WorldWideScience

Sample records for equipment receiving power

  1. TDRSS S-shuttle unique receiver equipment

    Science.gov (United States)

    Weinberg, A.; Schwartz, J. J.; Spearing, R.

    1985-01-01

    Beginning with STS-9, the Tracking and Date Relay Satellite system (TDRSS) will start providing S- and Ku-band communications and tracking support to the Space Shuttle and its payloads. The most significant element of this support takes place at the TDRSS White Sands Ground Terminal, which processes the Shuttle return link S- and Ku-band signals. While Ku-band hardware available to other TDRSS users is also applied to Ku-Shuttle, stringent S-Shuttle link margins have precluded the application of the standard TDRSS S-band processing equipment to S-Shuttle. It was therfore found necessary to develop a unique S-Shuttle Receiver that embodies state-of-the-art digital technology and processing techniques. This receiver, developed by Motorola, Inc., enhances link margins by 1.5 dB relative to the standard S-band equipment and its bit error rate performance is within a few tenths of a dB of theory. An overview description of the Space Shuttle Receiver Equipment (SSRE) is presented which includes the presentation of block diagrams and salient design features. Selected, measured performance results are also presented.

  2. Concentrated solar power generation using solar receivers

    Science.gov (United States)

    Anderson, Bruce N.; Treece, William Dean; Brown, Dan; Bennhold, Florian; Hilgert, Christoph

    2017-08-08

    Inventive concentrated solar power systems using solar receivers, and related devices and methods, are generally described. Low pressure solar receivers are provided that function to convert solar radiation energy to thermal energy of a working fluid, e.g., a working fluid of a power generation or thermal storage system. In some embodiments, low pressure solar receivers are provided herein that are useful in conjunction with gas turbine based power generation systems.

  3. Nuclear power generating station equipment qualification method and apparatus

    International Nuclear Information System (INIS)

    Fero, A.H.; Potochnik, L.M.; Riling, R.W.; Semethy, K.F.

    1990-01-01

    This patent describes a method of monitoring an object piece of qualified equipment in a nuclear power plant. It comprises providing a first passive mimic means for mimicking the effect of radiation received by the object piece on the object piece; providing a second mimic means for mimicking the effect of a thermal history of the object piece on the object piece and mounting the first passive mimic means and the second mimic means in close proximity to the object piece

  4. FUNDAMENTALS OF RELIABILITY OF ELECTRIC POWER SYSTEM AND EQUIPMENT

    OpenAIRE

    Engr. Anumaka; Michael Chukwukadibia

    2011-01-01

    Today, the electric power system consists of complex interconnected network which are prone to different problems that militates against the reliability of the power system. Inadequate reliability in the power system causes problems such as high failure rate of power system installations and consumer equipment, transient and intransient faults, symmetrical faults etc. This paper provides an extensive review of the powers system and equipment reliability and related failure patterns in equipment.

  5. Electrical and control equipment in nuclear power plants. Problems when replacing aging equipment

    International Nuclear Information System (INIS)

    Nordling, Anna; Haakansson, Goeran

    2012-01-01

    Interoperability between different technical systems is more complicated when old and new technology meet, such as between analog and digital technology. New electrical and I and C equipment is selected with consideration to simplify and improve the compatibility and interoperability. The original construction of nuclear power plants with electricity and I and C equipment had more natural interfaces. Generally experienced guidance, to the management of interoperability and interfaces, feels insufficient. Skills transfer programs are identified as a major need, as more and more important personnel are retiring and important information is lost with them. Lack of appropriate skills directly affects the ability to produce accurate and complete requirements specification. Failure modes of newer electrical and I and C equipment are perceived as more complex than the older equipment. When choosing equipment, attempts are made to minimize unnecessary features, to reduce the number of potential failure modes. There is a lack of consistent understanding of the meaning of robustness in electrical technology and I and C technology, in the nuclear plant engineering departments. The overall picture is that the robustness has worsened since the facilities were built. The Swedish nuclear power plants have an internal organizational structure with separated client and support organization. This splits the nuclear organization into two distinct parts which threaten to separate the two entities focus. Engineering departments at the Swedish nuclear power plants express a need for increased expertise in the client organization (blocks). Competence requested is for example, system knowledge to facilitate and enhance the quality of the initial analysis performed in the blocks. Suppliers receive more recently larger turnkey projects, both to minimize costs but also to minimize the interfaces and co-function problems. This, however, heightens demands for knowledge transfer between

  6. Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers

    International Nuclear Information System (INIS)

    DALE, R.N.

    2000-01-01

    Long Length Contaminated Equipment Removal System Receiver Trailer and Transport Trailer require a configuration management plan for design, requirements and operations baseline documents. This report serves as the plan for the Trailers

  7. Methods and equipments used in power reactors

    International Nuclear Information System (INIS)

    Beraha, R.; Delevallee, A.

    1976-01-01

    The various reactor γ fuel scanning facilities presently operating around the world are reviewed. Both equipments proposed by FRAMATOME are described: one is intended for scanning removable fuel pencils, and the other one for fuel assembly scanning [fr

  8. Nuclear power plant equipment design and construction rules

    International Nuclear Information System (INIS)

    Boiron, P.

    1983-03-01

    Presentation of the AFCEN (French association for nuclear power plant equipment design and construction rules) working, of its edition activity and of somes of its edited documents such as RCC-C (design and construction rules for PWR power plant fuel assemblies) and RCC-E (design and construction rules for nuclear facility electrical equipments) [fr

  9. Nuclear power equipment procurement management under EPC mode

    International Nuclear Information System (INIS)

    Shuai Yuezhi

    2014-01-01

    Nuclear power equipment procurement is one of the major constraints and management difficulties in the process of domestic nuclear power project construction for a long time. The construction of Hainan Changjiang Project can not meet the milestones due to the major equipment supply delay. Through the introduction to the organization and features of Changjiang project equipment procurement under EPC mode, and the main problems in the procurement process and its reason analysis, the purpose of this paper is to put forward ideas and suggestions of these items, i.e. selection of equipment suppliers, equipment localization, mass material design and procurement, complete system equipment supply, spare parts delivery and storage, owner process management, providing reference for follow-up projects. (author)

  10. Seismic qualification method of equipment for nuclear power plant

    International Nuclear Information System (INIS)

    Kim, J.S.; Choi, T.H.; Sulaimana, R.A.

    1995-01-01

    Safety related equipment installed in Korean Nuclear Power Plants are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Reg. Guide 1.100 Rev. 02 and IEEE Std. 344-1987. This paper defines and summarizes acceptable criteria and procedures, based on the Korean experience, for seismic qualification of purchased equipment to be installed in a nuclear power plant. As such the paper is intended to be a concise reference by equipment designers, architectural engineering company and plant owners in uniform implementation of commitments to nuclear regulatory agencies such as the USNRC or Korea Institute of Nuclear Safety (KINS) relating to adequacy of seismic Category 1 equipment. Thus, the paper provides the methodologies which can be used for qualifying equipment for safely related service in Nuclear Power Plants in a cost effective manner

  11. Quality assurance grading of conventional equipment at nuclear power station

    International Nuclear Information System (INIS)

    Li Ping; Li Shichang

    2006-01-01

    Equipment QA grading with the systematic and standardized approach will benefit the concerned organizations by effective allocating of limited resources to guarantee the quality of essential equipment. This paper presents a new quality assurance grading system for the convention systems/equipment of nuclear power station, which is operative and at the same time could help the owner to allot resource reasonably through the analysis of the purpose of grading and the experience and lessons of LINGAO Phase I project. (authors)

  12. Qualification of electric equipments for nuclear power plants

    International Nuclear Information System (INIS)

    Chauvin, G.; Raimondo, E.

    1983-03-01

    Description of the testing equipment, testing methods and standards of the resistance to seisms of electrical equipments (switches, pump motors, electrovalves, ...) for electronuclear power plants in France. Presentation of the French design and construction rules for electrical devices in the domestic and export nuclear market (resistance to thermodynamical and chemical stresses, to seisms, etc...) [fr

  13. Solids-based concentrated solar power receiver

    Science.gov (United States)

    None

    2018-04-10

    A concentrated solar power (CSP) system includes channels arranged to convey a flowing solids medium descending under gravity. The channels form a light-absorbing surface configured to absorb solar flux from a heliostat field. The channels may be independently supported, for example by suspension, and gaps between the channels are sized to accommodate thermal expansion. The light absorbing surface may be sloped so that the inside surfaces of the channels proximate to the light absorbing surface define downward-slanting channel floors, and the flowing solids medium flows along these floors. Baffles may be disposed inside the channels and oriented across the direction of descent of the flowing solids medium. The channels may include wedge-shaped walls forming the light-absorbing surface and defining multiple-reflection light paths for solar flux from the heliostat field incident on the light-absorbing surface.

  14. Power management in hydraulically actuated mobile equipment

    DEFF Research Database (Denmark)

    Pedersen, Henrik Clemmensen; Andersen, Torben Ole; Hansen, Michael Rygaard

    2008-01-01

    The focus of the current paper is on the control of hydraulic systems when utilizing the advances that electronic control may bring with regard to power management, prioritized flow sharing and anti-stall, arising from being able to control both pump, valves and engine electronically. A simple mo...

  15. The application of GIS equipment in nuclear power plant

    International Nuclear Information System (INIS)

    Ji Lin; Huang Pengbo; Chang Xin'ai

    2012-01-01

    In this paper, the advantage and disadvantage of gas insulated switchgear (GIS) in environmental adaptability, operation safety and economic benefit are analyzed. Issues concerning the manufacture, transportation, on-site installation, operation, maintenance and extension of GIS equipment are discussed. Comparing those characteristics with air insulated switchgear (AIS), GIS is characterized by better aseismic ability, less occupied area and installation process, lower fault rate, longer maintenance period, easier for extension and higher economic benefit, SF6 gas insures the operation safety and reliability of GIS equipment, modular transport and re-assembling improves the installation flexibility. Therefore, GIS equipment may be the first choice for the primary equipment of nuclear power plant. (authors)

  16. Conceptual design of advanced central receiver power systems sodium-cooled receiver concept. Volume 2, Book 2. Appendices. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-03-01

    The appendices include: (A) design data sheets and P and I drawing for 100-MWe commercial plant design, for all-sodium storage concept; (B) design data sheets and P and I drawing for 100-MWe commercial plant design, for air-rock bed storage concept; (C) electric power generating water-steam system P and I drawing and equipment list, 100-MWe commercial plant design; (D) design data sheets and P and I drawing for 281-MWe commercial plant design; (E) steam generator system conceptual design; (F) heat losses from solar receiver surface; (G) heat transfer and pressure drop for rock bed thermal storage; (H) a comparison of alternative ways of recovering the hydraulic head from the advanced solar receiver tower; (I) central receiver tower study; (J) a comparison of mechanical and electromagnetic sodium pumps; (K) pipe routing study of sodium downcomer; and (L) sodium-cooled advanced central receiver system simulation model. (WHK)

  17. Electrodynamic Wireless Power Transmission to Rotating Magnet Receivers

    International Nuclear Information System (INIS)

    Garraud, A; Jimenez, J D; Garraud, N; Arnold, D P

    2014-01-01

    This paper presents an approach for electrodynamic wireless power transmission (EWPT) using a synchronously rotating magnet located in a 3.2 cm 3 receiver. We demonstrate wireless power transmission up to 99 mW (power density equal to 31 mW/cm 3 ) over a 5-cm distance and 5 mW over a 20-cm distance. The maximum operational frequency, and hence maximal output power, is constrained by the magnetic field amplitude. A quadratic relationship is found between the maximal output power and the magnetic field. We also demonstrate simultaneous, power transmission to multiple receivers positioned at different locations

  18. Daya Bay Nuclear Power Station equipment reliability management system innovation

    International Nuclear Information System (INIS)

    Gao Ligang; Wang Zongjun

    2006-01-01

    Daya Bay Nuclear Power Station has achieved good performance since its commercial operation in 1994. The equipment reliability management system that features Daya Bay characteristics has been established through constant technology introduction, digestion and innovation. It is also based on the success of operational system, equipment maintenance system and technical support system. The system lays a solid foundation for the long-term safe operation of power station. This article emphasizes on the innovation part of equipment reliability management system in Daya Bay. (authors)

  19. Earthquake protection of nuclear power plant equipment

    Energy Technology Data Exchange (ETDEWEB)

    Nawrotzki, Peter [GERB Vibration Control Systems, Berlin (Germany)

    2010-05-15

    Power plant machinery can be dynamically decoupled from the substructure by the effective use of helical steel springs and viscous dampers. Turbine foundations, boiler feed pumps and other machine foundations benefit from this type of elastic support systems to mitigate the transmission of operational vibration. The application of these devices may also be used to protect against earthquakes and other catastrophic events, i.e. airplane crash, of particular importance in nuclear facilities. This article illustrates basic principles of elastic support systems and applications on power plant buildings in medium and high seismic areas. Spring-damper combinations with special stiffness properties are used to reduce seismic acceleration levels of turbine components and other safety or non-safety related structures. For turbine buildings, the integration of the turbine substructure into the machine building can further reduce stress levels in all structural members. (orig.)

  20. Earthquake protection of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Nawrotzki, Peter

    2010-01-01

    Power plant machinery can be dynamically decoupled from the substructure by the effective use of helical steel springs and viscous dampers. Turbine foundations, boiler feed pumps and other machine foundations benefit from this type of elastic support systems to mitigate the transmission of operational vibration. The application of these devices may also be used to protect against earthquakes and other catastrophic events, i.e. airplane crash, of particular importance in nuclear facilities. This article illustrates basic principles of elastic support systems and applications on power plant buildings in medium and high seismic areas. Spring-damper combinations with special stiffness properties are used to reduce seismic acceleration levels of turbine components and other safety or non-safety related structures. For turbine buildings, the integration of the turbine substructure into the machine building can further reduce stress levels in all structural members. (orig.)

  1. Construction and assembling optimization of power equipment

    Directory of Open Access Journals (Sweden)

    Marius Groza

    2005-10-01

    Full Text Available The main purpose of this paper is to elaborate a calculation program in Pascal language, using Delphi environment. This calculation program is designed to solve the power engineering optimization problems using the critical path method. For illustrating the use of the algorithm and the calculation program we propose an application from power engineering: a 400 kV electrical overhead line section realization. This paper is structured in 4 parts. In the first part of the paper we present the application as a problem of critic path. In the second part of the paper, we determine the critic path in a program graph and time reserves. In the third part of the paper we present a representative numerical application. In the fourth part of the paper it is described the calculation program.

