TWh, thus contributing 60.8% to the total net electricity generation. In the Federal Republic of Germany, the electricity generation in nuclear power plants rose by 2.8% in 1989 over the level of 1988, attaining 149.5 TWh, which marks roughly 39.5% of the public electricity supply. In Spain, nuclear power plants produced 56.1 TWh, which means a contribution of 38.4% to the total net electricity generation. In Hungary, 13.9 TWh were converted from nuclear power into electricity in 1989, thus achieving 47.5% of the total electricity generation in the country. In Britain, the share of nuclear power in the total net electricity generation was 63.4 TWh or 21.7%, in the Netherlands 3.8 TWh or 5.4%. (orig.)

  11. Software system for fuel management at Embalse nuclear power plant

    International Nuclear Information System (INIS)

    For accurate tracking of flux and power distribution in a CANDU reactor, the information needed is evaluated from a neutronic code calculation adjusted with experimental values, making use of in-core vanadium detectors at 102 locations together with auxiliary programs.The basic data that feed these programs come from the geometric and neutronic features and the actual instantaneous operating parameters. The system that provides all this information should be designed to meet with software quality assurance requirements. A software system was implemented at Embalse Nuclear Power Plant and it is in operation since 1998 after two year testing. This PC version replaced the former system introducing new concepts in its architecture. The neutronic code runs by procedures implemented in a language of macro instructions, so only new data are loaded for two consecutive instantaneous cases avoiding unnecessary data repetition. After each step, all results of neutronic calculation are stored in master files. Afterwards other auxiliary programs retrieve basic data for further evaluation and files are sorted in different thematic folders using a specific codification, for reevaluating further calculations over any specific case. The whole system can be installed in any PC. The package is provided with its general and particular support documentation and procedures for each program.The main purpose of the system is to track fuel and power distribution calculated after a certain period where fuelling operation were done in between. The main code, PUMA, evaluates in a 3-D, two-group scheme using finite difference diffusion theory. After neutronic calculation is performed, other programs allow to retrieve assorted information valid for fuel strategy and to build the fuelling operation list to be sent to the operation shifts. This program also permits to evaluate the accuracy of PUMA by doing comparisons with experimental values. Along with these features, some other system

  12. Direct FuelCell/Turbine Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hossein Ghezel-Ayagh

    2008-09-30

    This report summarizes the progress made in development of Direct FuelCell/Turbine (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T system employs an indirectly heated Turbine Generator to supplement fuel cell generated power. The concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, minimal emissions, reduced carbon dioxide release to the environment, simplicity in design, direct reforming internal to the fuel cell, and potential cost competitiveness with existing combined cycle power plants. Proof-of-concept tests using a sub-MW-class DFC/T power plant at FuelCell Energy's (FCE) Danbury facility were conducted to validate the feasibility of the concept and to measure its potential for electric power production. A 400 kW-class power plant test facility was designed and retrofitted to conduct the tests. The initial series of tests involved integration of a full-size (250 kW) Direct FuelCell stack with a 30 kW Capstone microturbine. The operational aspects of the hybrid system in relation to the integration of the microturbine with the fuel cell, process flow and thermal balances, and control strategies for power cycling of the system, were investigated. A subsequent series of tests included operation of the sub-MW Direct FuelCell/Turbine power plant with a Capstone C60 microturbine. The C60 microturbine extended the range of operation of the hybrid power plant to higher current densities (higher power) than achieved in initial tests using the 30kW microturbine. The proof-of-concept test results confirmed the stability and controllability of operating a fullsize (250 kW) fuel cell stack in combination with a microturbine. Thermal management of the system was confirmed and power plant operation, using the microturbine as the only source of fresh air supply

  13. Integrated approach to fire safety at the Krsko nuclear power plant - fire protection action plan

    International Nuclear Information System (INIS)

    Nuclear Power Plant Krsko (NPP Krsko) is a Westinghouse design, single-unit, 1882 Megawatt thermal (MWt), two-loop, pressurized water nuclear power plant. The fire protection program at NPP Krsko has been reviewed and reports issued recommending changes and modifications to the program, plant systems and structures. Three reports were issued, the NPP Krsko Fire Hazard Analysis (Safe Shout down Separation Analysis Report), the ICISA Analysis of Core Damage Frequency Due to Fire at the NPP Krsko and IPEEE (Individual Plant External Event Examination) related to fire risk. The Fire Hazard Analysis Report utilizes a compliance - based deterministic approach to identification of fire area hazards. This report focuses on strict compliance from the perspective of US Nuclear Regulatory Commission (USNRC), standards, guidelines and acceptance criteria and does not consider variations to comply with the intent of the regulations. The probabilistic analysis methide used in the ICISA and IPEEE report utilizes a risk based nad intent based approach in determining critical at-risk fire areas. NPP Krsko has already completed the following suggestions/recommendations from the above and OSART reports in order to comply with Appendix R: Installation of smoke detectors in the Control Room; Installation of Emergency Lighting in some plant areas and of Remote Shout down panels; Extension of Sound Power Communication System; Installation of Fire Annunciator Panel at the On-site Fire Brigade Station; Installation of Smoke Detection System in the (a) Main Control Room Panels, (b) Essential Service Water Building. (c) Component Cooling Building pump area, chiller area and HVAC area, (d) Auxiliary Building Safety pump rooms, (e) Fuel Handling room, (f) Intermediate Building AFFW area and compressor room, and (g) Tadwaste building; inclusion of Auxiliary operators in the Fire Brigade; training of Fire Brigade Members in Plant Operation (9 week course); Development of Fire Door Inspection and

  14. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    International Nuclear Information System (INIS)

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  15. The Oil-Fired MHD Power Plant

    International Nuclear Information System (INIS)

    It has been shown in an earlier paper what thermal efficiencies can be hoped for from a combined MHD-steam power station for different fuels, seeding, magnetic field strength, etc. However, a large pilot-plant is required to prove the intrinsic reliability of the MHD-power station, and also its probable competitiveness with a conventional power station. In this paper a possible pilot plant, a heavy-fuel-oil-fired MHD-steam power station is described. Residual fuel oil has been steadily increasing in significance in European power station practice over the past few decades. The MHD pilot plant must be as simple as possible in concept, so that the question of its reliability can be answered. The two essential unknowns are the designs of the MHD duct and the large superconducting magnets. Both preheating of the air above about 800°C and oxygen enrichment should be dispensed with for the time being. The combustion chamber should be constructed according to well-proved principles. It is proposed as well-that the seeding problem should be simply handled. In the example discussed, it seems possible that the specific plant costs of the whole power station will be kept to the level prevailing for steam power stations of the same output, while the thermal efficiency, after taking into account all the losses which can at the moment be assessed, is still 15% higher than that of the regular power station. If only the proposed pilot plant is considered, then the enormous development costs for the high temperature preheater and other costly items can be postponed until a later date, when the further development of the open cycle MHD-power station can be fully justified. (author)

  16. Measurement of vertical displacement of buildings in the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    The incorporation of the measurement of displacements of buildings in the construction documentation of the Mochovce nuclear power plant is dealt with. Each project design shows the points of ground control, the method of their stabilization, the intervals, accuracy and method of measurement, etc. Of great importance is the measurement of the turbine bearing frame, the turbine equipment, the main production units and the buildings of auxiliary operations handling radioactive material. The measured values of displacement were within the expected limits for all buildings. (E.J.)

  17. Nuclear power plant security assessment technical manual.

    Energy Technology Data Exchange (ETDEWEB)

    O' Connor, Sharon L.; Whitehead, Donnie Wayne; Potter, Claude S., III

    2007-09-01

    This report (Nuclear Power Plant Security Assessment Technical Manual) is a revision to NUREG/CR-1345 (Nuclear Power Plant Design Concepts for Sabotage Protection) that was published in January 1981. It provides conceptual and specific technical guidance for U.S. Nuclear Regulatory Commission nuclear power plant design certification and combined operating license applicants as they: (1) develop the layout of a facility (i.e., how buildings are arranged on the site property and how they are arranged internally) to enhance protection against sabotage and facilitate the use of physical security features; (2) design the physical protection system to be used at the facility; and (3) analyze the effectiveness of the PPS against the design basis threat. It should be used as a technical manual in conjunction with the 'Nuclear Power Plant Security Assessment Format and Content Guide'. The opportunity to optimize physical protection in the design of a nuclear power plant is obtained when an applicant utilizes both documents when performing a security assessment. This document provides a set of best practices that incorporates knowledge gained from more than 30 years of physical protection system design and evaluation activities at Sandia National Laboratories and insights derived from U.S. Nuclear Regulatory Commission technical staff into a manual that describes a development and analysis process of physical protection systems suitable for future nuclear power plants. In addition, selected security system technologies that may be used in a physical protection system are discussed. The scope of this document is limited to the identification of a set of best practices associated with the design and evaluation of physical security at future nuclear power plants in general. As such, it does not provide specific recommendations for the design and evaluation of physical security for any specific reactor design. These best practices should be applicable to the design and