  2. A proposal of nuclear fusion power plant equipped with SMES

    International Nuclear Information System (INIS)

    Natsukawa, Tatsuya; Makamura, Hirokazu; Molinas, Marta; Nomura, Shinichi; Tsuji-Iio, Shunji; Shimada, Ryuichi

    2000-01-01

    When we intend to operate the nuclear fusion power plant (NFPP) under the economically efficient conditions as an independent power plant, it is desirable that the generated electric power should be sent to network according to the power demand. With such strategy being expanded, some energy storage system is available. In this paper, NFPP equipped with the superconducting magnetic energy storage system (SMES) as electric power storage device is proposed. The advantages of NFPP equipped with SMES are discussed and a case study of 500 MW NFPP equipped with 6 GWh SMES is done with estimating its operational value. For SMES coil, the concept of Force Balanced Coil (FBC) is applied and 6 GWh class FBC is briefly designed

  3. Reliability of nuclear power plants and equipment

    International Nuclear Information System (INIS)

    1985-01-01

    The standard sets the general principles, a list of reliability indexes and demands on their selection. Reliability indexes of nuclear power plants include the simple indexes of fail-safe operation, life and maintainability, and of storage capability. All terms and notions are explained and methods of evaluating the indexes briefly listed - statistical, and calculation experimental. The dates when the standard comes in force in the individual CMEA countries are given. (M.D.)

  4. Method for keeping equipment and pipeline of nuclear power plant

    International Nuclear Information System (INIS)

    Okubo, Osamu.

    1990-01-01

    The present invention intends to suppress corrosion of equipments and pipelines in condensate, feedwater and feedwater heater drain systems during operation of a nuclear power plant. That is, condensate, feedwater and drain remained in equipments and pipelines just after the stopping of operation are passed through pipelines comprising only conduits, or they are introduced to a condensator passing through the pipelines and condensate pipes. Further, the remaining droplets on the inner surfaces are evaporated by the remaining heat of the equipments and the pipelines themselves. Then, the equipments and pipelines are isolated from other regions and kept. In view of the above, since condensate, feedwater and water feeder drains are introduced directly to the condensator passing through the conduits in which other equipments such as tanks and pumps are not present and are isolated and kept, corrosion of the equipments and the pipelines is suppressed and radioactive contamination is suppressed from prevailing by way of cruds. (I.S.)

  5. Problems in diagnosing and forecasting power equipment reliability

    Energy Technology Data Exchange (ETDEWEB)

    Popkov, V I; Demirchyan, K S

    1979-11-01

    This general survey deals with approaches to the resolution of such problems as the gathering, analysis and systematization of data on component defects in power equipment and setting up feedback with the manufacturing plants and planning organizations to improve equipment reliability. Such efforts on the part of designers, manufacturers and operating and repair organizations in analyzing faults in 300 MW turbogenerators during 1974-1977 reduced the specific fault rate by 20 to 25% and the downtime per failure by 35 to 40%. Since power equipment should operate for several hundreds of thousands of hours (20 to 30 years) and the majority of power components have guaranteed service lives of no more than 10/sup 5/ hours, an extremely difficult problem is the determination of the reliability of equipment past the 10/sup 5/ point. The present trend in the USSR Unified Power System towards increasing the number of shutdowns and startups, which in the case of turbogenerators of up 1200 MW power can reach 7500 to 10,000 cycles is noted. Other areas briefly treated are: MHD generator reliability and economy; nuclear power plant reliability and safety; the reliability of high-power high-voltage thyristor converters; the difficulties involved in scale modeling of power system reliability and the high cost of the requisite full-scale studies; the poor understanding of long term corrosion and erosion processes. The review concludes with arguments in favor of greater computerization of all aspects of power system management.

  6. Engineering electrodynamics electric machine, transformer, and power equipment design

    CERN Document Server

    Turowski, Janusz

    2013-01-01

    Due to a huge concentration of electromagnetic fields and eddy currents, large power equipment and systems are prone to crushing forces, overheating, and overloading. Luckily, power failures due to disturbances like these can be predicted and/or prevented.Based on the success of internationally acclaimed computer programs, such as the authors' own RNM-3D, Engineering Electrodynamics: Electric Machine, Transformer, and Power Equipment Design explains how to implement industry-proven modeling and design techniques to solve complex electromagnetic phenomena. Considering recent progress in magneti

  7. Application of Equipment Monitoring Technology in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kang, H. T.; Lee, J. K.; Lee, K. D.; Jo, S. H.

    2012-01-01

    The major goal of nuclear power industries during the past 10 years is to increase reliability and utility capacity factor. As the capacitor factor, however, crept upward. it became harder to attain next percentage of improvement. Therefore other innovative technologies are required. By the technologies applied to the fossil power plants, equipment health monitoring was performed on equipment to maintain it in operable condition and contributed on improving their reliability a lot. But the equipment monitoring may be limited to the observation of current system states in nuclear power plant. Monitoring of current system states is being augmented with prediction of future operating states and predictive diagnosis of future failure states. Such predictive diagnosis is motivated by the need for nuclear power plants to optimize equipment performance and reduce costs and unscheduled downtime. This paper reviews the application of techniques that focus on improving reliability in nuclear power plant by monitoring and predicting equipment health and suggests how possible to support on-line monitoring

  8. Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program

    International Nuclear Information System (INIS)

    McGuire, L.L.

    1991-01-01

    The Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program serves two purposes. The first is to track temperature trends during normal plant operation in areas where suspected deviations from established environmental profiles exist. This includes the use of Resistance Temperature Detectors, Recorders, and Temperature Dots for evaluation of equipment qualified life for comparison with tested parameters and the established Environmental Design Profile. It also may be used to determine the location and duration of steam leaks for effect on equipment qualified life. The second purpose of this program is to aid HVAC design engineers in determining the source of heat outside anticipated design parameters. Resistance Temperature Detectors, Recorders, and Temperature Dots are also used for this application but the results may include design changes to eliminate the excess heat or provide qualified equipment (cable) to withstand the elevated temperature, splitting of environmental zones to capture accurate temperature parameters, or continued environmental monitoring for evaluation of equipment located in hot spots

  9. Discussion of mechanical design for pressured cavity-air-receiver in solar power tower system

    Energy Technology Data Exchange (ETDEWEB)

    Fan, Zhilin; Zhang, Yaoming; Liu, Deyou; Wang, Jun; Liu, Wei [Hohai Univ., Nanjing (China). New Materials and Energy Sources Research and Exploitation Inst.

    2008-07-01

    In 2005, Hohai university and Nanjing Chunhui science and technology Ltd. of China, cooperating with Weizmann Institute of Science and EDIG Ltd. of Israel, built up a 70kWe solar power tower test plant in Nanjing, Jiangsu province, China, which was regarded as the first demonstration project to demonstrate the feasibility of solar power tower system in China. The system consists of heliostats field providing concentrated sunlight, a solar tower with a height of 33 meter, a pressured cavity-air-receiver transforming solar energy to thermal energy, a modified gas turbine adapting to solar power system, natural gas subsystem for solar-hybrid generation, cooling water subsystem for receiver and CPC, controlling subsystem for whole plant, et al. In this system, air acts as actuating medium and the system works in Brayton cycle. Testing results show that solar power tower system is feasible in China. To promote the development of solar powered gas turbine system and the pressured cavity-air-receiver technology in China, it is necessary to study the mechanical design for pressured Cavity-air-receiver. Mechanical design of pressured cavity-air-receiver is underway and some tentative principles for pressured cavity-air-receiver design, involving in power matching, thermal efficiency, material choosing, and equipment security and machining ability, are presented. At the same time, simplified method and process adapted to engineering application for the mechanical design of pressured cavity-air-receiver are discussed too. Furthermore, some design parameters and appearance of a test sample of pressured cavity-air-receiver designed in this way is shown. It is appealed that, in China, the research in this field should be intensified and independent knowledge patents for pivotal technological equipments such as receiver in solar power tower system should be formed. (orig.)

  10. Watt-level wireless power transmission to multiple compact receivers

    International Nuclear Information System (INIS)

    Garraud, A; Munzer, D J; Althar, M; Garraud, N; Arnold, D P

    2015-01-01

    This paper reports an electrodynamic wireless power transmission (EWPT) system using a low-frequency (300 Hz) magnetic field to transmit watt-scale power levels to multiple compact receivers. As compared to inductively or resonantly coupled coils, EWPT facilitates transmission to multiple non-interacting receivers with little restriction on their orientation. A single 3.0 cm 3 receiver achieves 1.25 W power transmission with 8% efficiency at a distance of 1 cm (350 mW/cm 3 power density) from the transmitter. The same prototype achieves 9 mW at a distance of 9 cm. Moreover, we demonstrate simultaneous recharge of two wearable devices, using two receivers located in arbitrary positions and orientations. (paper)

  11. Hybrid solar central receiver for combined cycle power plant

    Science.gov (United States)

    Bharathan, Desikan; Bohn, Mark S.; Williams, Thomas A.

    1995-01-01

    A hybrid combined cycle power plant including a solar central receiver for receiving solar radiation and converting it to thermal energy. The power plant includes a molten salt heat transfer medium for transferring the thermal energy to an air heater. The air heater uses the thermal energy to preheat the air from the compressor of the gas cycle. The exhaust gases from the gas cycle are directed to a steam turbine for additional energy production.

  12. Power-Consumption Measurements for LTE User Equipment

    DEFF Research Database (Denmark)

    Lauridsen, Mads

    wireless communications test set and the Agilent N6705B DC power analyzer to establish a power consumption model for LTE user equipment (UE). The model is useful when you need to examine the UE battery life in system-level simulations. We will explain how the Agilent equipment can be used in manual tests......, but we do not discuss how to make automated tests (for example, using VEE software). In this application note, we analyze smartphones adhering to the 3GPP LTE standard [1]....

  13. ASTRID© - Advanced Solar Tubular ReceIver Design: A powerful tool for receiver design and optimization

    Science.gov (United States)

    Frantz, Cathy; Fritsch, Andreas; Uhlig, Ralf

    2017-06-01

    In solar tower power plants the receiver is one of the critical components. It converts the solar radiation into heat and must withstand high heat flux densities and high daily or even hourly gradients (due to passage of clouds). For this reason, the challenge during receiver design is to find a reasonable compromise between receiver efficiency, reliability, lifetime and cost. There is a strong interaction between the heliostat field, the receiver and the heat transfer fluid. Therefore, a proper receiver design needs to consider these components within the receiver optimization. There are several design and optimization tools for receivers, but most of them focus only on the receiver, ignoring the heliostat field and other parts of the plant. During the last years DLR developed the ASTRIDcode for tubular receiver concept simulation. The code comprises both a high and a low-detail model. The low-detail model utilizes a number of simplifications which allow the user to screen a high number of receiver concepts for optimization purposes. The high-detail model uses a FE model and is able to compute local absorber and salt temperatures with high accuracy. One key strength of the ASTRIDcode is its interface to a ray tracing software which simulates a realistic heat flux distributions on the receiver surface. The results generated by the ASTRIDcode have been validated by CFD simulations and measurement data.

  14. Seismic fragility levels of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.; Hofmayer, C.H.

    1987-01-01

    Seismic fragility levels of safety-related electrical and mechanical equipment used in nuclear power plants are discussed. The fragility level is defined as the vibration level corresponding to initiation of equipment malfunctions. The test response spectrum is used as a measure of this vibration level. The fragility phenomenon of an equipment is represented by a number of response spectra corresponding to various failure modes. Analysis methods are described for determination of the fragility level by use of existing test data. Useful conversion factors are tabulated to transform test response spectra from one damping value to another. Results are presented for switch-gears and motor control centers. The capacity levels of these equipment assemblies are observed to be limited by malfunctioning of contactors, motor starters, relays and/or switches. The applicability of the fragility levels, determined in terms of test response spectra, to Seismic Margin Studies and Probabilistic Risk Assessments is discussed and specific recommendations are provided

  15. 47 CFR 76.923 - Rates for equipment and installation used to receive the basic service tier.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Rates for equipment and installation used to... § 76.923 Rates for equipment and installation used to receive the basic service tier. (a) Scope. (1... control units; and (iii) Inside wiring. (2) Subscriber charges for such equipment shall not exceed charges...

  16. Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

    International Nuclear Information System (INIS)

    DALE, R.N.

    2000-01-01

    A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O and M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085

  17. Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

    Energy Technology Data Exchange (ETDEWEB)

    DALE, R.N.

    2000-05-01

    A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O & M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085.

  18. Design of equipment management information system for nuclear power plant

    International Nuclear Information System (INIS)

    Wang Chengyuan

    1996-01-01

    The author describes the ideas and practical method for need analysis, system function dividing, code design, program design and network disposition of equipment purchase management system of nuclear power plant during building, from the view of engineering investment control, schedule control and quality control

  19. Dependence and power in healthcare equipment supply chains.

    Science.gov (United States)

    de Jong, Jurriaan L; Benton, W C

    2018-03-05

    Most healthcare organizations (HCOs) engage Group Purchasing Organizations (GPOs) as an outsourcing strategy to secure their supplies and materials. When an HCO outsources the procurement function to a GPO, this GPO will directly interact with the HCO's supplier on the HCO's behalf. This study investigates how an HCO's dependence on a GPO affects supply chain relationships and power in the healthcare medical equipment supply chain. Hypotheses are tested through factor analysis and structural equation modeling, using primary survey data from HCO procurement managers. An HCO's dependence on a GPO is found to be positively associated with a GPO's reliance on mediated power, but, surprisingly, negatively associated with a GPO's mediated power. Furthermore, analysis indicates that an HCO's dependence on a GPO is positively associated with an HCO's dependence on a GPO-contracted Original Equipment Manufacturer (OEM). HCO reliance on GPOs may lead to a buyer's dependence trap, where HCOs are increasingly dependent on GPOs and OEMs. Implications for HCO procurement managers and recommended steps for mitigation are offered. Power-dependence relationships in the medical equipment supply chain are not consistent with relationships in other, more traditional, supply chains. While dependence in a supply chain relationship typically leads to an increase in reliance on mediated power, GPO-dependent HCOs instead perceive a decrease in GPO mediated power. Furthermore, HCOs that rely on procurement service from GPOs are increasingly dependent on the OEMs.

  20. Efficiency improvement of technological preparation of power equipment manufacturing

    Science.gov (United States)

    Milukov, I. A.; Rogalev, A. N.; Sokolov, V. P.; Shevchenko, I. V.