  18. Nuclear power plant security assessment technical manual

    International Nuclear Information System (INIS)

    This report (Nuclear Power Plant Security Assessment Technical Manual) is a revision to NUREG/CR-1345 (Nuclear Power Plant Design Concepts for Sabotage Protection) that was published in January 1981. It provides conceptual and specific technical guidance for U.S. Nuclear Regulatory Commission nuclear power plant design certification and combined operating license applicants as they: (1) develop the layout of a facility (i.e., how buildings are arranged on the site property and how they are arranged internally) to enhance protection against sabotage and facilitate the use of physical security features; (2) design the physical protection system to be used at the facility; and (3) analyze the effectiveness of the PPS against the design basis threat. It should be used as a technical manual in conjunction with the 'Nuclear Power Plant Security Assessment Format and Content Guide'. The opportunity to optimize physical protection in the design of a nuclear power plant is obtained when an applicant utilizes both documents when performing a security assessment. This document provides a set of best practices that incorporates knowledge gained from more than 30 years of physical protection system design and evaluation activities at Sandia National Laboratories and insights derived from U.S. Nuclear Regulatory Commission technical staff into a manual that describes a development and analysis process of physical protection systems suitable for future nuclear power plants. In addition, selected security system technologies that may be used in a physical protection system are discussed. The scope of this document is limited to the identification of a set of best practices associated with the design and evaluation of physical security at future nuclear power plants in general. As such, it does not provide specific recommendations for the design and evaluation of physical security for any specific reactor design. These best practices should be applicable to the design and

  19. Scada Systems – Control, Supervision and Data Acquisition for the Power Plants Settled on a Stream (Part 2

    Directory of Open Access Journals (Sweden)

    Cosmin Ursoniu

    2015-09-01

    Full Text Available Scada (supervisory control and data acquisition is a complex system that supervises and controls an industrial process and performs several functions. A human machine interface will also be presented and how the process in a power plant is controlled and supervised through it by the operator. The main screen will be described (which is a global view of the hydro unit and what the operator can see and what he can press to control the power plants process also a few more screens will be presented for auxiliary installations and it will be described what the operator can see and what he can do to control the installation.

  20. Scada Systems – Control, Supervision and Data Acquisition for the Power Plants Settled on a Stream (Part 1

    Directory of Open Access Journals (Sweden)

    Cosmin Ursoniu

    2015-09-01

    Full Text Available Scada (supervisory control and data acquisition is a complex system that supervises and control an industrial process and performs several functions. A human machine interface will also be presented and how the process in a power plant is controlled and supervised through it by the operator. The main screen will be described (which is a global view of the hydro unit and what the operator can see and what he can press to control the power plants process also a few more screens will be presented for auxiliary installations and it will be described what the operator can see and what he can do to control the installation.

  1. 76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-01-10

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Cliffs Nuclear Power Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant... for light-water nuclear power reactors,'' which requires that the calculated emergency core...

  2. Water processing in power plants

    International Nuclear Information System (INIS)

    Surface water can be treated to a high degree of efficiency by means of new compact processes. The quantity of chemicals to be dosed can easily be adjusted to the raw water composition by intentional energy supply via agitators. In-line coagulations is a new filtration process for reducing organic substances as well as colloids present in surface water. The content of organic substances can be monitored by measuring the plugging index. Advanced ion-exchanger processes (fluidised-bed, compound fluidised-bed and continuously operating ion exchanger plants) allow the required quantity of chemicals as well as the plant's own water consumption to be reduced, thus minimising the adverse effect on the environment. The reverse-osmosis process is becoming more and more significant due to the low adverse effect on the environment and the given possibilities of automation. As not only ionogenic substances but also organic matter are removed by reverse osmosis, this process is particularly suited for treating surface water to be used as boiler feed water. The process of vacuum degassing has become significant for the cold removal of oxygen. (orig.)

  3. Periodic safety reviews of nuclear power plants

    International Nuclear Information System (INIS)

    Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

  4. Power plant perspectives for sugarcane mills

    International Nuclear Information System (INIS)

    Biomass, integral to life, is one of the main energy sources that modern technologies could widely develop, overcoming inefficient and pollutant uses. The sugarcane bagasse is one of the more abundant biomass. Moreover, the fluctuating sugar and energy prices force the sugarcane companies to implement improved power plants. Thanks to a multiyear collaboration between University of Rome and University of Piura and Chiclayo, this paper investigates, starting from the real data of an old sugarcane plant, the energy efficiency of the plant. Furthermore, it explores possible improvements as higher temperature and pressure Rankine cycles and innovative configurations based on gasifier plus hot gas conditioning and gas turbine or molten carbonate fuel cells. Even if the process of sugar extraction from sugarcane and the relative Rankine cycles power plants are well documented in literature, this paper shows that innovative power plant configurations can increase the bagasse-based cogeneration potential. Sugarcane companies can become electricity producers, having convenience in the use of sugarcane leaves and trash (when it is feasible). The worldwide implementation of advanced power plants, answering to a market competition, will improve significantly the renewable electricity produced, reducing CO2 emissions, and increasing economic and social benefits.

  5. A BWR power plant simulator for Barsebaeck

    International Nuclear Information System (INIS)

    A computer simulator of a Barsebaeck power plant unit has been developed in cooperation between Sydkraft AB, Lund Institute of Technology, and Risoe National Laboratory. The simulator is of the kind often referred to as a compact simulator, because it involves only a computer with display screens and other input/output devices plus the software needed for calculation and presentation of the plant state as a function of time, and no sort of model of the control room as in large reactor simulators for operator training. The purpose of training courses with the compact simulator is to give students a better understanding of the behaviour of the power plant under transient conditions by displaying variables, e.g. pressures, temperatures, reactivity, nuclear power, as functions of time, thereby showing the interactions between different parts of the plant during the transient and the influence of a number of possible operator actions. The present paper describes the Barsebaeck compact simulator with the emphasis on the software developed at Risoe National Laboratory. The Risoe work comprises the programming of the dynamic plant model, in the form of a number of Fortran subroutines containing the physical description of the power plant. (author)

  6. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  7. Nuclear Security for Floating Nuclear Power Plants

    International Nuclear Information System (INIS)

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  8. Nuclear power plants 1985 - a world survey

    International Nuclear Information System (INIS)

    The Quick Statistics annually compiled by atw lists 355 nuclear power plants with 263,027 gross MWe in operation in 26 countries in late 1985. Another 163 units with 157801 MWe were under construction in 25 countries, and 75 units with 77,328 MWe were ordered in 18 countries. This adds up to a total of 593 units with an aggregate 498,156 MWe. In the course of 1985 30 nuclear generating units with 28,375 MWe were newly commissioned in 17 countries and 33 units in 14 countries started commercial operation. In the survey of electricity generation in 1985 for which no information was made available from the Eastern block countries, a total of 289 nuclear power plants were covered. In the year under review they generated an aggregate 1,270,854 GWh, which is 18.4% less than in the previous year. The highest nuclear generation again was recorded in the USA with 404,515 GWh, followed by France with 24,644 GWh. The KWG Grohnde Nuclear Power Station in the Federal Republic of Germany attained the maximum annual production figure of 1,477 GWh. The survey includes 10 tables indicating the generating performance of each nuclear power plant, the development of electricity generation in nuclear plants, and status of, nuclear power plants at the end of 1985 arranged by countries, types of reactors, and reactor manufacturers. (orig.)

  9. Nuclear power plants 1995 - a world survey

    International Nuclear Information System (INIS)

    The atw Statistics Report compiled by atw lists 428 nuclear power plants with 363 397 gross MWe in operation in 30 countries in late 1995. Another 62 units with 55 180 gross MWe were under construction in 18 countries. This adds up to a total of 490 units with an aggregate 418 577 MWe. In the course of 1995 four units in four countries started commercial operation. In the survey of electricity generation in 1995 for which no information was made available from China and Kasachstan, a total of 417 nuclear power plants were covered. In the year under review they generated an aggregate 2 282 614 GWH, which is 3.4% more than in the previous year. The highest nuclear generation again was recorded in the USA with 705 771 GWh, followed by France with 377 021 GWh. The Grohnde power station in Germany attained the maximum annual production figure of 11 359 GWh. The survey includes nine tables indicating the generating performance of each nuclear power plant, the development of electricity generation in nuclear plants, and status of nuclear power plants at the end of 1995 arranged by countries, types of reactors, and reactor manufacturers. (orig.)

  10. Human factors in atomic power plant

    International Nuclear Information System (INIS)

    To ensure safety should have priority over all other things in atomic power plants. In Chernobyl accident, however, various human factors including the systems for bulb check after inspection and communication, troubles in the interface between hardwares such as warning speakers and instruments, and their operators, those in education and training for operators and those in the general management of the plant have been pointed out. Therefore, the principles and the practical measures from the aspect of human factors in atomic power plants were discussed here. The word, ''human factor'' was given a definition in terms of the direct cause and the intellectual system. An explanatory model for human factors, model SHEL constructed by The Tokyo Electric Power Co., Ltd., Inc. was presented; the four letter mean software(S), hardware(H), environment(E) and liveware(L). In the plants of the company, systemic measures for human error factors are taken now in all steps not only for design, operation and repairing but also the step for safety culture. Further, the level required for the safety against atomic power is higher in the company than those in other fields. Thus, the central principle in atomic power plants is changing from the previous views that technology is paid greater importance to a view regarding human as most importance. (M.N.)

  11. The assessment of the environmental external costs of power plants for both coal-fired plant and nuclear power plant

    International Nuclear Information System (INIS)

    Efforts were made to assess the environmental external costs of power plants for both Samchonpo coal-fired plant and Younggwang nuclear power plant by using the computer program developed by the IAEA. In the case that the emission control devices such as precipitator for particulates reduction, wet scrubber for SO2, and low-NOx burner for NOx were installed in the coal-fired power plant, total environmental external cost was estimated as 33.97Won/kWh, much higher than 0.76Won/kWh of Younggwang nuclear power plant. And this study also assessed and compared the environmental external costs when Younggwang nuclear power plant was replaced by the coal-fired power plant at the same site and with the same capacity. According to the result, total environmental external cost of coal-fired power plant, with the emisison control devices installed, was estimated as 792 million US$ and it was about 50 times higher than 15 million US$ of Younggwang nuclear power plant. Although the result of this study had some limits due to using the simplified model, it was still true that nuclear power was much more environmentally friendly power source than coal-fired power

  12. Insurance risk of nuclear power plant concentrations

    International Nuclear Information System (INIS)

    The limited number of sites available in the Federal Republic of Germany for the erection of nuclear power plants has resulted in the construction of multiple nuclear generating units on a few sites, such as Biblis, Gundremmingen and Neckarwestheim. At a value invested of approximately DM 1,200/kW this corresponds to a property concentration on one site worth DM 2 - 3 billion and more. This raises the question whether a concentration of value of this magnitude does not already exceed the limits of bearable economic risks. The property risk of a nuclear power plant, as that of any other industrial plant, is a function of the property that can be destroyed in a maximum probable loss. Insurance companies subdivide plants into so-called complex areas in which fire damage or nuclear damage could spread. While in some foreign countries twin nuclear power plants are built, where the technical systems of both units are installed in one building without any physical separation, dual unit plants are built in the Federal Republic in which the complexes with a high concentration of valuable property are physically separate building units. As a result of this separation, property insurance companies have no grounds for assessing the risk and hence, the premium different from those of single unit plants. (orig.)

  13. Computer determination of event maps with application to auxiliary supply systems

    International Nuclear Information System (INIS)

    A method of evaluating the reliability of sequential operations in systems containing standby and alternate supply facilities is presented. The method is based upon the use of a digital computer for automatic development of event maps. The technique is illustrated by application to a nuclear power plant auxiliary supply system. (author)

  14. Nuclear power plants, citizens' action groups, power of state

    International Nuclear Information System (INIS)

    If you follow the scientific discussion on the pros and cons of the peaceful utilization of nuclear energy (obviously only suicides agree on its non-peaceful utilization) you can state the following two tendencies at first sight: Scientists do only deal with this problem to strengthen hypotheses they have already made. In most cases they deal with a system which is characterized by a lack of calculations, an even greater lack of tests and by a lot of speculation. Advocates of nuclear power plants like to join in this argumentation. Only few scientists question the abstract model of calculation on the burden caused by nuclear power plants, showing that a larger radioactive burden may trigger an uncontrolable, complex reaction within the body (as e.g. Contergan did). In the following we discuss in outline form a few aspects to be considered by operators of nuclear power plants. (orig./GL)

  15. Dukovany nuclear power plant safety

    International Nuclear Information System (INIS)

    Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

  16. Efficiency improvement of thermal coal power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hourfar, D. [VEBA Kraftwerke Ruhr Ag, Gelsenkirchen (Germany)

    1996-12-31

    The discussion concerning an increase of the natural greenhouse effect by anthropogenic changes in the composition of the atmosphere has increased over the past years. The greenhouse effect has become an issue of worldwide debate. Carbon dioxide is the most serious emission of the greenhouse gases. Fossil-fired power plants have in the recent past been responsible for almost 30 % of the total CO{sub 2} emissions in Germany. Against this background the paper will describe the present development of CO{sub 2} emissions from power stations and present actual and future opportunities for CO{sub 2} reduction. The significance attached to hard coal as one of today`s prime sources of energy with the largest reserves worldwide, and, consequently, its importance for use in power generation, is certain to increase in the years to come. The further development of conventional power plant technology, therefore, is vital, and must be carried out on the basis of proven operational experience. The main incentive behind the development work completed so far has been, and continues to be, the achievement of cost reductions and environmental benefits in the generation of electricity by increasing plant efficiency, and this means that, in both the short and the long term, power plants with improved conventional technology will be used for environmentally acceptable coal-fired power generation.

  17. MARS calculation of PAFS (passive auxiliary feedwater system) heat exchanger in APR+

    International Nuclear Information System (INIS)

    APR+ (Advanced Power Reactor Plus), the next generation nuclear power plant in Korea, adopts PAFS (Passive Auxiliary Feedwater System) as one of the advanced safety feature. To design the condensation heat exchanger in PAFS, the two-phase flow phenomena in horizontal U-tube and PCCT (Passive Condensate Cooling Tank) were investigated by MARS calculation. By benchmarking with NOKO experimental result, MARS code showed a reasonable capability to quantitatively predict the condensation in horizontal tube heat exchanger. And the design of PAFS heat exchanger was proved to sufficiently remove the decay heat by the condensation heat transfer without any active auxiliary feedwater system

  18. Evaluation of Effect of N2 Gas on the Cooling Capability of Passive Auxiliary Feedwater System

    International Nuclear Information System (INIS)

    Advanced Power Reactor Plus (APR+), a next generation nuclear power plant in Korea, adopts Passive Auxiliary Feedwater System (PAFS) to replace the conventional active auxiliary feedwater system. Because PAFS removes decay heat from the reactor core, it is required to verify the performance of PAFS in postulated accidents cases. In addition, an effect of non-condensable gas such as N2 gas on the heat removal capability of PAFS should be evaluated since the non-condensable gas may deteriorate a condensation heat transfer through the condensation heat exchanger in PAFS. In this study, MARS code is used to evaluate the effect of N2 gas

  19. MARS calculation of PAFS (passive auxiliary feedwater system) heat exchanger in APR+

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Byoung Uhn; Yun, Byong Jo; Bae, Sung Won; Choi, Ki Yong; Song, Chul Hwa [KAERI, Daejeon (Korea, Republic of); Cheon, Jong [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2009-07-01

    APR+ (Advanced Power Reactor Plus), the next generation nuclear power plant in Korea, adopts PAFS (Passive Auxiliary Feedwater System) as one of the advanced safety feature. To design the condensation heat exchanger in PAFS, the two-phase flow phenomena in horizontal U-tube and PCCT (Passive Condensate Cooling Tank) were investigated by MARS calculation. By benchmarking with NOKO experimental result, MARS code showed a reasonable capability to quantitatively predict the condensation in horizontal tube heat exchanger. And the design of PAFS heat exchanger was proved to sufficiently remove the decay heat by the condensation heat transfer without any active auxiliary feedwater system.