    2017-11-01

    Competitiveness of power equipment primarily depends on speeding-up the development and mastering of new equipment samples and technologies, enhancement of organisation and management of design, manufacturing and operation. Actual political, technological and economic conditions cause the acute need in changing the strategy and tactics of process planning. At that the issues of maintenance of equipment with simultaneous improvement of its efficiency and compatibility to domestically produced components are considering. In order to solve these problems, using the systems of computer-aided process planning for process design at all stages of power equipment life cycle is economically viable. Computer-aided process planning is developed for the purpose of improvement of process planning by using mathematical methods and optimisation of design and management processes on the basis of CALS technologies, which allows for simultaneous process design, process planning organisation and management based on mathematical and physical modelling of interrelated design objects and production system. An integration of computer-aided systems providing the interaction of informative and material processes at all stages of product life cycle is proposed as effective solution to the challenges in new equipment design and process planning.

  1. Electrodynamic wireless power transmission to a torsional receiver

    International Nuclear Information System (INIS)

    McEachern, K M; Arnold, D P

    2013-01-01

    This paper presents a wireless power transmission (WPT) concept that uses electrodynamic coupling and torsional motion of a permanent magnet in the receiver. The system is shown to transfer an average power of 3.09 mW (power density equal to 143 μW/cm 3 ) over a distance of 1 cm, an average power of 1.98 mW over a distance of 2 cm, and an average power of 126 μW over a distance of 7 cm. We also demonstrate unaltered power transmission through conductive media, including a human hand and an aluminum plate, highlighting a key advantage of the electrodynamic wireless power transmission approach

  2. Communications received from Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1994-04-01

    The Director General has received notes verbales to the export of nuclear material, equipment and technology from the following Permanent Missions to the International Atomic Energy Agency: notes verbales dated 1 March 1994 from the Permanent Missions of Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Hungary, Italy, Japan, the Netherlands, Poland, Portugal, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, the United States of America; and a note verbale dated 12 March 1994 from the Permanent Mission of Romania. The purpose of these notes verbales is to provide further information on these Governments' nuclear export policies and practices

  3. Automatization of welding for nuclear power equipments and facilities

    International Nuclear Information System (INIS)

    Tamai, Yasumasa; Matsumoto, Teruo; Koyama, Takaichi

    1980-01-01

    For the requirement of high reliability in the construction of nuclear power plants and the reduction of radiation exposure in the modefying works of existing plants, the automation and remote operation of welding have increased their necessity. In this paper, the present state of the automation of welding for making machines, equipments and pipings for nuclear power plants in Hitachi Ltd. is described, and the aim of developing the automation, the features of the equipments and the state of application to actual plants are introduced, centering around the automation of welding for large structures such as reactor containment vessels and the remote type automatic welding system for pipings. By these automations, the large outcomes were obtained in the improvement of welding quality required for the machines and equipments for atomic energy. Moreover, the conspicuous results were also obtained in case of the peculiar works to nuclear power plants, in which the reduction of the radiation exposure related to human bodies and the welding of high quality are demanded. The present state of the automation of welding for nuclear installations in Hitachi Ltd., the development of automatic welding equipments and the present state of application to actual plants, and the development and application of the automatic pipe working machine for reducing radiation exposure are explained. (Kako, I.)

  4. Wake-up receiver based ultra-low-power WBAN

    CERN Document Server

    Lont, Maarten; Roermund, Arthur van

    2014-01-01

    This book presents the cross-layer design and optimization of wake-up receivers for wireless body area networks (WBAN), with an emphasis on low-power circuit design. This includes the analysis of medium access control (MAC) protocols, mixer-first receiver design, and implications of receiver impairments on wideband frequency-shift-keying (FSK) receivers. Readers will learn how the overall power consumption is reduced by exploiting the characteristics of body area networks. Theoretical models presented are validated with two different receiver implementations, in 90nm and 40nm CMOS technology.   • Provides an overview of wireless body area network design from the network layer to the circuit implementation, and an overview of the cross-layer design trade-offs; • Discusses design at both the network or MAC-layer and circuit-level, with an emphasis on circuit design; • Covers the design of low-power frequency shift keying (FSK) wake-up-receivers; • Validates theory presented with two different recei...

  5. Assessment of electrical equipment aging for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The electrical and instrumentation equipments, especially whose parts are made of polymer material, are gradually degraded by thermal and radiation environment in the normal operation, and the degradation is thought to progress rapidly when they are exposed to the environment of the design basis event (DBE). The integrity of the equipments is evaluated by the environmental qualification (EQ) test simulating the environment of the normal operation and the DBE. The project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) indicated the importance of applying simultaneous thermal and radiation aging for simulating the aging in normal operation. The project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008 to apply the outcome of ACA to the other electrical and instrumentation equipment and to establish an advanced EQ test method that can appropriately simulate the environment in actual plants. In FY2012, aging characteristics of thermal aging and simultaneous aging were obtained for the epoxy resin of electrical penetrations and the O-ring of connectors. Physical property measurement was carried out for epoxy resin of electrical penetration subject to the type testing in FY2010. (author)

  6. Assessment of electrical equipment aging for nuclear power plant

    International Nuclear Information System (INIS)

    2013-01-01

    The electrical and instrumentation equipments, especially whose parts are made of polymer material, are gradually degraded by thermal and radiation environment in the normal operation, and the degradation is thought to progress rapidly when they are exposed to the environment of the design basis event (DBE). The integrity of the equipments is evaluated by the environmental qualification (EQ) test simulating the environment of the normal operation and the DBE. The project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) indicated the importance of applying simultaneous thermal and radiation aging for simulating the aging in normal operation. The project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008 to apply the outcome of ACA to the other electrical and instrumentation equipment and to establish an advanced EQ test method that can appropriately simulate the environment in actual plants. In FY2012, aging characteristics of thermal aging and simultaneous aging were obtained for the epoxy resin of electrical penetrations and the O-ring of connectors. Physical property measurement was carried out for epoxy resin of electrical penetration subject to the type testing in FY2010. (author)

  7. Advanced Receiver/Converter Experiments for Laser Wireless Power Transmission

    Science.gov (United States)

    Howell, Joe T.; ONeill, Mark; Fork, Richard

    2004-01-01

    For several years NASA Marshall Space Flight Center, UAH and ENTECH have been working on various aspects of space solar power systems. The current activity was just begun in January 2004 to further develop this new photovoltaic concentrator laser receiver/converter technology. During the next few months, an improved prototype will be designed, fabricated, and thoroughly tested under laser illumination. The final paper will describe the new concept, present its advantages over other laser receiver/converter approaches (including planar photovoltaic arrays), and provide the latest experiment results on prototype hardware (including the effects of laser irradiance level and cell temperature). With NASA's new human exploration plans to first return to the Moon, and then to proceed to Mars, the new photovoltaic concentrator laser receiver/converter technology could prove to be extremely useful in providing power to the landing sites and other phases of the missions. For example, to explore the scientifically interesting and likely resource-rich poles of the Moon (which may contain water) or the poles of Mars (which definitely contain water and carbon dioxide), laser power beaming could represent the simplest means of providing power to these regions, which receive little or no sunlight, making solar arrays useless there. In summary, the authors propose a paper on definition and experimental results of a novel photovoltaic concentrator approach for collecting and converting laser radiation to electrical power. The new advanced photovoltaic concentrator laser receiver/converter offers higher performance, lighter weight, and lower cost than competing concepts, and early experimental results are confirming the expected excellent Performance levels. After the small prototypes are successfully demonstrated, a larger array with even better performance is planned for the next phase experiments and demonstrations. Thereafter, a near-term flight experiment of the new technology

  8. Development of remote automatic equipment for BWR power plants

    International Nuclear Information System (INIS)

    Sasaki, Masayoshi

    1984-01-01

    The development of remote control, automatic equipment for nuclear power stations has been promoted to raise the rate of operation of plants by shortening regular inspection period, to improve the safety and reliability of inspection and maintenance works by mechanization, to reduce the radiation exposure dose of workers and to reduce the manpower required for works. The taking-off of control rod drives from reactors and fixing again have been mechanized, but the disassembling, cleaning, inspection and assembling of control rod drives are manually carried out. Therefore, Hitachi Ltd. has exerted effort to develop the automatic equipment for this purpose. The target of development, investigation, the construction and function of the equipment, the performance and the effect of adopting it are reported. The equipment for the volume reduction of spent fuel channel boxes and spent control rods is developed since these are major high level radioactive solid wastes, and their apparent volume is large. Also the target of development, investigated things, the construction and function of the equipment, the performance and the effect of adopting it are reported. (Kako, I.)

  9. Maintenance of fire systems and equipment at Virginia Power

    International Nuclear Information System (INIS)

    Doubrely, E.B. Jr.

    1989-01-01

    The basics of fire protection systems maintenance are well codified and documented in the National Fire Codes published by the National Fire Protection Association. In addition, Insurers often promulgate minimum standards for fire protection systems design and maintenance to which they attach conditions of insurability. Regulatory agencies and even in-house corporate policies can impact the maintenance of fire protection systems and equipment. This presentation will focus on the various methods and alternate ways of performing system maintenance, whether required by code, insurer, or by some regulatory commitment at Virginia Powers North Anna and Surry nuclear power stations. The approach to performing similar work is handled differently at each station. This difference can be attributed to proximity to outside assistance as well as plant philosophy. In addition to station maintenance practices, a discussion of in-house servicing of portable fire suppression equipment is offered. 1 tab

  10. Decommissioning and equipment replacement of nuclear power plants under uncertainty

    International Nuclear Information System (INIS)

    Takashima, Ryuta; Naito, Yuta; Kimura, Hiroshi; Madarame, Haruki

    2007-01-01

    This study examines the optimal timing for the decommissioning and equipment replacement of nuclear power plants. We consider that the firm has two options of decommissioning and equipment replacement, and determines to exercise these options under electricity price uncertainty. This problem is formulated as two optimal stopping problems. The solution of this model provides the value of the nuclear power plant and the threshold values for decommissioning and replacement. The dependence of decommissioning and replacement strategies on uncertainty and each cost is shown. In order to investigate the probability of events for decommissioning and replacement, Monte Carlo calculations are performed. We also show the probability distribution and the conditional expected time for each event. (author)

  11. After-hours Power Status of Office Equipment and Inventory of Miscellaneous Plug-load Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Roberson, Judy A.; Webber, Carrie A.; McWhinney, Marla C.; Brown, Richard E.; Pinckard, Margaret J.; Busch, John F.

    2004-01-22

    This research was conducted in support of two branches of the EPA ENERGY STAR program, whose overall goal is to reduce, through voluntary market-based means, the amount of carbon dioxide emitted in the U.S. The primary objective was to collect data for the ENERGY STAR Office Equipment program on the after-hours power state of computers, monitors, printers, copiers, scanners, fax machines, and multi-function devices. We also collected data for the ENERGY STAR Commercial Buildings branch on the types and amounts of ''miscellaneous'' plug-load equipment, a significant and growing end use that is not usually accounted for by building energy managers. This data set is the first of its kind that we know of, and is an important first step in characterizing miscellaneous plug loads in commercial buildings. The main purpose of this study is to supplement and update previous data we collected on the extent to which electronic office equipment is turned off or automatically enters a low power state when not in active use. In addition, it provides data on numbers and types of office equipment, and helps identify trends in office equipment usage patterns. These data improve our estimates of typical unit energy consumption and savings for each equipment type, and enables the ENERGY STAR Office Equipment program to focus future effort on products with the highest energy savings potential. This study expands our previous sample of office buildings in California and Washington DC to include education and health care facilities, and buildings in other states. We report data from twelve commercial buildings in California, Georgia, and Pennsylvania: two health care buildings, two large offices (> 500 employees each), three medium offices (50-500 employees), four education buildings, and one ''small office'' that is actually an aggregate of five small businesses. Two buildings are in the San Francisco Bay area of California, five are in

  12. A Digital Power Quality Monitoring Equipment Designed for Digital Substation

    Science.gov (United States)

    Li, Wei; Wang, Xin; Geng, Jiewen

    2018-01-01

    Taking into account both current status and development trend of digital substation, this paper proposed a design of a new multi-channelled digital power quality monitoring equipment with high compatibility. The overall functional structure, hardware architecture, software architecture, interface architecture and some key techniques such as IEC 61850 modelling of transient event and harmonic measurement method under the condition of non-synchronous sampling are described in this paper.

  13. Nuclear power plants. Electrical equipment of the safety system. Qualification

    International Nuclear Information System (INIS)

    2001-01-01

    This International Standard applies to electrical parts of safety systems employed at nuclear power plants, including components and equipment of any interface whose failure could affect unfavourably properties of the safety system. The standard also applies to non-electrical safety-related interfaces. Furthermore, the standard describes the generic process of qualification certification procedures and methods of qualification testing and related documentation. (P.A.)

  14. A heat receiver design for solar dynamic space power systems

    Science.gov (United States)

    Baker, Karl W.; Dustin, Miles O.; Crane, Roger

    1990-01-01

    An advanced heat pipe receiver designed for a solar dynamic space power system is described. The power system consists of a solar concentrator, solar heat receiver, Stirling heat engine, linear alternator and waste heat radiator. The solar concentrator focuses the sun's energy into a heat receiver. The engine and alternator convert a portion of this energy to electric power and the remaining heat is rejected by a waste heat radiator. Primary liquid metal heat pipes transport heat energy to the Stirling engine. Thermal energy storage allows this power system to operate during the shade portion of an orbit. Lithium fluoride/calcium fluoride eutectic is the thermal energy storage material. Thermal energy storage canisters are attached to the midsection of each heat pipe. The primary heat pipes pass through a secondary vapor cavity heat pipe near the engine and receiver interface. The secondary vapor cavity heat pipe serves three important functions. First, it smooths out hot spots in the solar cavity and provides even distribution of heat to the engine. Second, the event of a heat pipe failure, the secondary heat pipe cavity can efficiently transfer heat from other operating primary heat pipes to the engine heat exchanger of the defunct heat pipe. Third, the secondary heat pipe vapor cavity reduces temperature drops caused by heat flow into the engine. This unique design provides a high level of reliability and performance.

  15. Designing a power supply for Nim-bin formatted equipment

    International Nuclear Information System (INIS)

    Banuelos G, L. E.; Hernandez D, V. M.; Vega C, H. R.

    2016-09-01

    From an old Nuclear Chicago power supply that was practically in the trash, was able to recover the 19 inches casing, rear connectors and the housing where the circuits were. From here all mechanical parts were cleaned and the electronic design was started to replace the original voltage and current functions of this equipment. The cards for the ±6, ±12 and ±24 voltages were designed, simulated and tested with circuitry that does not rely on specialized components or that is sold only by the equipment manufacturer. In the handling of the current by each voltage to operate, was possible to tie with the specifications of the manufacturers like Ortec or Canberra where a model of power supply gives a power of 160 Watts. Basic tests were performed to show that the behavior is very similar to commercial equipment; such as the full load regulation index and the noise level in the supply voltages. So our Nim-bin voltage source is viable for use in our institution laboratories. (Author)

  16. 30 CFR 77.500 - Electric power circuits and electric equipment; deenergization.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Electric power circuits and electric equipment... OF UNDERGROUND COAL MINES Electrical Equipment-General § 77.500 Electric power circuits and electric equipment; deenergization. Power circuits and electric equipment shall be deenergized before work is done on...