  20. Nuclear Mpd Gas Turbine Power Plant

    International Nuclear Information System (INIS)

    In MPD generators employing alkali-metal-seeded inert gases as the working fluid, the possibility of utilizing magnetically-induced non-equilibrium ionization has been established on theoretical grounds and there is supporting experimental evidence. Joule heating of the working plasma preferentially enhances the electron temperature, producing plasma electrical conductivity levels much higher than apply for thermal equilibrium ionization. The effect is increased by increasing the applied magnetic field and (within limits) by reducing the operating pressure level. If high levels of electrical conductivity can be maintained in this non-equilibrium mode, a cycle in which temperature levels are dictated on thermodynamic grounds only can be selected. The optimization of a Brayton cycle in terms of thermodynamic efficiency and specific power is considered. The proposed cycle consists simply of a heat source, MPD generator, recuperator, heat sink and compressor, the latter being driven either electrically or by a turbine in the circuit. The general features of a land-based nuclear, recuperative closed-cycle MPD power plant are presented. An all-graphite prismatic core helium-cooled nuclear reactor is the heat source. A single gas thermodynamic cycle is considered rather than combined gas and steam cycles, to avoid the hazards of water-graphite reactions due to in-leakage from a high pressure steam cycle and to simplify the plant and its control. The detailed plant layout-suggested is given theoretical and practical justification. Detailed parametric surveys on the MPD generator and the cycle thermodynamics have been performed and some of the combined results are presented. With a reactor outlet temperature of 1800°K, gas turbine inlet temperature of 1200°K, single intercooling and cycle losses estimated from present technological data, it is shown that net plant efficiencies of 55-60% can be obtained. Fuel temperatures for a range of reactor and fuel geometries, reactor

  1. Nuclear power/water pumping-up composite power plant

    International Nuclear Information System (INIS)

    In a nuclear power/water pumping-up composite power plant, a reversible pump for pumping-up power generation connected to a steam turbine is connected to an upper water reservoir and a lower water reservoir. A pumping-up steam turbine for driving the turbine power generator, a hydraulic pump for driving water power generator by water flowing from the upper water reservoir and a steam turbine for driving the pumping-up pump by steams from a nuclear reactor are disposed. When power demand is small during night, the steam turbine is rotated by steams of the reactor, to pump up the water in the lower water reservoir to the upper water reservoir by the reversible pump. Upon peak of power demand during day time, power is generated by the steams of the reactor, as well as the reversible pump is rotated by the flowing water from the upper water reservoir to conduct hydraulic power generation. Alternatively, hydraulic power generation is conducted by flowing water from the upper reservoir. Since the number of energy conversion steps in the combination of nuclear power generation and pumping-up power generation is reduced, energy loss is reduced and utilization efficiency can be improved. (N.H.)

  2. Nuclear power plants are getting movable

    International Nuclear Information System (INIS)

    Russia is building the first floating nuclear plant. This ship named 'Academic Lomonosov' is 144 meter long and 30 meter wide, it carries 2 compact reactors KCT-40S we find usually on ice-breakers and submarines (although the enrichment of their nuclear fuel will be lower), each one releases an electrical power of 35 MW, together they are sufficient to power a city of 200.000 inhabitants. The 'Academic Lomonosov' is scheduled to be operating in 2012 in the Kamchatka peninsula. Its cost rounds 230 millions euros and 6 similar floating plants are planned to be built in Russia till 2020. In order to comply with the non-proliferation treaty, the floating power plants will be rented to foreign operators but not sold. The Russian owner will stay in charge of the operating and maintenance works and of the complete nuclear fuel cycle. This project confirms the actual and general trend for smaller nuclear units. (A.C.)

  3. Nuclear power plant and state border

    International Nuclear Information System (INIS)

    The paper constitutes the slightly revised version of a legal opinion given to those local authorities in Germany which are affected by the construction of the Cattenom powerplant centre in France near to her borders with Germany and Luxembourg. In this opinion, especially claims were examined which might be raised by local authorities according to public and private law, or by the inhabitants of frontier areas, constituting, among other things, claims to the information required, to necessary measures to be taken for the safety of the population and for environmental protection, and ways and means of enforcing them. In addition, the power plant owner's civil liability for the damaging effects of power plant operation are examined as well as the international liability of the state which builds power plants. (HSCH)

  4. Ground acceleration in a nuclear power plant

    International Nuclear Information System (INIS)

    A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

  5. Hitachi's maintenance technologies for nuclear power plant

    International Nuclear Information System (INIS)

    Abstract of high maintenance technologies for nuclear power plants, the technologies for new inspection system, maintenance of in-core instruments and piping, and technologies for high output power of plants are stated. The high maintenance technologies aim at long-term stable operation, increase of capacity factor, and decrease of exposure. Some examples of maintenance technologies of in-core equipments and primary loop recirculation (PLR) piping such as stress improvement and repair work are explained. Hydrogen water chemistry (HWC) and noble metal chemical addition (NMCA) for corrosion are described. Abstract of maintenance technologies, execution of water jet peening (WJP), outline of equipments of induction heating stress improvement (IHSI), the outside appearance of remote operation vehicle (ROV), advanced vortex nozzle (AVN), continuous cover blade (CCB), combined intermediate valve (CIV), moisture separator and heater (MSH), and evaluation examples of high output power of plants are illustrated. (S.Y.)

  6. Environmental protection in thermal power plants

    International Nuclear Information System (INIS)

    This workbook is a compilation of the most important facts and data that are relevant today for environmental protection in thermal power plants. Unlike the other issues the text is not in the form of a random collection of data but in the form of a complete presentation. Possible elaboration projects for pupils can be easily derived from the individual sections. These deal with: the discussion about environmental protection; forest decline; sources of emission; nuisances in the Federal Republic of Germany; environmental protection in fossil-fuel power plants - clean air - cooling water utilization and water protection - noise; environmental protection in nuclear power plants - radioactive material produced in nuclear reactors and the retention of such materials - radioactive waste materials - monitoring of radioactive emissions; accessory materials and hints. (orig./HSCH)

  7. Customer benefit and power plant development

    International Nuclear Information System (INIS)

    In recent years, many aspects of the power market and customer needs in plant operation have been changing more rapidly than manufacturers could launch new products on the market. As a result, flexibility is required not only in the operation of power plants, but also in drawing up product specifications and in the ensuing engineering. The familiar major objectives of development work, such as low specific investment cost and high efficiency, remain important. Also in the context of reducing CO2 emissions and trading with CO2 certificates, improving the efficiency of power plants is a measure that, over and above today's cost optimum, represents the 'action of least regret' with a view to sustainably meeting the requirements of the Kyoto Protocol. (orig.)

  8. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole fourth quarter of 1991. The load factor average was 94.7 % (the whole year 90.9 %). All the events in the last annual quarter, which are classified on the International Nuclear Event Scale, were below scale/level 0. Also the events which occurred in the other quarters of the year 1991 were rated at the scale's lowest levels. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure originating in nuclear power plants were detected in the samples collected in the vicinity of the nuclear power plants

  9. Electronuclear power plants in future nuclear power production

    International Nuclear Information System (INIS)

    The article outlines several options for achieving the transmutation of long-lived radioactive wastes. A brief description of fast reactors and proton accelerators for this purpose is given. The article then describes several possible uses of electronuclear plants, consisting of a subcritical blanket with an external neutron source comprised of a linear proton accelerator and a neutron-producing target, for transmutation. Transmutation in electronuclear plants without energy consumption, with power production, and with power production as well as the production of new fissioning materials are all outlined. 11 refs

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

    International Nuclear Information System (INIS)

    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

  11. Bid invitation specifications for nuclear power plants

    International Nuclear Information System (INIS)

    The Guidebook on Bid Invitation Specifications for Nuclear Power Plants is primarily directed to the managers and senior professional staff of plant owner organizations intending to launch a call for bids for a first nuclear power plant. However, the Guidebook should also be of some value for experienced owners who are about to acquire a follow-up unit. The purpose of this Guidebook is to give advice on the kind of information to be provided by the prospective plant owner to the prospective suppliers. This information should enable them to have a clear conception of the owner's wishes, of his requirements and preferences, the conditions and circumstances under which the tasks should be performed, and the detailed data and information requested of them. The presentation of this information should be such that bid evaluation and contract negotiations are facilitated

  12. Fiber optic applications in nuclear power plants

    International Nuclear Information System (INIS)

    Fiber optic technology possesses many desirable attributes for applications in commercial nuclear power plants. The non-electrical nature of fiber optics is an important factor in an industry governed by federal safety regulations such as Class 1E isolation and separation criteria. Immunity from Electromagnetic Interference (EMI), an increasing industry problem area, is another significant characteristic. Because of the extremely wide bandwidth offered, fiber optics better addresses the data acquisition and communication requirements of the complex processes of a nuclear power plant. Potential for fiber optic sensor applications exists within the nuclear industry because their small size and physical flexibility allows access into normally inaccessible areas. They possess high accuracy and allow environmentally sensitive electronics to be remotely located. The purpose of this paper is to explore current applications for fiber optic technology in modern nuclear plants, document examples of present day usage in C-E plants and suggest possible future application areas

  13. Thermal power plant wastes and their management

    International Nuclear Information System (INIS)

    The problem of pollution caused by coal-fired thermal power plants is still of importance because of the tremendous growth in use of electrical energy. The wastewaters of a typical coal fired power plant include cooling tower blowdown, wastewaters from ash handling system, boiler blowdown, regenerate wastes, floor and yard drains, coal pile run off etc. The solid waste is the fly ash. The present communication deals with the physico-chemical characteristics of fly ash pond effluent and the fly ash and their effects on certain chemical properties of soil, seed germination pattern and the growth of some crop plants. The plants selected for these studies were as follows: for fly ash pond effluent - kidney bean (Phaseolus aureus) and lady's finger (Abelmoschus esculentus), whereas for the fly ash - wheat (Triticum aestivum) and pea (Pisum sativum). 7 tabs.; 20 refs. (author)

  14. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    While refurbishments for the long-term operation of nuclear power plants and for the lifetime extension of such plants have been widely pursued in recent years, the number of plants to be decommissioned is nonetheless expected to increase in future, particularly in the United States and Europe. It is thus important to understand the costs of decommissioning so as to develop coherent and cost-effective strategies, realistic cost estimates based on decommissioning plans from the outset of operations and mechanisms to ensure that future decommissioning expenses can be adequately covered. This study presents the results of an NEA review of the costs of decommissioning nuclear power plants and of overall funding practices adopted across NEA member countries. The study is based on the results of this NEA questionnaire, on actual decommissioning costs or estimates, and on plans for the establishment and management of decommissioning funds. Case studies are included to provide insight into decommissioning practices in a number of countries. (authors)

  15. Power plant conceptual studies in Europe

    International Nuclear Information System (INIS)

    The European Power Plant Conceptual Study (PPCS) has been a study of conceptual designs for commercial fusion power plants. It focussed on five power plant models, named PPCS A, B, AB, C and D, which are illustrative of a wider spectrum of possibilities. They are all based on the tokamak concept and they have approximately the same net electrical power output, 1500 MWe. These span a range from relatively near-term, based on limited technology and plasma physics extrapolations, to an advanced conception. All five PPCS plant models differ substantially from the models that formed the basis of earlier European studies. They also differ from one another, which lead to differences in economic performance and in the details of safety and environmental impacts. The main emphasis of the study was on system integration. Systems analyses were used to produce self-consistent plant parameter sets with approximately optimal economic characteristics for all models. In the PPCS models, the favourable, inherent, features of fusion have been exploited to provide substantial safety and environmental advantages. The broad features of the safety and environmental conclusions of previous studies have been confirmed and demonstrated with increased confidence. Two key innovative developments made within the PPCS study are worthy of a special note. One is the development of a scheme for the scheduled replacement of the internal components which shows the potential for an overall plant availability in excess of 75%. The other is a conceptual design for a helium-cooled divertor, which permits the toleration of heat loads of at least 10 MW/m2. The PPCS study has highlighted the need for specific design and R and D activities, in addition to those already underway within the European long term R and D programme, as well as the need to clarify the concept of DEMO, the device that will bridge the gap between ITER and the first-of-a-kind fusion power plant. (author)

  16. Operator training simulator for nuclear power plant

    International Nuclear Information System (INIS)

    In nuclear power plants, training of the operators is important. In Japan, presently there are two training centers, one is BWR operation training center at Okuma-cho, Fukushima Prefecture, and another the nuclear power generation training center in Tsuruga City, Fukui Prefecture, where the operators of PWR nuclear power plants are trained. This report describes the BWR operation training center briefly. Operation of a nuclear power plant is divided into three stages of start-up, steady state operation, and shut down. Start-up is divided into the cold-state start-up after the shut down for prolonged period due to periodical inspection or others and the hot-state start-up from stand-by condition after the shut down for a short time. In the cold-state start-up, the correction of reactivity change and the heating-up control to avoid excessive thermal stress to the primary system components are important. The BWR operation training center offers the next three courses, namely beginner's course, retraining course and specific training course. The training period is 12 weeks and the number of trainees is eight/course in the beginner's course. The simulator was manufactured by modeling No. 3 plant of Fukushima First Nuclear Power Station, Tokyo Electric Power Co. The simulator is composed of the mimic central control panel and the digital computer. The software system comprises the monitor to supervise the whole program execution, the logic model simulating the plant interlock system and the dynamic model simulating the plant physical phenomena. (Wakatsuki, Y.)

  17. OPTIMIZING THE PERFORMANCE OF THERMAL POWER PLANTS

    OpenAIRE

    Sushila Mishra; Ganesh Chembedu

    2016-01-01

    Failure of boiler tubes has been a familiar phenomenon in power plants resulting in unscheduled plant shut down; in consequence, there are heavy losses in industrial production. The failure of boiler tubes appears in the form of bending, bulging, cracking, wearing or rupture, causing leakage of the tubes. The failure can be caused by one or more modes such as overheating, stress corrosion cracking (SCC), hydrogen embrittlement, creep, flame impingement, sulfide attack, weld attack, ash erosio...

  18. Nuclear power plant outage optimisation strategy

    International Nuclear Information System (INIS)

    Competitive environment for electricity generation has significant implications for nuclear power plant operations, including among others the need of efficient use of resources, effective management of plant activities such as on-line maintenance and outages. Nuclear power plant outage management is a key factor for good, safe and economic nuclear power plant performance which involves many aspects: plant policy, co-ordination of available resources, nuclear safety, regulatory and technical requirements and, all activities and work hazards, before and during the outage. This technical publication aims to communicate these practices in a way they can be used by operators and utilities in the Member States of the IAEA. It intends to give guidance to outage managers, operating staff and to the local industry on planning aspects, as well as examples and strategies experienced from current plants in operation on the optimization of outage period. This report discusses the plant outage strategy and how this strategy is actually implemented. The main areas identified as most important for outage optimization by the utilities and government organizations participating in this report are: organization and management; outage planning and preparation, outage execution, safety outage review, and counter measures to avoid extension of outages and to easier the work in forced outages. This report was based on discussions and findings by the authors of the annexes and the participants of an Advisory Group Meeting on Determinant Causes for Reducing Outage Duration held in June 1999 in Vienna. The report presents the consensus of these experts regarding best common or individual good practices that can be used at nuclear power plants with the aim to optimize

  19. Experience in operation of nuclear power plant

    International Nuclear Information System (INIS)

    Following a brief description of the structure, financing and generating plant of Sydkraft, the Barsebaeck plant is briefly described. The construction schedule and personnel are outlinrd as are the investment and operating costs, which are compared with the utility's oil-fired generating costs. The causes of outages are briefly presented and discussed. The wastes from generating the same amount of power as Barsebaeck in 1977 using oil fuel are compared with the radioactive waste for that year. (JIW)

  20. Seismic instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

    A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those plants, against the action of earth quarks is described. The instrumentation is based on the nuclear standards and other components used, as well as their general localization is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The accelerometer is described in detail. (Author)

  1. Study of auxiliary power systemsfor offshore wind turbines : an extended analysis of a diesel gen-setsolution

    OpenAIRE

    Berggren, Joakim

    2013-01-01

    Until today the offshore wind power has grown in a steady pace and many new wind farms are being constructed around the globe. An important factor that is investigated today in the industry are the security of power supply to the equipment needed for controlling the offshore system during emergency situations. When a offshore wind farm is disconnected from the external grid and an emergency case occur the wind turbine generators lose their ability to transfer power and they are forced to be t...

  2. The EU power plant conceptual study

    International Nuclear Information System (INIS)

    An integrated Power Plant Conceptual Study (PPCS) was launched in 1988 in the frame of the European Fusion Programme. The objective of the PPCS is to demonstrate: the credibility of fusion power plant design(s); the claims for the safety and environmental advantages and for the economic viability of fusion power. In addition results of the PPCS Programme will help to define the R and D Programme. The strategy of the PPCS is to study a limited number of Plant Models that span the expected range of possibilities. These range from an advanced version of International Thermonuclear Experimental Reactor (ITER) through to the presently foreseen ultimately achievable values of the plasma physics and technology parameters, together with a range of blanket and high heat flux technologies. The primary focus of detailed studies, and the first work to be undertaken, is on two Plant Models that emphasise limited extrapolation, since credibility within the philosophy of a possible fast-track development of fusion power is a major aim of the study. The remainder of this paper discusses the physics studies and the preliminary technology studies that have formed the launching pad for the detailed studies of Plant Models within the PPCS. The discussion concentrates on the 'limited extrapolation' Models that are being studied first, with brief reference to the Models that are further from ITER

  3. Exergy analysis of a cogeneration power plant

    International Nuclear Information System (INIS)

    In the following study exergetic evaluation of a cogeneration power plant in operation with installed electrical capacity of 24 MW and process heat demand of 190 MW it is performed. The main objective of the research was to determine the influence of the increase in power generation capacity, raising the superheated steam parameters and the number of regenerative heaters on the second law efficiency and irreversibilities in the different components of the plant. To study the power plant was divided into subsystems: steam generator blowdown expander, main steam pipe, steam turbine regenerative heaters, reduction system, deaerator and pumps. The study results show that exergy losses and irreversibilities differ widely from one subsystem to another. In general, the total irreversibility accounted for 70.7% of primary fuel availability. The steam generator subsystem had the highest contribution to the irreversibility of the plant by 54%. It was determined that the increased steam parameters helps reduce the irreversibility and increase the exergetic efficiency of installation. The suppression of the reduction and incorporation of extraction-condensing turbine produce the same effect and helps to reduce power consumption from the national grid. Based on the results recommendations for improving plant efficiency are made. (full text)