  17. Financing future exports of Canada's electrical power equipment industry

    International Nuclear Information System (INIS)

    Hay, K.A.J.; Saravanamuttoo, C.A.

    1992-01-01

    The economic impact on the Canadian power sector of continued constraints on the availability of concessionary export financing is examined. An overview of the structure of the Canadian electrical power equipment industry is provided, followed by a discussion of its competitiveness and performance. Export prospects are outlined and separate reviews are presented of hydroelectric and thermal expansion. A global market of US $17 billion for hydroelectric power in the 1990s is forecast, and a market of US $300 billion for all forms of power generation in developing Asia. The export strategies of international competitive bidding, forming a consortium within an international multinational enterprise, co-financing with Japanese aid agencies, and direct negotiation are discussed. The costs and benefits of concessional financing are assessed and shown to bring net fiscal benefits. 12 refs., 2 tabs

  18. Heat receivers for solar dynamic space power systems

    Science.gov (United States)

    Perez-Davis, Marla Esther

    A review of state-of-the-art technology is presented and discussed for phase change materials. Some of the advanced solar dynamic designs developed as part of the Advanced Heat Receiver Conceptual Design Study performed for LeRC are discussed. The heat receivers are analyzed and several recommendations are proposed, including two new concepts. The first concept evaluated the effect of tube geometries inside the heat receiver. It was found that a triangular configuration would provide better heat transfer to the working fluid, although not necessarily with a reduction in receiver size. A sensible heat receiver considered in this study uses vapor grown graphite fiber-carbon (VGCF/C) composite as the thermal storage media and was designed for a 7 kW Brayton engine. The proposed heat receiver stores the required energy to power the system during eclipse in the VGCF/C composite. The heat receiver analysis was conducted through the Systems Improved Numerical Differencing Analyzer and Fluid Integrator (SINDA) software package. The proposed heat receiver compares well with other latent and advanced sensible heat receivers while avoiding the problems associated with latent heat storage salts and liquid metal heat pipes. The weight and size of the system can be optimized by changes in geometry and technology advances for this new material. In addition to the new concepts, the effect of atomic oxygen on several materials is reviewed. A test was conducted for atomic oxygen attack on boron nitride, which experienced a negligible mass loss when exposed to an atomic oxygen fluence of 5 x 10 exp 21 atoms/sq cm. This material could be used to substitute the graphite aperture plate of the heat receiver.

  19. Communication Received from Argentina regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    1993-10-01

    The Director General has received letters dated 27 May 1993 from the Resident Representatives of Portugal and Spain to the Agency concerning the export of nuclear material and of certain categories of equipment and other material [ru

  20. Communications received from Members regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    1993-10-01

    The Director General has received letters dated 27 May 1993 from the Resident Representatives of Portugal and Spain to the Agency concerning the export of nuclear material and of certain categories of equipment and other material [es

  1. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment or technology

    International Nuclear Information System (INIS)

    1988-11-01

    The document reproduces the text of a Note Verbale dated 20 October 1988 received by the IAEA Director General from the Permanent Mission of Spain relating to the export of nuclear material, equipment or technology

  2. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment or technology

    International Nuclear Information System (INIS)

    1990-08-01

    The document reproduces the text of the Note Verbale dated 1 August 1990 received by the Director General of the IAEA from the Permanent Mission of Romania and relating to the export of nuclear material, equipment and technology

  3. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1992-01-01

    The document reproduces the text of the Note Verbale dated 18 December 1991 received by the Director General of the IAEA from the Permanent Mission of Austria and relating to the export of nuclear material, equipment and technology

  4. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1993-01-01

    The document reproduces the Note Verbale dated 2 December 1992 received by the Director General from the Resident Representative of Argentina to the Agency relating to the export of nuclear material, equipment or technology, in order to provide information on that Government's Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material and related Technology

  5. Power/response spectrum transformations in equipment qualification

    International Nuclear Information System (INIS)

    Unruh, J.F.; Kana, D.D.

    1985-01-01

    Since its introduction a few years ago the use of the power/response spectrum transformation has gained considerable interest and acceptance, and a number of new applications of the transformation have been developed in the equipment qualification area. A brief review of the power/response spectrum transformation is given with a discussion of the input/output relationships for linear systems required for elevated power spectrum generation. Frequency content of earthquakelike signals is discussed with emphasis on the resolution given by the PSD. The problem of excessive ZPA due to inconsistent spectra enveloping and mechanical nonlinearities is also discussed. The PSD/RS transformation is applied to the problems of combining various dynamic load events, developing bounding spectra, and developing damping consistent test spectra. Development of elevated component spectra corrected for base overtest and generation from in-situ measurements is reviewed

  6. Overview of nuclear power plant equipment qualification issues and practices

    International Nuclear Information System (INIS)

    Torr, K.G.

    1989-01-01

    This report presents a view of and commentary on the current status of equipment qualification (EQ) in nuclear industries of the major western nations. The introductory chapters discuss the concepts of EQ, the elements of EQ process and highlight some of the key issues in EQ. A brief review of industry practices and some of the prevalent industrial standards is presented, followed by an overview of current regulatory positions in the USA, France, Germany and Sweden. A summary and commentary on the latest research findings on issues relating to accident simulation, to aging simulation and some special topics related to EQ, has been contributed by Franklin Research Centre of Philadelphia. The last part of the report deals with equipment qualification in Canada and gives recommendations on EQ for new plants as well as currently operational CANDU nuclear power plants

  7. Review of foreign equipment for powered support control

    Energy Technology Data Exchange (ETDEWEB)

    Sikora, W; Sobczyk, J

    1986-10-01

    A new generation of control systems are comparatively evaluated developed by Dowty, Hemscheidt and Thyssen-Siemens for powered supports and shield supports. Types of functions controlled by each system are discussed: support advancing (lowering support canopy, advancing, increasing pressure), control of support position, advancing chain conveyor. The following control systems are described: fully automatic control, remote control from a gate road, manual control from an adjacent support unit. Types of electronic equipment used in the control systems are described: microcomputers (8-bit CMOS device), 8-bit microcomputers, transmission systems, measuring instruments. Advantages of control systems developed and manufactured by the 3 companies are comparatively evaluated.

  8. Crud separation from equipment drain of BWR atomic power station

    International Nuclear Information System (INIS)

    Hayashi, Masaru; Yamaguchi, Hisashi; Moriya, Yasuhiro; Koshiba, Yukihiko; Ota, Yoshiharu.

    1977-01-01

    In the primary cooling systems of BWR nuclear power stations, radioactive crud is generated and accumulates in reactors and circulating systems, which causes the radiation exposure of workers at the time of the inspection and maintenance of reactors. The chemical composition and grain size distribution of crud differ largely according to the construction of primary systems, the operational conditions of reactors, and the process of operation. The study on the application of nuclear pore membrane filter NPMF to the separation of crud in the waste water from equipment drain systems has been carried out. With the NPMF, clarified filtrate can be obtained without any filter aid, therefore the secondary waste of filter sludge is not generated. When the filter is clogged, the filtration capability can be regenerated by reverse flow washing, and continuous filtration is possible actually because the regeneration takes only short time. The NPMF is the polycarbonate membrane of about 10 μm thick, to which charged particles are irradiated vertically, and the flight tracks are etched with alkali solution, thus the required pore treatment is applied. The basic investigation of waste liquid, the endurance test of actual filters, the filtration test with the pilot apparatus, the demonstration test with an actual equipment, and the design of the actual equipment have been carried out for three years. (Kako, I.)

  9. Communications received from Members regarding the Export of Nuclear Material and of Certain Categories of Equipment and other Material

    International Nuclear Information System (INIS)

    1993-05-01

    On 13 December 1990 the Director General received a letter dated 10 December 1990 from the Resident Representative of Austria to the Agency in the same terms as the letter and its Annex reproduced in document INFCIRC/209/Rev.1. That document deals with communications received from Members regarding the export of nuclear material and of certain categories of equipment and other material [ru

  10. Communications received from Members regarding the Export of Nuclear Material and of Certain Categories of Equipment and other Material

    International Nuclear Information System (INIS)

    1993-06-01

    On 13 December 1990 the Director General received a letter dated 10 December 1990 from the Resident Representative of Austria to the Agency in the same terms as the letter and its Annex reproduced in document INFCIRC/209/Rev.1. That document deals with communications received from Members regarding the export of nuclear material and of certain categories of equipment and other material [es

  11. Response of equipment in nuclear power plants to airplane crash

    International Nuclear Information System (INIS)

    Schalk, M.; Woelfel, H.

    1976-01-01

    Nuclear power plants in Germany are to be designed against airplane crash. Two problems arise: first, the local problem of penetration as well as local destruction of the building and secondly the airplane induced vibrations of the whole building which cause loadings for secondary systems (equipment). This paper deals especially with the second problem. Floor response spectra due to airplane crash are presented for two different power plant buildings. The influence of various parameters (time history of excitation, direction and location of impact, mathematical model, soil, damping, etc.) are discussed. A comparison with the results of earthquake loading is given. Suggestions are made for developing suitable floor design spectra and using them to analyse multidegree-of-freedom systems. However, the paper gives only a partial answer to the questions arising because of some important restrictions which had to be made. Studies concerning these restrictions are still being conducted and will be presented in a separate paper. (Auth.)

  12. Studies for aseismatic design of atomic power equipment

    International Nuclear Information System (INIS)

    Uchiyama, Yuichi; Takayanagi, Masaaki; Moriyama, Takeo; Mizuno, Sadao

    1976-01-01

    The social requirements for the safety of nuclear power stations are very severe, and especially in Japan where earthquakes occur frequently, the safety against earthquakes is regarded as an important matter. The numerous machinery and equipments composing nuclear power plants have largely different roles in the safety, accordingly it is important to maintain effectively the safety as a whole. The design is carried out by classifying buildings, machinery and equipments, pipings and electric appliances according to the importance, and so that the aseismatic property corresponding to the importance is given to each. In most cases, the aseismatic design is carried out with computing codes, but it is necessary to forward the design by proving the propriety of analysis models and calculated results. Efforts are exerted in Hitachi Ltd. to improve the accuracy of the aseismatic analysis by carrying out basic experiment, the demonstration test in actual plants and the study on analytical method as many as possible. The measurement of the vibration of actual pipings in order to confirm the supporting conditions, the comparison of multi-input analysis and SRSS method for piping analysis, and the vibration tests of a model containment vessel and a fuel assembly were carried out, and the results are reported in this paper. It is important to improve the accuracy of earthquake response analysis further. (Kako, I.)

  13. Solar central receiver hybrid power system. Phase I study

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-11-01

    A management plan is presented for implementation during the Solar Central Receiver Hybrid Power System - Phase I study project. The project plan and the management controls that will be used to assure technically adequate, timely and cost effective performance of the work required to prepare the designated end products are described. Bechtel in-house controls and those to be used in directing the subcontractors are described. Phase I of the project consists of tradeoff studies, parametric analyses, and engineering studies leading to conceptual definition and evaluation of a commercial hybrid power system that has the potential for supplying economically competitive electric power to a utility grid in the 1985-1990 time frame. The scope also includes the preparation of a development plan for the resolution of technical uncertainties and the preparation of plans and a proposal for Phase II of the program. The technical approach will be based on a central receiver solar energy collection scheme which supplies thermal energy to a combined cycle, generating system, consisting of a gas turbine cycle combined with a steam bottoming cycle by means of a heat recovery steam generator.

  14. Outdoor Power Equipment Technician: Apprenticeship Course Outline. Apprenticeship and Industry Training. 5111.1

    Science.gov (United States)

    Alberta Advanced Education and Technology, 2011

    2011-01-01

    The graduate of the Outdoor Power Equipment Technician apprenticeship program is a certified journeyperson who will be able to: (1) supervise, train and coach apprentices; (2) service, maintain, repair and rebuild outdoor power equipment and outdoor power equipment accessories; (3) communicate clearly with customers, staff, suppliers, as required;…

  15. 30 CFR 18.21 - Machines equipped with powered dust collectors.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Machines equipped with powered dust collectors... TESTING, EVALUATION, AND APPROVAL OF MINING PRODUCTS ELECTRIC MOTOR-DRIVEN MINE EQUIPMENT AND ACCESSORIES Construction and Design Requirements § 18.21 Machines equipped with powered dust collectors. Powered dust...

  16. Communications received from Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1994-11-01

    The Director General has received notes verbales relating to the export of nuclear material, equipment and technology from the following Permanent Missions to the International Atomic Energy Agency: notes verbales dated 15 June 1994 from the Permanent Missions of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Romania, the Slovak Republic, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland and the United States of America; and a note verbale dated 10 November 1994 from the Permanent Mission of the Russian Federation. The purpose of these notes verbales is to provide further information on these Governments' nuclear export policies and practices. In the light of the wish expressed at the end of each note verbale, the analogous text of the notes verbales is attached hereto. The enclosure of these notes verbales with the amendments to the ''Guidelines for Nuclear Transfers'' contained in INFCIRC/254/Rev.1/Part 1/Mod.1 is reproduced in the Annex

  17. Aging management guidelines for commercial nuclear power plant equipment

    International Nuclear Information System (INIS)

    Nakos, J.T.; Gazdzinski, R.F.; Toman, G.J.

    1994-01-01

    The US Department of Energy, in cooperation with the Electric Power Research Institute and nuclear power plant utilities, has prepared ''Aging Management Guidelines'' (AMGs) for commodity types of equipment (e.g., pumps, electrical switchgear) important to license renewal. For the most part, this is also consistent with the Maintenance Rule, 10 CFR 50.65 (1991). AMGs concentrate on technical, (not licensing) issues and are directed toward systems engineers and plant maintenance staff. AMGs include a detailed summary of operating history, stressors, aging mechanisms, and various types of maintenance practices that can be combined to create effective programs that manage aging. All aging mechanisms were addressed; no attempt was made to limit the evaluation to aging mechanisms ''unique to license renewal,'' as defined in the License Renewal Rule, 10 CFR 54 (1991). The first AMG on Electrical Switchgear was published in July 1993. Six (6) additional AMGs will be published by the first quarter of calendar year 1994. It is anticipated that two more AMGs will be started in 1994. The seven ongoing AMG topics are as follows: (1) battery chargers, inverters and uninterruptible power supplies; (2) batteries, stationary; (3) heat exchangers; (4) motor control centers; (5) pumps; (6) switchgear, electric; (7) transformers, power and distribution. In Section 7, industry feedback regarding AMGs is discussed. Overall, the response has been very positive

  18. Field vibration test of principal equipment of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shiraki, Kazuhiro; Fujita, Katsuhisa; Kajimura, Motohiko; Ikegami, Yasuhiko; Hanzawa, Katsumi; Sakai, Yoshiyuki; Kokubo, Eiji; Igarashi, Shigeru

    1984-09-01

    Japan is one of the most earthquake-stricken countries in the world, and demands for aseismic design have become severer recently. In a nuclear power plant in particular, consisting of a reactor vessel and other facilities dealing with a radioactive substance in some form or other, it is essential from the standpoint of safety to eliminate any possibility of radioactive hazards for the local public, and the employees at the plant as well, if these facilities are struck by an earthquake. This paper is related to the reactor vessel, reactor primary cooling equipment and piping system and important general piping as examples of important facilities of a nuclear power plant, and discusses vibration tests of an actual plant in the field from the standpoint of enhancing the aseismic safety of the Mitsubishi PWR nuclear power plant. Especially concerning vibration test technology, the effects in the evaluation of aseismic safety and its limits are studied to prove how it contributes to the enhancement of the reliability of aseismic design of nuclear power plants.

  19. Impact of power uprate on environmental qualification of equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Raheja, R.D.; Mohiuddin, A.; Alsammarae, A.

    1996-01-01

    Many nuclear power facilities are finding it economically beneficial to increase reactor output, from operating plants, by resorting to power uprates. A power uprate implies that a utility can increase the reactor output, or the megawatts generated, by increasing steam pressure without adding or changing any plant systems. This is perhaps one of the least expensive options for increasing the generating capacity of a power plant. However, a nuclear plant requires a comprehensive review of the plant systems, structures and components to assure their capability to withstand the resulting increased normal and accident plant conditions. A power uprate will typically result in a plant operating at higher than the originally designed environmental conditions. Safety related equipment in nuclear plants is presently qualified to the UFSAR Chapter 15 accident events and the resulting temperatures, pressures, radiation levels etc. These values will increase when the reactor is producing a higher MWe output. Components that are sensitive to the environment must be re-evaluated and assessed to determine their acceptability and operability under the revised environmental conditions. Most safety-related mechanical and electrical equipment will require an assessment from an environmental qualification standpoint. Utilities must perform this task in a systematic, auditable and cost effective manner to optimize their resources and minimize plant costs associated with modifications, replacements or equipment testing. This paper discusses various approaches and provides recommendations to achieve equipment qualification while satisfying the plant's objective of a power uprate

  20. Specific issues for seismic performance of power plant equipment

    Energy Technology Data Exchange (ETDEWEB)

    Nawrotzki, Peter [GERB Vibration Control Systems, Berlin (Germany)

    2010-01-15

    Power plant machinery can be dynamically decoupled from the substructure by the effective use of helical steel springs and viscous dampers. Turbine foundations, coal mills, boiler feed pumps and other machine foundations benefit from this type of elastic support systems to mitigate the transmission of operational vibration. The application of these devices may also be used to protect against earthquakes and other catastrophic events, i.e. airplane crash, of particular importance in nuclear facilities. This article illustrates basic principles of elastic support systems and applications on power plant equipment and buildings in medium and high seismic areas. Spring damper combinations with special stiffness properties are used to reduce seismic acceleration levels of turbine components and other safety or non-safety related structures. For turbine buildings, the integration of the turbine sub-structure into the machine building can further reduce stress levels in all structural members. The application of this seismic protection strategy for a spent fuel storage tank in a high seismic area is also discussed. Safety in nuclear facilities is of particular importance and recent seismic events and the resulting damage in these facilities again brings up the discussion. One of the latest events is the 2007 Chuetsu earthquake in Japan. The resulting damage in the Kashiwazaki Kariwa Nuclear Power Plant can be found in several reports, e.g. in Yamashita. (orig.)

  1. On the technical superiority of domestic power plant equipment and its development

    International Nuclear Information System (INIS)

    Zhao Zhiyi

    1993-01-01

    Under the Presumption of affirmed superiority of domestic power plant equipment, some existing deficiencies are pointed out. The scientific and technical development of domestic power equipment can be impelled through catching up with advanced technologies. The necessity of optimal matching of plant equipment from the engineering point of view is emphasized by the authors in association with a prospective outlook of key power equipment and development suggestions

  2. Design of mobile receiving and treatment equipment for radioactive liquid waste

    International Nuclear Information System (INIS)

    Kong Jinsong; Guo Weiqun; Lu Jingbin

    2012-01-01

    The advantage and disadvantage of radioactive liquid waste treatment technology are analyzed in this paper. The experimental disposal equipment for radioactive liquid waste with complicated sources is designed by combining the far infrared calcification technology with evaporation technology. It has advantages of low energy consuming and high decontamination efficiency. The frothy and dirt appear rarely in this equipment. (authors)

  3. Power system engineering planning, design, and operation of power systems and equipment

    CERN Document Server

    Schlabbach, Juergen

    2014-01-01

    With its focus on the requirements and procedures of tendering and project contracting, this book enables the reader to adapt the basics of power systems and equipment design to special tasks and engineering projects, e.g. the integration of renewable energy sources.

  4. 30 CFR 75.509 - Electric power circuit and electric equipment; deenergization.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Electric power circuit and electric equipment... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Electrical Equipment-General § 75.509 Electric power circuit and electric equipment; deenergization. [Statutory Provisions] All...

  5. 77 FR 17099 - Proposed Extension of Existing Information Collection; Diesel-Powered Equipment for Underground...

    Science.gov (United States)

    2012-03-23

    ... to underground coal miners who work in mines that use diesel-powered equipment. Diesel equipment can... provide important safety protections to underground coal miners who work in mines that use diesel-powered... maintenance of fire suppression systems on the equipment and at fueling stations; exhaust gas sampling...

  6. Investigation of smoke corrosivity in nuclear power plant equipment

    International Nuclear Information System (INIS)

    Nowlen, S.P.

    1987-01-01

    This paper presents certain results of fire safety research at Sandia National Laboratories (SNL). The work presented here is related to the issue of the development of standardized tests for determining the corrosive potential of materials when burned. This effort is associated with the investigation of the effects of fire on the operability of a nuclear power generating station and involves a number of programs. This paper will focus on information about five specific aspects of the corrosivity issue that has been gathered as a part of several individual experimental and analytical studies. These five topics are (1) the current perception of fire risk for nuclear power plants and the roll of corrosivity in that risk, (2) the composition of smoke particulate from large-scale enclosure cable fire tests, (3) the aging behavior of smoke particulate, (4) the effect of fire size on the physical characteristics of generated smoke particulate, and (5) electrical equipment fire exposure test results. 4 refs., 2 figs., 1 tab

  7. A low-power CMOS frequency synthesizer for GPS receivers

    International Nuclear Information System (INIS)

    Yu Yunfeng; Xiao Shimao; Zhuang Haixiao; Ma Chengyan; Ye Tianchun; Yue Jianlian

    2010-01-01

    A low-power frequency synthesizer for GPS/Galileo L1/E1 band receivers implemented in a 0.18 μm CMOS process is introduced. By adding clock-controlled transistors at latch outputs to reduce the time constant at sensing time, the working frequency of the high-speed source-coupled logic prescaler supplying quadrature local oscillator signals has been increased, compared with traditional prescalers. Measurement results show that this synthesizer achieves an in-band phase noise of -87 dBc/Hz at 15 kHz offset, with spurs less than -65 dBc. The whole synthesizer consumes 6 mA in the case of a 1.8 V supply, and its core area is 0.6 mm 2 . (semiconductor integrated circuits)

  8. Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The present Manual on Quality Assurance (QA) for Installation and Commissioning of Instrumentation, Control and Electrical (ICE) Equipment of Nuclear Power Plants contains supporting material and illustrative examples for implementing basic requirements of the quality assurance programme in procurement, receiving, installation and commissioning of this equipment. The Manual on Quality Assurance for Installation and Commissioning of ICE Equipment is designed to supplement and be consistent with the Guidebook as well as with the IAEA Code and Safety Guides on Quality Assurance. It is intended for the use of managerial staff and QA personnel of nuclear power plant owners or the organizations respectively responsible for the legal, technical, administrative and financial aspects of a nuclear power plant. The information provided in the Manual will also be useful to the inspection staff of the regulatory organization in the planning and performance of regulatory inspections at nuclear power plants

  9. Equipment acquisition plans for the SSCL magnet excitation power system

    International Nuclear Information System (INIS)

    Winje, R.

    1993-05-01

    This report gives a brief description of the major electrical technical equipment used in the Superconducting Super Collider accelerators systems and the present laboratory plans for the acquisition of the equipment

  10. Communications received from certain member states regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1993-04-01

    The document reproduces the Note Verbale dated 8 February 1993 received by the Director General from the Permanent Mission of the Russian Federation to the International Organizations in Vienna, relating to the export of nuclear material, equipment or technology, in order to provide information on that Government's Guidelines for Nuclear Transfer

  11. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1993-01-01

    The document reproduces the Note Verbale dated 2 December 1992 received by the Director General from the Resident Representative of Argentina to the Agency relating to the export of nuclear material, equipment and technology in order to clarify parts of the Trigger List which is incorporated in Annex A to the Guidelines for Nuclear Transfers

  12. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1994-04-01

    The Director General has received notes verbales dated 27 August 1993 and 28 October 1993 from the Permanent Missions of Finland and Spain to the International Atomic Energy relating to the export of nuclear material, equipment and technology. The purpose of these notes verbales is to provide further information on those Governments' nuclear export policies and practices

  13. Communications received from certain member states regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1993-04-01

    The document reproduces the text of a Note Verbale dated 5 March 1993 received by the Director General from the Ministry of Foreign Affairs of the Slovak Republic, in order to provide information on that Government's Guidelines for Nuclear Transfer and for Transfers of Nuclear - Related Dual-Use Equipment, Material and Related Technology

  14. Communication received from Argentina regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1995-10-01

    The Director General has received a letter of 27 June 1995 from the Resident Representative of Argentina to the Agency concerning the export of nuclear material and of certain categories of equipment and other material. In the light of the wish expressed at the end of the letter, the text of the letter is attached hereto

  15. A guide to qualification of electrical equipment for nuclear power plants. Final report, November 1983

    International Nuclear Information System (INIS)

    Marion, A.; Lamken, D.; Harrall, T.; Kasturi, S.; Holzman, P.; Carfagno, S.; Thompson, D.; Boyer, B.; Hanneman, H.; Rule, W.

    1983-09-01

    Equipment qualification demonstrates that nuclear power plant equipment can perform its safety function - that despite age or the adverse conditions of a design basis accident the equipment can work as needed. This report is a guide to the overall process of electrical equipment qualification. It should interest those who design such equipment, those who buy it, or test it, and even those who install and maintain it. (author)

  16. 30 CFR 75.1710 - Canopies or cabs; diesel-powered and electric face equipment.

    Science.gov (United States)

    2010-07-01

    ...-powered and electric face equipment, including shuttle cars, be provided with substantially constructed... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Canopies or cabs; diesel-powered and electric... Miscellaneous § 75.1710 Canopies or cabs; diesel-powered and electric face equipment. In any coal mine where the...

  17. Increasing efficiency and optimizing thermoelectric power plant equipment. Povyshenie effektivnosti i optimizatsiia teploenergeticheskikh ustanovok

    Energy Technology Data Exchange (ETDEWEB)

    Andriushchenko, A.I.

    1981-01-01

    The problems of increasing the efficiency and optimizing the operational conditions of a thermoelectric power plant and providing efficient operational conditions of the primary and auxillary equipment at a thermoelectric power plant are examined. Methodologies and designs for optimizing the primary parameters of the power-generating equipment based on economic factors are given. A number of recommendations for designing equipment based on the research results are given.

  18. Communications received from Members regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1992-05-01

    The document reproduces the text of the letters dated 2 March 1992, received by the Director General of the IAEA from the Resident Representatives to the Agency of Australia, Austria, Canada, Czechoslovakia, Denmark, Finland, the Federal Republic of Germany, Greece, Hungary, Ireland, Japan, Luxemburg, the Netherlands, Norway, Poland, Romania, Sweden, the United Kingdom of Great Britain and Northern Ireland and the United States of America regarding the export of nuclear material and of certain categories of equipment and other material, namely plants for the production of heavy water, deuterium and deuterium compound and equipment especially designed or prepared thereof

  19. Power and Efficiency Analysis of a Solar Central Receiver Combined Cycle Plant with a Small Particle Heat Exchanger Receiver

    Science.gov (United States)

    Virgen, Matthew Miguel

    Two significant goals in solar plant operation are lower cost and higher efficiencies. To achieve those goals, a combined cycle gas turbine (CCGT) system, which uses the hot gas turbine exhaust to produce superheated steam for a bottoming Rankine cycle by way of a heat recovery steam generator (HRSG), is investigated in this work. Building off of a previous gas turbine model created at the Combustion and Solar Energy Laboratory at SDSU, here are added the HRSG and steam turbine model, which had to handle significant change in the mass flow and temperature of air exiting the gas turbine due to varying solar input. A wide range of cases were run to explore options for maximizing both power and efficiency from the proposed CSP CCGT plant. Variable guide vanes (VGVs) were found in the earlier model to be an effective tool in providing operational flexibility to address the variable nature of solar input. Combined cycle efficiencies in the range of 50% were found to result from this plant configuration. However, a combustor inlet temperature (CIT) limit leads to two distinct Modes of operation, with a sharp drop in both plant efficiency and power occurring when the air flow through the receiver exceeded the CIT limit. This drawback can be partially addressed through strategic use of the VGVs. Since system response is fully established for the relevant range of solar input and variable guide vane angles, the System Advisor Model (SAM) from NREL can be used to find what the actual expected solar input would be over the course of the day, and plan accordingly. While the SAM software is not yet equipped to model a Brayton cycle cavity receiver, appropriate approximations were made in order to produce a suitable heliostat field to fit this system. Since the SPHER uses carbon nano-particles as the solar absorbers, questions of particle longevity and how the particles might affect the flame behavior in the combustor were addressed using the chemical kinetics software Chemkin

  20. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1992-07-01

    The document reproduces the text of the notes verbales dated 15 May 1992, received by the Director General from the Resident Representatives to the Agency of Australia, Austria, Belgium, Bulgaria, Canada, Czech and Slovak Federal Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Romania, Russia Federation, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology and the Guidelines for Transfer of Nuclear-Related Dual-Use Equipment, Material and Related Technology. An Annex to these Guidelines contains the list of Nuclear-Related Dual-Use Equipment and Materials and Related Technology

  1. DESIGNING FEATURES OF POWER OPTICAL UNITS FOR TECHNOLOGICAL EQUIPMENT

    Directory of Open Access Journals (Sweden)

    M. Y. Afanasiev

    2016-03-01

    Full Text Available This paper considers the question of an optical unit designing for transmitting power laser radiation through an optical fiber. The aim of this work is designing a simple construction unit with minimized reflection losses. The source of radiation in the optical unit described below is an ultraviolet laser with diode pumping. We present the general functioning scheme and designing features for the three main parts: laser beam deflecting system, laser beam dump and optical unit control system. The described laser beam deflection system is composed of a moving flat mirror and a spherical scattering mirror. Comparative analysis of the production technology for such mirrors was carried out, and, as a result, the decision was made to produce both mirrors of 99.99 % pure molybdenum without coating. A moving mirror deflects laser emission from a source through a fiber or deflects it on a spherical mirror and into the laser beam dump, moreover, switching from one position to another occurs almost immediately. It is shown that a scattering mirror is necessary, otherwise, the absorbing surface of the beam dump is being worn out irregularly. The laser beam dump is an open conical cavity, in which the conical element with its spire turned to the emission source is placed. Special microgeometry of the internal surface of the beam dump is suggested for the better absorption effect. An optical unit control system consists of a laser beam deflection system, laser temperature sensor, deflection system solenoid temperature sensor, and deflection mirror position sensor. The signal processing algorithm for signals coming from the sensors to the controller is described. The optical unit will be used in special technological equipment.