  4. Seismic safety of nuclear power plants

    International Nuclear Information System (INIS)

    This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in Eastern Europe and in particular WWER type nuclear power plants during the past seven years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on 'Benchmark study for the seismic analysis and testing of WWER type nuclear power plants'. These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

  5. Ground assessment methods for nuclear power plant

    International Nuclear Information System (INIS)

    It is needless to say that nuclear power plant must be constructed on the most stable and safe ground. Reliable assessment method is required for the purpose. The Ground Integrity Sub-committee of the Committee of Civil Engineering of Nuclear Power Plant started five working groups, the purpose of which is to systematize the assessment procedures including geological survey, ground examination and construction design. The works of working groups are to establishing assessment method of activities of faults, standardizing the rock classification method, standardizing assessment and indication method of ground properties, standardizing test methods and establishing the application standard for design and construction. Flow diagrams for the procedures of geological survey, for the investigation on fault activities and ground properties of area where nuclear reactor and important outdoor equipments are scheduled to construct, were established. And further, flow diagrams for applying investigated results to design and construction of plant, and for determining procedure of liquidification nature of ground etc. were also established. These systematized and standardized methods of investigation are expected to yield reliable data for assessment of construction site of nuclear power plant and lead to the safety of construction and operation in the future. In addition, the execution of these systematized and detailed preliminary investigation for determining the construction site of nuclear power plant will make much contribution for obtaining nation-wide understanding and faith for the project. (Ishimitsu, A.)

  6. High power proton accelerator for nuclear power plant

    International Nuclear Information System (INIS)

    The novel nuclear power system--Energy Amplifier, proposed by C. Rubbia, attracts the interest as a prior option for the development of the next generation nuclear power plant in the first half of the 21st century. The accelerator used to drive the system should provide proton beam power tens higher than that of LAMPF. The accelerator physics and technology have been advancing greatly since LAPMF was built more than 20 years ago. These new progresses become the essential basis for the intense beam accelerator to advance up to a much higher beam power. However, some challenges are still being faced, including beam loss, high efficiency, reliability, as well as some technical issues associated with high power CW operation. The accelerator design options to tackle with the difficulties are discussed. The suggestions on R and D of high power accelerator in China are presented

  7. Development of concentrated solar power and conventional power plant hybrids

    OpenAIRE

    Suojanen, Suvi

    2016-01-01

    CSP hybrids are one of the possible technical solutions in order to increase the share of renewable energy and decrease greenhouse gas emission levels as well as fuel consump-tion. The main objectives of the thesis are to research state-of-the-art technologies in concentrated solar power (CSP) and conventional power plants, to comprehensively study the possible integration options and to develop one CSP hybrid configuration by using Advanced Process Simulator (Apros), which is a dynamic model...

  8. Virtual environments for nuclear power plant design

    Energy Technology Data Exchange (ETDEWEB)

    Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W. [and others

    1996-03-01

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

  9. Nuclear Power Plant Temelin Technical Support Centre

    International Nuclear Information System (INIS)

    The erection of the Technical Support Centre for the Nuclear Power Plant Temelin has been a relatively sophisticated and costly issue. It was by proper use of the existing systems, as e.g. I and C, ISE and other systems, that a robust system has been created that is able to meet any requirements laid on the performance of the Technical Support Centre. The decision of the utility CEZ, a.s. that made it possible to establish the Technical Support Centre at the Nuclear Power Plant Temelin has been a right step which shows the level of safety culture within the utility. (author)

  10. Nuclear power plant siting: Hydrogeologic aspects

    International Nuclear Information System (INIS)

    This Safety Guide gives guidelines and methods for determining the ground water concentration of radionuclides that could result from postulated releases from nuclear power plants. The Guide gives recommendations on the data to be collected and the investigations to be performed at various stages of nuclear power plant siting in relation to the various aspects of the movement of accidentally released radioactive material through the ground water, the selection of an appropriate mathematical or physical model for the hydrodynamic dispersion even two-phase distribution of the radioactive material and an appropriate monitoring programme

  11. Virtual environments for nuclear power plant design

    International Nuclear Information System (INIS)

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP)

  12. Decommissioning of nuclear power plants - safety aspects

    International Nuclear Information System (INIS)

    The stages of decommissioning a nuclear power plant are presented in popular form. There exist two alternatives: Safe containment of activated and highly contaminated components within the nuclear power plant unit or dismantling of all components and buildings. Stage 1 provides for safe containment in a) previously sealed buildings without any dismantling; b) containment resp. reactor building; c) underground structures. Stage 2 provides for partial dismantling with safe containment of the remaining parts a) within the biological shield, b) underground, after dismantling the parts above ground level. Stage 3 provides for total dismantling. (orig.)

  13. Diagnostic system for combine cycle power plant

    International Nuclear Information System (INIS)

    We developed the Diagnostic System for Combined Cycle Power Plant which enables inexperienced operators as well as experienced operators to cope with abnormal conditions of Combined Cycle Power Plant. The features of this system are the Estimate of Emergency Level for Operation and the Prediction of Subsequent Abnormality, adding to the Diagnosis of Cause and the Operation Guidance. Moreover in this system, Diagnosis of Cause was improved by using our original method and support screens can be displayed for educational means in normal condition as well. (Authors)

  14. Robotic fabrication and inspection for power plants

    International Nuclear Information System (INIS)

    The usage of Robotic Automation is now an integral part of the modern manufacturing systems. Applications in nuclear power plants is no exception. As a matter of fact, as a result of the hazards of radiations for the human workers makes automation of the on-site working highly desirable. This presentation will focus on the broad benefits by use of automation in Power plants. Various processes and technologies for robotic applications in fabrication, maintenance and inspection will be highlighted. The specific technology features for use in nuclear environments will be highlighted

  15. Nuclear power plant database internet version

    International Nuclear Information System (INIS)

    The nuclear power plant database contains the design information on 50 domestic light-water reactor nuclear power plants retrieved from the safety analysis reports. Its version for the main frame computer in the Japan Atomic Energy Research Institute (JAERI) was opened to the public in 1995. In the present Internet version, approximately 64,000 data were retrieved from the main frame version and stored. These data include the shapes, dimensions, performances, etc. of the equipment and components described in 'Appendix 8: Safety design of the reactor facility' of each safety analysis report. This report describes the database structure, program specification and information retrieval functions of the Internet version. (author)

  16. Site survey for nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide describes the first stage of the siting process for nuclear power plants - the site survey to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No.50-C-S). The organization, procedures, methodologies, guidance for documenting the site survey process and examples of detailed procedures on some safety-related site characteristics are given in the Guide

  17. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 steam plant. Described in this Final (Third Annual) Technical Progress Report is the accomplishment of the project's final milestone, an in-plant intelligent control experiment conducted on April 1, 1993. The development of the experiment included: simulation validation, experiment formulation and final programming, procedure development and approval, and experimental results. Other third year developments summarized in this report are: (1) a theoretical foundation for Reconfigurable Hybrid Supervisory Control, (2) a steam plant diagnostic system, (3) control console design tools and (4) other advanced and intelligent control

  18. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    During the second quarter of 1990 the Finnish nuclear plant units Loviisa 1 and 2 and TVO and II were in commercial operation for most of the time. The feedwater pipe rupture at Loviisa 1 and the resulting inspections and repairs at both Loviisa plant units brought about an outage the overall duration of which was 32 days. The annual maintenance outages of the TVO plant units were arranged during the report period and their combined duration was 31.5 days. Nuclear electricity accounted for 35.3% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 83.0%. Three events occurred during the report period which are classified as Level 1 on the International Nuclear Event Scale: feedwater pipe rupture at Loviisa 1, control rod withdrawal at TVO I in a test during an outage when the hydraulic scram system was rendered inoperable and erroneous fuel bundle transfers during control rod drives maintenance at TVO II. Other events during this quarter are classified as Level Zero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. Only small amounts of nuclides originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  19. Aging effects in PWR power plants components

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Diogo da S.; Guimaraes, Antonio C.F.; Moreira, Maria de Lourdes, E-mail: diogosb@outlook.com, E-mail: tony@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    This paper presents a contribution to the study of aging process of components in commercial plants of Pressurized Water Reactors (PWRs). The analysis is made through application of the Fault Trees Method, Monte Carlo Method and Fussell-Vesely Importance Measure. The approach of the study of aging in nuclear power plants, besides giving attention to the economic factors involved directly with the extent of their operational life, also provide significant data on security issues. The latest case involving process of life extension of a PWR could be seen in Angra 1 Nuclear Power Plant through investing of $27 million for the installation of a new reactor lid. The corrective action has generated an estimated operating life extension of Angra I in twenty years, offering great economy compared with building cost of a new plant and anterior decommissioning, if it had reached the time operating limit of forty years. The Extension of the operating life of a nuclear power plant must be accompanied by a special attention to the components of the systems and their aging process. After the application of the methodology (aging analysis of the injection system of the containment spray) proposed in this work, it can be seen that 'the increase in the rate of component failure, due the aging process, generates the increase in the general unavailability of the system that containing these basic components'. The final results obtained were as expected and may contribute to the maintenance policy, preventing premature aging process in Nuclear Plant Systems. (author)