  2. On the distribution and mean of received power in stochastic cellular network

    OpenAIRE

    Cao, Fengming; Ganesh, Ayalvadi; Armour, Simon; Sooriyabandara, Mahesh

    2016-01-01

    This paper exploits the distribution and mean of received power for cellular network with stochastic network modeling to study the difference between the two cell association criteria, i.e. the strongest received power based cell association and the closest distance based cell association. Consequently we derive the analytical expression of the distribution and the mean of the nth strongest received power and the received power from the nth nearest base station and the derivations have been c...

  3. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2002-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 31 August 2001, from the Resident Representatives to the Agency of Argentina, Austria, Belarus, Belgium, Brazil, Bulgaria, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Latvia, Luxembourg, Netherlands, New Zealand, Portugal, Republic of Korea, Romania, Russian Federation, Slovakia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United States and the United Kingdom, relating to the export of nuclear material, equipment and technology

  4. A robust low quiescent current power receiver for inductive power transmission in bio implants

    Science.gov (United States)

    Helalian, Hamid; Pasandi, Ghasem; Jafarabadi Ashtiani, Shahin

    2017-05-01

    In this paper, a robust low quiescent current complementary metal-oxide semiconductor (CMOS) power receiver for wireless power transmission is presented. This power receiver consists of three main parts including rectifier, switch capacitor DC-DC converter and low-dropout regulator (LDO) without output capacitor. The switch capacitor DC-DC converter has variable conversion ratios and synchronous controller that lets the DC-DC converter to switch among five different conversion ratios to prevent output voltage drop and LDO regulator efficiency reduction. For all ranges of output current (0-10 mA), the voltage regulator is compensated and is stable. Voltage regulator stabilisation does not need the off-chip capacitor. In addition, a novel adaptive biasing frequency compensation method for low dropout voltage regulator is proposed in this paper. This method provides essential minimum current for compensation and reduces the quiescent current more effectively. The power receiver was designed in a 180-nm industrial CMOS technology, and the voltage range of the input is from 0.8 to 2 V, while the voltage range of the output is from 1.2 to 1.75 V, with a maximum load current of 10 mA, the unregulated efficiency of 79.2%, and the regulated efficiency of 64.4%.

  5. The design and qualification of radiation tolerant equipment for the nuclear power industry

    International Nuclear Information System (INIS)

    Sharp, R.; Pater, L.

    1995-01-01

    The nuclear power industry has many demands for equipment tolerant to the damaging effects of radiation. The wide variety of applications, including components handling, tooling, monitoring and communications, means that a systematic evaluation of the effects of radiation on materials and components used for equipment in radioactive facilities is often required. This paper describes the various effects of radiation on equipment, and discusses how to manage them when using and designing equipment. (Author)

  6. Supplier selection based on improved MOGA and its application in nuclear power equipment procurement

    International Nuclear Information System (INIS)

    Yan Zhaojun; Wang Dezhong; Zhou Lei

    2007-01-01

    Considering the fact that there are few objective and available methods supporting the supplier selection in nuclear power equipment purchasing process, a supplier selection method based on improved multi-objective genetic algorithm (MOGA) is proposed. The simulation results demonstrate the effectiveness and efficiency of this method for the supplier selection in nuclear power equipment procurement process. (authors)

  7. 30 CFR 56.12071 - Movement or operation of equipment near high-voltage power lines.

    Science.gov (United States)

    2010-07-01

    ...-voltage power lines. 56.12071 Section 56.12071 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION... NONMETAL MINES Electricity § 56.12071 Movement or operation of equipment near high-voltage power lines. When equipment must be moved or operated near energized high-voltage powerlines (other than trolley...

  8. 30 CFR 75.1907 - Diesel-powered equipment intended for use in underground coal mines.

    Science.gov (United States)

    2010-07-01

    ... underground coal mines. 75.1907 Section 75.1907 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Diesel-Powered Equipment § 75.1907 Diesel-powered equipment intended for use in underground coal mines. (a) As of...

  9. Power levels in office equipment: Measurements of new monitors and personal computers

    International Nuclear Information System (INIS)

    Roberson, Judy A.; Brown, Richard E.; Nordman, Bruce; Webber, Carrie A.; Homan, Gregory H.; Mahajan, Akshay; McWhinney, Marla; Koomey, Jonathan G.

    2002-01-01

    Electronic office equipment has proliferated rapidly over the last twenty years and is projected to continue growing in the future. Efforts to reduce the growth in office equipment energy use have focused on power management to reduce power consumption of electronic devices when not being used for their primary purpose. The EPA ENERGY STAR[registered trademark] program has been instrumental in gaining widespread support for power management in office equipment, and accurate information about the energy used by office equipment in all power levels is important to improving program design and evaluation. This paper presents the results of a field study conducted during 2001 to measure the power levels of new monitors and personal computers. We measured off, on, and low-power levels in about 60 units manufactured since July 2000. The paper summarizes power data collected, explores differences within the sample (e.g., between CRT and LCD monitors), and discusses some issues that arise in m etering office equipment. We also present conclusions to help improve the success of future power management programs.Our findings include a trend among monitor manufacturers to provide a single very low low-power level, and the need to standardize methods for measuring monitor on power, to more accurately estimate the annual energy consumption of office equipment, as well as actual and potential energy savings from power management

  10. Recommendations for managing equipment aging in nuclear power plants

    International Nuclear Information System (INIS)

    Gunther, W.E.; Subudhi, M.; Aggarwal, S.K.

    1992-01-01

    Research conducted under the auspices of the US NRC's Nuclear Plant Aging Research (NPAR) Program has resulted in a large database of component and system operating, maintenance, and testing information. This database has been used to determine the susceptibility to aging of selected components, and the potential for equipment aging to impact plant safety and availability. it has also identified methods for detecting and mitigating component and system aging. This paper describes the research recommendations on electrical components which could be applied to maintenance, testing, and inspection activities to detect and mitigate the effects of aging prior to equipment failures

  11. The establish and application of equipment reliability database in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zheng Wei; Li He

    2006-03-01

    Take the case of Daya Bay Nuclear Power Plant, the collecting and handling of equipment reliability data, the calculation method of reliability parameters and the establish and application of reliability databases, etc. are discussed. The data source involved the design information of the equipment, the operation information, the maintenance information and periodically test record, etc. Equipment reliability database built on a base of the operation experience. It provided the valid tool for thoroughly and objectively recording the operation history and the present condition of various equipment of the plant; supervising the appearance of the equipment, especially the safety-related equipment, provided the very practical worth information for enhancing the safety and availability management of the equipment and insuring the safety and economic operation of the plant; and provided the essential data for the research and applications in safety management, reliability analysis, probabilistic safety assessment, reliability centered maintenance and economic management in nuclear power plant. (authors)

  12. Research on the security of nuclear power equipment

    International Nuclear Information System (INIS)

    Zhao Jiong; Wu Jinzong

    2008-06-01

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

  13. Power Factor Correction for Thyristor Equipment in Glass Industry ...

    African Journals Online (AJOL)

    Thyristor power controllers are now widely used in the glass industry for controlling furnace temperature. While offering a number of operational advantages, they operate at lagging power factors which require correction for minimum power cost. Harmonic resonance with the utility feed, however, complicate the use of ...

  14. Maintenance of the Photovolatic Plants Using UAV Equipped with Low-cost GNSS RTK Receiver

    DEFF Research Database (Denmark)

    Bilal, Muhammad; Prasad, Ramjee; Nisi, Marco

    2017-01-01

    of low-cost GNSS RTK receiver, is the maintenance of photovoltaic (PV) plants using Unmanned Aerial Vehicle (UAV). This paper proposes a solution that aims at automating the maintenance of PV plant with enhanced reliability in a time and cost effective manner, which otherwise requires intermediate human...... intervention. The paper presents the architectural concept, system design, and end-to-end algorithm that plays a pivotal role in enabling the automatic report generation of PV plant status. Preliminary results of the proof-of-concept shows the feasibility of the proposed solution....

  15. On the Use of Tunable Power Splitter for Simultaneous Wireless Information and Power Transfer Receivers

    Directory of Open Access Journals (Sweden)

    Abdul Quddious

    2018-01-01

    Full Text Available The use of a tunable power splitter (PS as a constituent component of a simultaneous wireless information and power transfer (SWIPT system is discussed. Two varactor diodes are used to achieve a tunable output power ratio P2 : P3 varying from 1 : 1 to 1 : 10 under good matching conditions. The SWIPT system that operates at 2.4 GHz consists of a typical patch antenna, cascaded with the tunable PS, and a voltage doubler rectifier. The constituent components were implemented and tested as stand-alone devices and were subsequently combined in a measurement system using interconnectors. The effect of the tunable PS was explored with respect to the SNR measurements on the port that is intended for the information decoding receiver and the DC voltage measurements on the termination load of the rectifier that is connected directly on the energy harvesting port of the tunable PS. A spectrum analyzer is used for the SNR measurements while the input power is controlled using a signal generator. Both wireless power transmission and on-board measurements verify that the harvested energy can be maximized by using the minimum SNR at the information decoding branch at the expense of DC power consumption required for the biasing of the varactor diodes.

  16. Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Ramsden, T.

    2013-04-01

    This report discusses an analysis of the total cost of ownership of fuel cell-powered and traditional battery-powered material handling equipment (MHE, or more typically 'forklifts'). A number of fuel cell MHE deployments have received funding support from the federal government. Using data from these government co-funded deployments, DOE's National Renewable Energy Laboratory (NREL) has been evaluating the performance of fuel cells in material handling applications. NREL has assessed the total cost of ownership of fuel cell MHE and compared it to the cost of ownership of traditional battery-powered MHE. As part of its cost of ownership assessment, NREL looked at a range of costs associated with MHE operation, including the capital costs of battery and fuel cell systems, the cost of supporting infrastructure, maintenance costs, warehouse space costs, and labor costs. Considering all these costs, NREL found that fuel cell MHE can have a lower overall cost of ownership than comparable battery-powered MHE.

  17. Communication received from certain member states regarding guidelines for the export of nuclear material, equipment and technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-24

    The document contains the text of note verbales dated 30 September 1997 received by the Director General of the IAEA from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, France, Germany, Greece, Hungary, Ireland, Italy, Japan, the Republic of Korea, New Zealand, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to export of nuclear material, equipment and technology. The purpose of the notes verbale is to provide further information about the Guidelines for Transfers of Nuclear-related Dual-use Equipment, material and related Technology in accordance with which the relevant Governments act.

  18. Communication received from certain member states regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1998-01-01

    The document contains the text of note verbales dated 30 September 1997 received by the Director General of the IAEA from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, France, Germany, Greece, Hungary, Ireland, Italy, Japan, the Republic of Korea, New Zealand, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to export of nuclear material, equipment and technology. The purpose of the notes verbale is to provide further information about the Guidelines for Transfers of Nuclear-related Dual-use Equipment, material and related Technology in accordance with which the relevant Governments act

  19. Central receiver power plant: an environmental, ecological, and socioeconomic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Davison, M.; Grether, D.

    1977-06-01

    The technical details of the central receiver design are reviewed. Socio-economic questions are considered including: market penetration, air industrial sector model, demands on industry, employment, effluents associated with manufacture of components, strains due to intensive construction, water requirements, and land requirements. The ecological effects in the vicinity of the central receiver plant site are dealt with, with emphasis on effects on land surface, mammals, and reptiles and amphibians. Climatological considerations are reviewed including: desert types, effects of surface albedo modification, effects of aerosols, effects on evaporation rates, the heliostat canopy, effects on turbulent transfer rates, effects on the wind profile, a model of convection about a central receiver plant, and a global scenario. Drawings of heliostat and plant design are included in appendices. (MHR)

  20. Electromagnetic compatibility for the control and command equipments in nuclear power plants

    International Nuclear Information System (INIS)

    Buisson, J.