  20. Aging effects in PWR power plants components

    International Nuclear Information System (INIS)

    This paper presents a contribution to the study of aging process of components in commercial plants of Pressurized Water Reactors (PWRs). The analysis is made through application of the Fault Trees Method, Monte Carlo Method and Fussell-Vesely Importance Measure. The approach of the study of aging in nuclear power plants, besides giving attention to the economic factors involved directly with the extent of their operational life, also provide significant data on security issues. The latest case involving process of life extension of a PWR could be seen in Angra 1 Nuclear Power Plant through investing of $27 million for the installation of a new reactor lid. The corrective action has generated an estimated operating life extension of Angra I in twenty years, offering great economy compared with building cost of a new plant and anterior decommissioning, if it had reached the time operating limit of forty years. The Extension of the operating life of a nuclear power plant must be accompanied by a special attention to the components of the systems and their aging process. After the application of the methodology (aging analysis of the injection system of the containment spray) proposed in this work, it can be seen that 'the increase in the rate of component failure, due the aging process, generates the increase in the general unavailability of the system that containing these basic components'. The final results obtained were as expected and may contribute to the maintenance policy, preventing premature aging process in Nuclear Plant Systems. (author)

  1. Development of robots for nuclear power plants

    International Nuclear Information System (INIS)

    In nuclear power plants, the reduction of maintenance time, the reduction of radiation exposure and man-power saving are increasingly required. To achieve these purposes, various remote-controlled devices, such as robots in a broad sense, have been earnestly developed. Of these, three machines for replacing, four devices for inspection, two systems for cleaning, and two equipment for processing are tabulated in this paper. Typical eight machines or equipment are briefly introduced, mainly describing their features or characteristics. Those are: a remotely handling machine for control rod drive mechanism, an automatic refueling machine, an automatic ultrasonic flaw detection system replacing for a manually operated testing system for the welded parts of primary cooling system, an automatic cask washing machine for decontamination, a floor-type remote inspection vehicle for various devices operating inside power plants, a monorail-type remote inspection vehicle for inspection in spaces where floor space is short, and a remote-controlled automatic pipe welding machine for welding operations in a radioactive environment such as replacing the piping of primary cooling system. Most of these devices serves for radiation exposure reduction at the same time. Existing nuclear power plant design assumes direct manual maintenance, which limits the introduction of robots. Future nuclear power plants should be designed on the assumption of automatic remote-controlled tools and devices being used in maintenance work. (Wakatsuki, Y.)

  2. Emissions from power plants 1988-1997

    International Nuclear Information System (INIS)

    The document gives statistics on the pollutive emissions from Danish power plants during the period 1988-1997, the main pollutants being sulphur dioxide, nitrogen oxides and carbon dioxide. Data on efficiency levels relative to the production of electricity and heating and on the power plants' contribution to the total emission of CO2, NOx, and SO2 from energy consumption in Denmark, are presented, and also as corrected for the net import of electricity. Other data on the emission of each of these chemicals by power plants are presented as factual, and corrected in accordance with the net import of electricity, and as factual per consumed and produced energy unit at the power plants. Short notes on related Danish legislation are found in addition to information on sources, methods and definitions used as a basis for the production of this document. Emission from power stations is dependent on their energy consumption which is in turn controlled by the demand for electricity and heating. It is stated that efforts to reduce emissions of sulphur dioxide, nitrogen oxides and carbon dioxide have led to a small reduction in air pollution by these chemicals during recent years. (AB)

  3. Nuclear power plant common aging terminology

    International Nuclear Information System (INIS)

    This report defines and encourages the use of a set of common terms and definitions that characterize aging and aging management of nuclear power plant systems, structures, and components. Common aging terminology encompasses the areas of degradation causes, degradation/aging, life, failure, and maintenance. The terminology should prove useful in plant license renewal, life-cycle management, maintenance, and equipment qualification. The principal intended benefits are improved reporting and interpretation of plant experience data (especially failure data) and improved interpretation and compliance with codes, standards, and regulations related to aging of nuclear power plants. The terminology was developed using a sound, systematic technical and lexicographical approach, as well as input from a committee with members from electric utilities, the Nuclear Management and Resources Council (NUMARC), the Electric Power Research Institute (EPRI), the United States Nuclear Regulatory Commission (NRC), and national research laboratories. Draft definitions received an extensive industry review. Formal comments were received from 19 organizations worldwide. The report presents the results of this effort and contains definitions, figures, examples of usage, dictionary definitions, and discussions describing the relationships among the 85 terms and 27 synonyms of the common aging terminology. The terms and definitions are generally consistent with similar terminology used by the Institute of Nuclear Power Operations (INPO). The common aging terminology has been reviewed by NUMARC and the NRC and is recommended for use throughout the nuclear power industry

  4. Nuclear power plant in whose backyard

    International Nuclear Information System (INIS)

    The authority to regulate the nuclear power industry resides largely with the federal government. But states have the responsibility to protect the health and safety of their citizens and to regulate land use within their borders. The siting of nuclear power plants can engender conflicts between these jurisdictions that are usually resolved in the courts. Most state challenges to federal control of nuclear power have been struck down or severely weakened by the preemption doctrine contained in the supremacy clause of Article VI of the Constitution, which provides for the preemption of federal law over state law in the event of direct conflict. The existing avenues for state control over siting and operation of nuclear power plants can be greatly strengthened while avoiding direct conflict with federal jurisdiction

  5. The earthquake security of the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    The seismic safety of Paks Nuclear Power Plant is analyzed. Assessment of earthquake risk has been done at the site of the plant, and seismic resistance of the nuclear power plant is analyzed together. (TRA)

  6. Alpha-nuclides in nuclear power plants

    International Nuclear Information System (INIS)

    The behaviour of alpha-nuclides in nuclear power plants is subject of the investigations presented. The source of alpha-nuclides is a contamination with fissile material (so called tramp uranium or tramp fuel) which deposits on fuel rod surfaces and leads to the build-up of transuranium nuclides. The determination of a defect situation with fuel release as well as the quantification of the fissile material contamination background is given for BWR and PWR plants. The quantification of the fuel release and the tramp uranium background can be calculated with different, measurable nuclides in BWR and PWR plants. (orig.)

  7. Ageing management in German nuclear power plants

    International Nuclear Information System (INIS)

    In Germany the term ageing management comprises several aspects. A demand for a special 'ageing monitoring' programme is not explicitly contained in the regulations. However, from the Atomic Energy Act and its regulations results the operator's obligation to perform extensive measures to maintain the quality of the plant and the operating personnel working in the plant. From this point of view, comprehensive ageing management in German nuclear power plants has taken place right from the start under the generic term of quality assurance. (orig.)

  8. Accident Monitoring Systems for Nuclear Power Plants

    International Nuclear Information System (INIS)

    In the Fukushima Daiichi accident, the instrumentation provided for accident monitoring proved to be ineffective for a combination of reasons. The accident has highlighted the need to re-examine criteria for accident monitoring instrumentation. This publication covers all relevant aspects of accident monitoring in NPPs. The critical issues discussed reflect the lessons learned from the Fukushima Daiichi accident, involve accident management and accident monitoring strategies for nuclear power plants, selection of plant parameters for monitoring plant status, establishment of performance, design, qualification, display, and quality assurance criteria for designated accident monitoring instrumentation, and design and implementation considerations. Technology needs and techniques for accident monitoring instrumentation are also addressed

  9. Ageing management in German nuclear power plants

    International Nuclear Information System (INIS)

    In Germany, the term 'ageing management' comprises several aspects. A demand for a special ageing monitoring programme is not explicitly contained in the regulations. However, from the Atomic Energy Act and its regulations results the operator's obligation to perform extensive measures to maintain the quality of the plant and the operating personnel working in the plant. From this point of view, comprehensive ageing management in German nuclear power plants has taken place right from the start under the generic term of quality assurance. (author)

  10. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tubulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

  11. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hzard to the personnel or the environment

  12. Investment scenarios for Chinese power plants

    International Nuclear Information System (INIS)

    An analysis is provided of returns for investment in power plants in China and India. Three sample investment scenarios are compared to illustrate the relative merits of each financing arrangement. The best returns would seem to be offered by a mix of debt and equity financing. The potential problem of gradual currency depreciation can be overcome by early cash payments. Foreign investment in China's power generation industry would be more readily forthcoming if easier access to debt finance were available. (UK)