    1985-06-01

    Different kinds of electrical interference produce some disturbance on electronic sub-assemblies used to assume the control and the command of nuclear reactors. Following interferences are described: power supply lines perturbations, potential difference between grounding connections, electromagnetic fields. A method is described for testing the EMC of different equipments. The advantages of this method are: no destructive method, usable for testing equipment ''in situ'' in operating conditions on nuclear power plant, usable for testing equipment before operating conditions (acceptance test), level of the testing signals similar to the electrical interference level induced by the electromagnetic environment in normal operating conditions, no particular equipment and installation for test are required [fr

  1. Baseload Nitrate Salt Central Receiver Power Plant Design Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Tilley, Drake [Abengoa Solar LLC, Lakewood, CO (United States); Kelly, Bruce [Abengoa Solar LLC, Lakewood, CO (United States); Burkholder, Frank [Abengoa Solar LLC, Lakewood, CO (United States)

    2014-12-12

    The objectives of the work were to demonstrate that a 100 MWe central receiver plant, using nitrate salt as the receiver coolant, thermal storage medium, and heat transport fluid in the steam generator, can 1) operate, at full load, for 6,400 hours each year using only solar energy, and 2) satisfy the DOE levelized energy cost goal of $0.09/kWhe (real 2009 $). To achieve these objectives the work incorporated a large range of tasks relating to many different aspects of a molten salt tower plant. The first Phase of the project focused on developing a baseline design for a Molten Salt Tower and validating areas for improvement. Tasks included a market study, receiver design, heat exchanger design, preliminary heliostat design, solar field optimization, baseline system design including PFDs and P&IDs and detailed cost estimate. The baseline plant met the initial goal of less than $0.14/kWhe, and reinforced the need to reduce costs in several key areas to reach the overall $0.09/kWhe goal. The major improvements identified from Phase I were: 1) higher temperature salt to improve cycle efficiency and reduce storage requirements, 2) an improved receiver coating to increase the efficiency of the receiver, 3) a large receiver design to maximize storage and meet the baseload hours objective, and 4) lower cost heliostat field. The second Phase of the project looked at advancing the baseline tower with the identified improvements and included key prototypes. To validate increasing the standard solar salt temperature to 600 °C a dynamic test was conducted at Sandia. The results ultimately proved the hypothesis incorrect and showed high oxide production and corrosion rates. The results lead to further testing of systems to mitigate the oxide production to be able to increase the salt temperature for a commercial plant. Foster Wheeler worked on the receiver design in both Phase I and Phase II looking at both design and lowering costs utilizing commercial fossil boiler

  2. Front end power dissipation minimization and optimal transmission rate for wireless receivers

    NARCIS (Netherlands)

    Heuvel, van den J.H.C.; Wu, Y.; Baltus, P.G.M.; Linnartz, J.P.M.G.; Roermund, van A.H.M.

    2014-01-01

    Most wireless battery-operated devices spend more energy receiving than transmitting. Hence, minimizing the power dissipation in the receiver front end, which, in many cases, is the prominent power consuming part of the receiver, is an important challenge. This paper addresses this challenge by

  3. About Economy of Fuel at Thermal Power Stations due to Optimization of Utilization Diagram of Power-Generating Equipment

    Directory of Open Access Journals (Sweden)

    M. V. Svechko

    2008-01-01

    Full Text Available Problems of rational fuel utilization becomes more and more significant especially for thermal power stations (TPS. Thermal power stations have complicated starting-up diagrams and utilization modes of their technological equipment. Method of diagram optimization of TPS equipment utilization modes has been developed. The method is based on computer analytical model with application of spline-approximation of power equipment characteristics. The method allows to economize fuel consumption at a rate of 15-20 % with accuracy of the predicted calculation not more than 0.25 %.

  4. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Czech Republic, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to the export of nuclear material, equipment and technology

  5. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Czech Republic, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to the export of nuclear material, equipment and technology [es

  6. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-15

    The document reproduces the text of the Notes Verbales dated 1 February 2000 received by the Director General of the IAEA from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Brazil, Canada, the Czech Republic, Germany, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, the Netherlands, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Switzerland, Ukraine, the United Kingdom and the United States relating to export of nuclear material, equipment and technology. The purpose of the notes verbale is to provide further information on those Governments' Guidelines for Nuclear Transfers. The attachment to these Notes Verbales is also included.

  7. Communications received from Members regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1994-04-01

    The Director General has received a letter dated 7 October 1993 from the Permanent Mission of Bulgaria, letters dated 8 October 1993 from the Permanent Missions of Australia, Austria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, the Netherlands, Norway, Portugal, the Russian Federation, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, the United States of America, and a letter dated 11 October 1993 from the Permanent Mission of Poland to the International Atomic Energy Agency concerning the export of nuclear material and of certain categories of equipment and other material. Text of the letter is presented

  8. Communications received from Member States regarding the Export of Nuclear Material and of Certain Categories of Equipment and other Material

    International Nuclear Information System (INIS)

    1994-08-01

    The Director General has received letters concerning the export of nuclear material and of certain categories of equipment and other material from the following Resident Representatives to the International Atomic Energy Agency: a letter dated 28 February 1994 from the Resident Representative of France; letters dated 1 March 1994 from the Resident Representatives of Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, and the United States of America; and a letter dated 22 March 1994 from the Resident Representative of Romania [es

  9. Communications received from certain member states regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1992-07-01

    The document reproduces the text of the notes verbales dated 1 June 1992, received by the Director General from the Resident Representatives to the Agency of Australia, Austria, Belgium, Bulgaria, Canada, Czech and Slovak Federal Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Romania, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland and the United States of America relating to the export of nuclear material, equipment for technology. The purpose of these notes verbales is to clarify parts of the Trigger List incorporated in the Annex A to the Guidelines for Nuclear Transfer. 1 tab

  10. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    2000-01-01

    The document reproduces the text of the Notes Verbales dated 1 February 2000 received by the Director General of the IAEA from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Brazil, Canada, the Czech Republic, Germany, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, the Netherlands, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Switzerland, Ukraine, the United Kingdom and the United States relating to export of nuclear material, equipment and technology. The purpose of the notes verbale is to provide further information on those Governments' Guidelines for Nuclear Transfers. The attachment to these Notes Verbales is also included

  11. Communications received from Members regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1990-02-01

    The document reproduces the text of the letters and their annex dated 1 December 1989 received by the Director General of the IAEA from the Resident Representatives to the Agency of the following Member States: Australia, Canada, Czechoslovakia, Finland, the German Democratic Republic, Greece, Hungary, Japan, the Netherlands, Norway, Sweden, the Union of Soviet Socialist Republics, the United Kingdom of Great Britain and Northern Ireland and the United States of America concerning the commitments of these Member States under Article III paragraph 2, of the Treaty on the Non-Proliferation of Nuclear Weapons. It refers to the export of the equipment especially designed or prepared for the separation of isotopes of uranium

  12. Communications received from Member States regarding the Export of Nuclear Material and of Certain Categories of Equipment and other Material

    International Nuclear Information System (INIS)

    1994-01-01

    The Director General has received letters concerning the export of nuclear material and of certain categories of equipment and other material from the following Resident Representatives to the International Atomic Energy Agency: a letter dated 28 February 1994 from the Resident Representative of France; letters dated 1 March 1994 from the Resident Representatives of Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, and the United States of America; and a letter dated 22 March 1994 from the Resident Representative of Romania [fr

  13. Response of equipment in nuclear power plants to airplane crash

    International Nuclear Information System (INIS)

    Schalk, M.; Woelfel, H.

    1975-01-01

    The question has been posed concerning the effect of airplane crash on the safety of the equipment (pipes, vessels, etc.) mounted on the floors and walls inside the outer structure. This equipment is set into vibration by the crash-induced shaking of the outer building; the resulting stresses may be quite appreciable. The following questions arise: a) how large are these stresses. Can they, for example, be larger than the stresses produced by earthquake loading. b) What are the significant response parameters. c) Which methods of analysis and design criteria are reasonable. To what extent is it possible to apply the techniques which have become generally accepted for earthquake loading. The paper presents a preliminary answer to these questions pending further work in this area. (orig./HP) [de

  14. Electrical and control equipment in nuclear power plants. Problems when replacing aging equipment; El och kontrollutrustning i kaernkraftverk - Problematik vid utbyte av aaldrad utrustning

    Energy Technology Data Exchange (ETDEWEB)

    Nordling, Anna; Haakansson, Goeran

    2012-11-01

    Interoperability between different technical systems is more complicated when old and new technology meet, such as between analog and digital technology. New electrical and I and C equipment is selected with consideration to simplify and improve the compatibility and interoperability. The original construction of nuclear power plants with electricity and I and C equipment had more natural interfaces. Generally experienced guidance, to the management of interoperability and interfaces, feels insufficient. Skills transfer programs are identified as a major need, as more and more important personnel are retiring and important information is lost with them. Lack of appropriate skills directly affects the ability to produce accurate and complete requirements specification. Failure modes of newer electrical and I and C equipment are perceived as more complex than the older equipment. When choosing equipment, attempts are made to minimize unnecessary features, to reduce the number of potential failure modes. There is a lack of consistent understanding of the meaning of robustness in electrical technology and I and C technology, in the nuclear plant engineering departments. The overall picture is that the robustness has worsened since the facilities were built. The Swedish nuclear power plants have an internal organizational structure with separated client and support organization. This splits the nuclear organization into two distinct parts which threaten to separate the two entities focus. Engineering departments at the Swedish nuclear power plants express a need for increased expertise in the client organization (blocks). Competence requested is for example, system knowledge to facilitate and enhance the quality of the initial analysis performed in the blocks. Suppliers receive more recently larger turnkey projects, both to minimize costs but also to minimize the interfaces and co-function problems. This, however, heightens demands for knowledge transfer between

  15. After-hours power status of office equipment and energy use of miscellaneous plug-load equipment

    Energy Technology Data Exchange (ETDEWEB)

    Roberson, Judy A.; Webber, Carrie A.; McWhinney, Marla C.; Brown, Richard E.; Pinckard, Marageret J.; Busch, John F.

    2004-05-27

    This research was conducted in support of two branches of the EPA ENERGY STAR program, whose overall goal is to reduce, through voluntary market-based means, the amount of carbon dioxide emitted in the U.S. The primary objective was to collect data for the ENERGY STAR Office Equipment program on the after-hours power state of computers, monitors, printers, copiers, scanners, fax machines, and multi-function devices. We also collected data for the ENERGY STAR Commercial Buildings branch on the types and amounts of miscellaneous plug-load equipment, a significant and growing end use that is not usually accounted for by building energy managers. For most types of miscellaneous equipment, we also estimated typical unit energy consumption in order to estimate total energy consumption of the miscellaneous devices within our sample. This data set is the first of its kind that we know of, and is an important first step in characterizing miscellaneous plug loads in commercial buildings. The main purpose of this study is to supplement and update previous data we collected on the extent to which electronic office equipment is turned off or automatically enters a low power state when not in active use. In addition, it provides data on numbers and types of office equipment, and helps identify trends in office equipment usage patterns. These data improve our estimates of typical unit energy consumption and savings for each equipment type, and enables the ENERGY STAR Office Equipment program to focus future effort on products with the highest energy savings potential. This study expands our previous sample of office buildings in California and Washington DC to include education and health care facilities, and buildings in other states. We report data from sixteen commercial buildings in California, Georgia, and Pennsylvania: four education buildings, two medical buildings, two large offices (> 500 employees each), three medium offices (50-500 employees each), and five small

  16. Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

    International Nuclear Information System (INIS)

    Sturm, A.; Foerster, R.

    1977-01-01

    Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

  17. Communication received from certain member states regarding guidelines for the export of nuclear material, equipment and technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-16

    The document contains the text of note verbales dated 17 October 1996 received by the Director General of the IAEA from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, the Republic of Korea, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to export of nuclear material, equipment and technology. A similar note verbal dated 30 July 1997 has been received by the Director General of the IAEA from the Resident Representative to the Agency of Brazil. The purpose of the notes verbale is to provide further information on those Governments` Guidelines for Nuclear Transfers.

  18. Communication received from certain member states regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1997-01-01

    The document contains the text of note verbales dated 17 October 1996 received by the Director General of the IAEA from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, the Republic of Korea, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to export of nuclear material, equipment and technology. A similar note verbal dated 30 July 1997 has been received by the Director General of the IAEA from the Resident Representative to the Agency of Brazil. The purpose of the notes verbale is to provide further information on those Governments' Guidelines for Nuclear Transfers

  19. A low power automatic gain control loop for a receiver

    Energy Technology Data Exchange (ETDEWEB)

    Li Guofeng; Geng Zhiqing; Wu Nanjian, E-mail: nanjian@red.semi.ac.c [State Key Laboratory for Super lattices and Microstructures, Institute of Semiconductors, Chinese Academy of Sciences, Beijing 100083 (China)

    2010-09-15

    This paper proposes a new structure to lower the power consumption of a variable gain amplifier (VGA) and keep the linearity of the VGA unchanged. The structure is used in a high rate amplitude-shift keying (ASK) based IF-stage. It includes an automatic gain control (AGC) loop and ASK demodulator. The AGC mainly consists of six-stage VGAs. The IF-stage is realized in 0.18 {mu}m CMOS technology. The measurement results show that the power consumption of the whole system is very low. The system consumes 730 {mu}A while operating at 1.8 V. The minimum ASK signal the system could detect is 0.7 mV (peak to peak amplitude). (semiconductor integrated circuits)

  20. Design of measurement equipment for high power laser beam shapes

    DEFF Research Database (Denmark)

    Hansen, K. S.; Olsen, F. O.; Kristiansen, Morten

    2013-01-01

    To analyse advanced high power beam patterns, a method, which is capable of analysing the intensity distribution in 3D is needed. Further a measuring of scattered light in the same system is preferred. This requires a high signal to noise ratio. Such a system can be realised by a CCD-chip impleme...... by a commercial product has been done. The realised system might suffer from some thermal drift at high power; future work is to clarify this....

  1. Optimization of maintenance for power system equipment using a predictive health model

    NARCIS (Netherlands)

    Bajracharya, G.; Koltunowicz, T.; Negenborn, R.R.; Papp, Z.; Djairam, D.; Schutter, B.D. de; Smit, J.J.

    2009-01-01

    In this paper, a model-predictive control based framework is proposed for modeling and optimization of the health state of power system equipment. In the framework, a predictive health model is proposed that predicts the health state of the equipment based on its usage and maintenance actions. Based

  2. Modern methods of overlay welding for corrosion protection of power generating equipment

    International Nuclear Information System (INIS)

    Ershov, A.V.; Shul'man, I.E.; Potapov, N.N.

    1989-01-01

    Methods for overlay welding of inner surfaces of power equipment for corrosion protection are analysed. Various methods of electroslag overlay welding by a band electrode (overlay welding by two-electrode bands by a wide band with magnetic control, by an electrode band with high melting velocity) are marked to be the most perspective for cladding of NPP vessel equipment

  3. The use of ultrasound for decontamination of tools and equipment in nuclear power plant Krshko

    International Nuclear Information System (INIS)

    Erman, R.