  13. Energy investment in nuclear power plants

    International Nuclear Information System (INIS)

    The energy investment in terms of electrical and thermal energy requirements for nuclear power plants is examined. The total lifetime energy inputs required for a 1000-MW(e) plant based on a 30-year plant lifetime and 0.75 plant factor are presented for several pressurized-water-reactor (PWR) and boiling-water-reactor (BWR) systems, two high-temperature gas-cooled reactor (HTGR) systems, and one heavy-water-reactor (HWR) system. The energy analyses reviewed here have demonstrated that the energy expenditures for the various reactor systems are very much less than the energy produced by the reactors and that the initial energy investments are recovered in a short time after startup--several months to 2 years. The energy requirements associated with the individual processes, such as mining, enrichment, construction, and waste disposal, are tabulated for two different fuel cycles for a PWR and a BWR. The enriching process is by far the largest component of the electrical requirements, representing 85 to 90% of the total electrical energy investment. The energy used in constructing and operating the reactor constitutes the largest single investment of thermal energy, representing 50% of the total thermal energy requirements. Results of several analyses are examined and comparisons made between nuclear power plants, a coal plant, and a solar thermal-conversion plant

  14. Safer design for a nuclear power plant

    International Nuclear Information System (INIS)

    During the regulatory process for the issuing of the construction permit and the operating licence of the first Austrian nuclear power plant, more than 1200 injunctions have been issued for increasing its safety standard. In principle they belong to three groups: quality assurance and quality control; the improvement of the design; and probabilistic issues. Examples of all these three groups are given. When discussions with the parties in the regulatory process on the issuing of the operating licence were going on, work at the nuclear power plant was suddenly terminated following the negative outcome of a referendum. The main content of the discussions was that the nuclear inspectors keep permanent control over the plant and have a permanent record of occurrences there, that participation of the regulatory body is included in all issues which might influence the safety standard of the plant, and that the regulatory body may issue new injunctions on the operation of the plant if new standards arise from backfitting ensuing from lessons learned, from the treatment of generic issues, from new rules and regulations and from reactor safety research. Special attention is given to the process of mothballing the plant as was necessary after the referendum. The work on the plant was terminated in an orderly way; a final report was issued which stated what still would have to be done at the plant in order to go into operation. The mothballing began by demounting some systems, emptying others and shutting down a third group. Some ventilation systems are in operation. These activities are also recorded in reports; these, together with a final report of the status reached, could be the basis for revitalization work. Finally it is shown how Austria, with its limited means in terms of funds and personnel, is dealing with the problems of keeping the safety standard of the plant as high as at the plants in other countries with more funds and personnel available. (author)

  15. Control method for BWR type power plant

    International Nuclear Information System (INIS)

    The present invention provides a method of controlling a BWR type plant having internal pumps capable of sufficiently utilizing the performance of a whole volume turbine bypass plant to enable stable supply of electric power upon load interruption of power generator thereof. Namely, upon occurrence of load interruption of a power generator or turbine trip, a plurality of internal pumps are tripped simultaneously to abruptly reduce a reactor core flow rate by a predetermined value or more. In this case, a reactor core flow rate abruptly reduction scram signal is prevented. Alternatively, a plurality of internal pumps are tripped simultaneously to abruptly reduce the reactor core flow rate. In this case, a reactor core flow rate abrupt reduction scram set value is changed in order to inhibit the reactor core flow rate abrupt reduction scram signal. With such procedures, upon load interruption of power generator or upon trip of turbine, reactor core flow rate is abruptly reduced by trip of internal pumps for avoiding increase of neutron fluxes due to reactor pressure change. However, since reactor scram is avoided, the operation can be continued upon load interruption of power generator. As a result, performance of whole volume turbine bypass plant can be utilized sufficiently even upon occurrence of load interruption of power generator. (I.S.)

  16. Institutional approach to power plant safety culture

    International Nuclear Information System (INIS)

    The thesis of this paper is that the requirements for safety culture in nuclear power plants can be failing to recognize contradictions in the various pressures on the organization that have to be balanced in an optimal manner. Nuclear power plants are influenced by pressures from both external and internal sources, that can be viewed as comprising the two main institutionalizing influences on the organization. Most of the effort on safety culture definition and implementation has addressed the utility and the power plant, producing definitions of good practices and of hindrances to good utility safety culture. These often lack formal representation of the demands of the organization and of its environment that are related to institutional processes rather than to productivity. This paper adopts an institutional approach to organizations as a way of clarifying the nature of the interfaces between the power plant and its external agencies, and their respective safety culture requirements. The plant must respond to its own internal organizational demands that are both technical, related to efficiency and productivity, and institutionalizing in terms of organizational processes. External agencies create environmental demands that are primatily institutionalizing in nature, such as the legitimate requirements of society as represented by the regulatory body ; standards of practice desctibed by professional groups; or obligation to conform to international commitments. These inputs mu st be cognizant of all of the parameters of the plant's functioning if they are not to risk detracting from plant efficiency, and so safety. This is a measure of the safety culture of these external agencies. The utility's safety culture is dependent on its abi1ity to balance external demands , internal processes and technical imperatives. (author)

  17. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    During the first quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

  18. Risks of potential accidents of nuclear power plants in Europe

    OpenAIRE

    Slaper H; Eggink GJ; Blaauboer RO

    1993-01-01

    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed on an integrated assessment of probabilistic cancer mortality risks due to possible accidental releases from the European nuclear power plants. For each of the European nuclear power plants the prob...

  19. Recent advances in nuclear power plant simulation

    International Nuclear Information System (INIS)

    The field of industrial simulation has experienced very significant progress in recent years, and power plant simulation in particular has been an extremely active area. Improvements may be recorded in practically all simulator subsystems. In Europe, the construction of new full- or optimized-scope nuclear power plant simulators during the middle 1990's has been remarkable intense. In fact, it is possible to identify a distinct simulator generation, which constitutes a new de facto simulation standard. Thomson Training and Simulation has taken part in these developments by designing, building, and validation several of these new simulators for Dutch, German and French nuclear power plants. Their characteristics are discussed in this paper. The following main trends may be identified: Process modeling is clearly evolving towards obtaining engineering-grade performance, even under the added constraints of real-time operation and a very wide range of operating conditions to be covered; Massive use of modern graphic user interfaces (GUI) ensures an unprecedented flexibility and user-friendliness for the Instructor Station; The massive use of GUIs also allows the development of Trainee Stations (TS), which significantly enhance the in-depth training value of the simulators; The development of powerful Software Development Environments (SDE) enables the simulator maintenance teams to keep abreast of modifications carried out in the reference plants; Finally, simulator maintenance and its compliance with simulator fidelity requirements are greatly enhanced by integrated Configuration Management Systems (CMS). In conclusion, the power plant simulation field has attained a strong level of maturity, which benefits its approximately forty years of service to the power generation industry. (author)

  20. Commissioning of the water demineralization plant of Atucha II Nuclear Power Plant

    International Nuclear Information System (INIS)

    In Argentina there are two operating Nuclear Power Reactors and a third one is being constructed. Embalse NPP is a 648 Mwe CANDU®-600 type pressurized heavy water reactor (PHWR), designed and built by Atomic Energy of Canada (AECL) and in commercial operation since 1984. Atucha I is a Pressurized Vessel Heavy Water Reactor (PVHWR) of 340 Mwe, in operation since 1974, and Atucha II (also PHWR) of 740 Mwe is in advanced construction state, both of them designed by SIEMENS-KWU. All of these Nuclear Power Plants are operated by Nucleoelectrica Argentina (N.A.S.A.). The Comision Nacional de Energia Atomica (C.N.E.A.) is the R and D nuclear institution in the country that, among many other topics, provides technical support to the plants. Although the Atucha II project has suffered some years of delay, pressure tests are expected to be carried out by the end of the year 2010 and in that sense, water chemistry related activities, specifications, chemistry manuals, laboratories organization and personnel training are acquiring importance. The demineralized water needed for the secondary and auxiliary systems is obtained by means of a demineralization plant, which purifies water from Parana River up to nuclear grade. This plant was designed by Degremont in 1979 and consists of a preliminary treatment by coagulation - flocculation and gravel filters, and subsequent demineralization with ion exchange resins. For the commissioning of the demineralization plant, preliminary tests in the chemical laboratory are performed. The flocculator is simulated using a Jar-Test, different coagulants and coagulation aids are tested with the objective of selecting the best product and defining its optimum dosage. The coagulated water is filtered by means of a funnel with filtration paper and sand. The clarified water thus obtained is treated by ion exchange resins, the train consisting of a cationic, an anionic and a mixed bed. The purpose of the laboratory experiments is to test the resins