    1987-01-01

    This paper describes the main principles of the ultrasonic generator functioning and the use of ultrasound for decontamination of tools and equipment in nuclear power plant Krshko. The paper gives the operating procedure and presents decontamination results of tools and equipment fabricated from various materials. (author) 3 refs.; 1 tab

  4. The Japanese power equipment market - potential for foreign companies

    International Nuclear Information System (INIS)

    Bell, G.D.; Matsumoto, Satoru

    1993-01-01

    The potential for foreign companies for sales of heavy electrical equipment in Japan is assessed. The Japanese heavy electrical equipment industry (HEI) has very close links with the electricity supply industry. Traditionally a small circle of domestic manufacturers have supplied all the electric utilities. However, there is criticism in Japan of the inefficiencies which have arisen as a result of the close relationship and the cost competitiveness of domestic products has been eroded by the appreciation of the yen. The chief driving force in the opening of the market to foreign products is political, though. Friction between Japan and the USA and European Community on the subject of trade imbalance, has led the Ministry of Internal Trade and Industry to encourage major utilities to increase their imports from abroad. Consequently, opportunities now exist for foreign suppliers to gain access to the Japanese HEI market but only if they are willing to make a long term investment. Market entry is still likely to be very difficult, however, and unlikely to produce quick returns. In the longer term, though, access to the Japanese market could open up even wider opportunities. (UK)

  5. Using cast-on electroslag technology for manufacturing nuclear power station equipment

    International Nuclear Information System (INIS)

    Rabinovich, V.I.; Borodin, M.A.; Chistyakov, G.A.; Karpov, O.S.; Kriger, Yu.N.

    1984-01-01

    An application of a new electroslag cast-on process for manufacturing nuclear power station equipment is described. This process is compared with a welding process for manufacturing a D /SUB s/ -400-mm gate valve bonnet

  6. Enhancing reliability of ultrasonic testing of welds of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Shcherbinskij, V.G.

    1981-01-01

    Results of investigation of factors influencing the reliability of manual ultrasonic testing of welded joints and weld deposited metal power-generating equipment are presented. Recommendations on the enhancing of reliability are given [ru

  7. Strategy and implementation of resources control of key equipments in nuclear power plant

    International Nuclear Information System (INIS)

    Zha Qing

    2014-01-01

    The strategic resources of the construction of nuclear power plant, which include the main equipment of nuclear island, heavy forgings, the bottleneck equipment and strategic materials, is one of the key issues in the construction of nuclear power projects. The control of these strategic resources has become the focus of competition in industry and the major nuclear power groups are willing to fight for this huge advantages. The resource control strategies of key equipment of nuclear power projects are analyzed in this paper. This paper put forward specific measures and methods for the strategic resources control. By the application to a plurality of nuclear power engineering construction projects, these specific measures and methods achieved good results and will be with important guidance and reference for the construction of future nuclear power projects in China. (author)

  8. Power enhancement of piezoelectric transformers by adding heat transfer equipment.

    Science.gov (United States)

    Su, Yu-Hao; Liu, Yuan-Ping; Vasic, Dejan; Wu, Wen-Jong; Costa, François; Lee, Chih-Kung

    2012-10-01

    It is known that piezoelectric transformers have several inherent advantages compared with conventional electromagnetic transformers. However, the maximum power capacity of piezoelectric transformers is not as large as electromagnetic transformers in practice, especially in the case of high output current. The theoretical power density of piezoelectric transformers calculated by stress boundary can reach 330 W/cm(3), but no piezoelectric transformer has ever reached such a high power density in practice. The power density of piezoelectric transformers is limited to 33 W/cm(3) in practical applications. The underlying reason is that the maximum passing current of the piezoelectric material (mechanical current) is limited by the temperature rise caused by heat generation. To increase this current and the power capacity, we proposed to add a thermal pad to the piezoelectric transformer to dissipate heat. The experimental results showed that the proposed techniques can increase by 3 times the output current of the piezoelectric transformer. A theoretical-phenomenological model which explains the relationship between vibration velocity and generated heat is also established to verify the experimental results.

  9. Reliability of nondestructive testing of metal strength properties for power equipment

    International Nuclear Information System (INIS)

    Bugaj, N.V.; Lebedev, A.A.; Sharko, A.V.

    1985-01-01

    Ultrasonic control which is a constituent part of a complex control system which includes specimen-free (by hardness) tests, random breaking tests and acoustic measurements is stUdied for its reliability with respect to strength properties of power-equipment metal. Quantitative and alternative criteria are developed to estimate quality of elements for power-equipment according to results of metal strength properties. Acoustic control results are presented for ultimate strength in 12Kh1MF-steel

  10. Emergency Mitigating Equipments - Post Fukushima Actions at Canadian Nuclear Power Plants - Portable AC Power Sources

    International Nuclear Information System (INIS)

    Vucetic, Jasmina; Kameswaran, R.

    2015-01-01

    In response to the Fukushima Daiichi NPP accident in 2011, the Canadian Nuclear Safety Commission set up a Task Force to evaluate operational, technical and regulatory implications on Canadian NPPs. While accepting that the risk from beyond-design-basis accidents (BDBA) at Canadian NPPs is very low, the Task Force identified a number of areas where additional improvements or confirmatory assessments would further enhance safety. As a result, a set of 36 Fukushima Action Items (FAIs) were assigned to the licensees. This paper focuses on the FAI related to electrical power system enhancements to address a total loss of all AC Power leading to a possibility of loss of heat sinks (i.e. Station Blackout). This required the licensees to implement the following: - Additional back up power supplied by portable diesel generator(s) to allow key instrumentation and control equipment and key electrical loads to remain operable; - Provisions for a storage and timely transportation and connection of the portable generator(s) to the applicable units; - Provisions for testing of the portable generator; - Provisions for fuelling of portable generators; - Provisions such as panels, receptacles, and connectors to quickly deploy the portable generators to plant system, and separate feeder cables route to avoid a common mode failure; - Load shedding strategy to extend the existing station's battery life to ensure that the connection of portable generators can be completed before the batteries are depleted; - Provisions to supply water to steam generators and Irradiated Fuel Bay using portable pumps; The paper will also provide a brief description of Electrical power systems of the Canadian NPPs designed to satisfy the high safety and reliability requirements for nuclear systems, which are based on the following: - 2 group design philosophy (Group 1 and Group 2 Electrical Power Systems) - 2 separate groups of onsite emergency generators (Class III Standby generators and Emergency

  11. 3. General principles of assessing seismic resistance of technological equipment of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    The evaluation of the seismic resistance of technological equipment is performed by computation, experimental trial, possibly by combining both methods. Existing and prepared standards in the field of seismic resistance of nuclear power plants are mentioned. Accelerograms and response spectra of design-basis earhtquake and maximum credible earthquake serve as the basic data for evaluating seismic resistance. The nuclear power plant in Mochovce will be the first Czechoslovak nuclear power plant with so-called partially seismic design. The problem of dynamic interaction of technological equipment and nuclear power plant systems with a bearing structure is discussed. (E.F.)

  12. Confirmation of the seismic resistance of nuclear power plant equipment after assembly

    International Nuclear Information System (INIS)

    Kaznovsky, P. S.; Kaznovsky, A. P.; Saakov, E. S.; Ryasnyj, S. I.

    2013-01-01

    It is shown that the natural frequencies and damping decrements of nuclear power plant equipment can only be determined experimentally and directly at the power generation units (reactors) of nuclear power plants under real disassembly conditions for the equipment, piping network, thermal insulation, etc. A computational experimental method is described in which the natural frequencies and damping decrements are determined in the field and the seismic resistance is reevaluated using these values. This method is the basis of the standards document “Methods for confirming the dynamic characteristics of systems and components of the generating units of nuclear power plants which are important for safety” prepared and introduced in 2012.

  13. Capital goods for energy development: power equipment for developing countries

    International Nuclear Information System (INIS)

    Parikh, J.K.

    1986-01-01

    Questions of energy policy in developing countries are considered, with the goal of 'evolution from exports to indigenization' i.e. independence. Levels of technologies are considered in relation to the resources of each country. Nuclear power is considered among other energy sources. (G.Q.)

  14. 1E Qualification of Electrical Equipment - Requirement for Safety Nuclear Power Plants

    International Nuclear Information System (INIS)

    Geambasu, C.; Segarceanu, D.; Albu, J.

    2002-01-01

    The paper presents the qualification methods of the safety related equipment according to the safety class 1E. There are presented the qualification principles, procedure and documents, emphasis being laid on the qualification approach by type tests. This approach assumes the equipment test under both normal and accident conditions (design basis events) simulating the operational conditions and covers the largest part of electrical equipment from a nuclear power plant.The safety related equipment is to be qualified is subjected to a sequential test that will be detailed in the paper. (author)

  15. 30 CFR 36.4 - Mobile diesel-powered transportation equipment for which certificates of approval may be granted.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Mobile diesel-powered transportation equipment... REQUIREMENTS FOR PERMISSIBLE MOBILE DIESEL-POWERED TRANSPORTATION EQUIPMENT General Provisions § 36.4 Mobile... of approval will be granted for completely assembled mobile diesel-powered transportation equipment...

  16. Investigation of potential fire-related damage to safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Wanless, J.

    1985-11-01

    Based on a review of vendor information, fire damage reports, equipment qualification and hydrogen burn test results, and material properties, thirty-three types of equipment found in nuclear power plants were ranked in terms of their potential sensitivity to fire environments. The ranking considered both the functional requirements and damage proneness of each component. A further review of the seven top-ranked components was performed, considering the relative prevalence and potential safety significance of each. From this, relays and hand switches dominate as first choices for fire damage testing with logic equipment, power supplies, transmitters, and motor control centers as future candidates

  17. Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Rios O, J. E.; Martinez L, A. G.

    2008-01-01

    A equipment is reliable if it fulfills the function for which was designed and when it is required. To implement a project of reliability in a nuclear power plant this associate to a process of continuous analysis of the operation, of the conditions and faults of the equipment. The analysis of the operation of a system, of the equipment of the same faults and the parts that integrate to equipment take to identify the potential causes of faults. The predictive analysis on components and equipment allow to rectify and to establish guides to optimize the maintenance and to guarantee the reliability and function of the same ones. The reliability in the equipment is without place to doubts a wide project that embraces from the more small component of the equipment going by the proof of the parts of reserve, the operation conditions until the operative techniques of analysis. Without place of doubt for a nuclear power plant the taking of decisions based on the reliability of their systems and equipment will be the appropriate for to assure the operation and reliability of the same one. In this work would appear the project of reliability its processes, criteria, indicators action of improvement and the interaction of the different disciplines from the Nuclear Power Plant of Laguna Verde like a fundamental point for it put in operation. (Author)

  18. Possible alternatives for diesel powered mobile equipment for the conditions of deep mines

    Energy Technology Data Exchange (ETDEWEB)

    Paraszczak, J.; Kotersi, O [Laval Univ., Quebec City, PQ (Canada). Dept. of Mining, Metallurgical and Materials Engineering

    2008-07-01

    The challenges associated with mining at considerable depths were discussed. Mines such as Kidd Creek, LaRonde and Creighton are deeper than 2500 m. High rock temperature is among the challenges that operators face in such conditions. Conventional diesel powered load-hauling equipment constitute an additional source of heat and noxious gases. As such, more intense ventilation is needed in order to keep ambient temperature and air quality at a level that is acceptable for human workers. This paper examined possible alternatives for diesel powered equipment, including those that are commercially available as well as those that are underdevelopment or in the prototype stage. The equipment was reviewed with reference to the required infrastructure, stage of technology development and progress. The flexibility, practicality and economic viability of the equipment was also investigated. The potential for its use in deep Canadian mines was discussed along with the most promising drive alternatives for vehicles designed for deep mine operations. Electric drives have proven to be effective in many mining applications since they have significant advantages over diesel drives. The characteristics of cable powered equipment, trolley-wire powered equipment, and battery powered equipment were described. The key advantages and disadvantages of hybrid diesel electric equipment were also reviewed along with the viability of power plants based on the use of hydrogen. The principle types of hydrogen power plants include hydrogen combustion engines; HY-Drive systems and fuel cells. It was concluded that although there is no viable alternative for diesel engines at present, Canadian mining companies operating at great depths have made significant progress in these fields and remain among the leaders in mining innovation. 17 refs.

  19. Safety review for seismic qualification on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Fang Qingxian

    1995-01-01

    The standards and requirements for seismic qualification of nuclear power plant's component have been fully addressed, including the scope of seismic qualification, the approach and the method of common seismic qualification, the procedure of the seismic tests, and the criteria for the seismic qualification review. The problems discovered in the safety review and the solution for these problems and some other issues are also discussed

  20. Condition monitoring of electrical equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Sugarman, A.

    1986-01-01

    Condition monitoring (CM) is a subset of maintenance testing. It is a quantitative, predictive technique for assessing the effects of all types of aging (environmental, cyclic, operational, etc) on the ''health'' of the equipment. A difference between CM and maintenance testing is that the latter is neither quantitative (i.e., measures the relative condition of the component or material as opposed to merely verifying that its condition is acceptable) nor predictive (i.e., makes judgments, on the ability of the component to perform at a future time). A common example of the principle of CM can be illustrated with the automobile which has a lifetime that is small enough to observe all the periods (break in, random failure, wear out) that occur throughout aging. There are several weak link components in the car (e.g., water hoses, contacts in the distributor, generator, spark plug cables, solenoid, etc) which if they fail will cause failure of the automobile to either start or run. From the day the car is put on the road and is subjected to heat and vibration, significant aging of these components occurs. Degradation in the water hoses, for example is manifested by the elastomeric casing becoming brittle and cracking

  1. Central receiver solar thermal power system, phase 1. Progress report for period ending December 31, 1975

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-04-01

    The program objective is the preliminary design of a 10 MWe pilot solar power plant supported by major subsystem experiments. Progress is reported on the following task elements: 10 MWe pilot plant; collector subsystem design and analysis; receiver subsystem requirements; receiver subsystem design; thermal storage subsystem; electrical power generation subsystem; and pilot plant architectural engineering and support. (WDM)

  2. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    2005-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 25 October 2004 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Canada, Cyprus, Czech Republic, Estonia, Finland, France, Greece, Hungary, Italy, Japan, Malta, Netherlands, Norway, Republic of Korea, South Africa, Spain, Sweden, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America relating to the export of nuclear materials, equipment and technology. The purpose of the Notes Verbales is to provide further information on those Governments' guidelines for nuclear transfers. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full

  3. Communications received from certain Member States regarding Guidelines for the Export of Nuclear Material, Equipment and Technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-16

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 28 February 2003, from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Canada, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Kazakhstan, Latvia, Netherlands, Norway, Poland, Portugal, the Republic of Korea, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America, relating to the export of nuclear material, equipment and technology. The purpose of the Note Verbales is to provide further information on those Governments' Guidelines for Nuclear Transfers. In light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to the Notes Verbales is also reproduced in full.

  4. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-02-23

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 25 October 2004 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Canada, Cyprus, Czech Republic, Estonia, Finland, France, Greece, Hungary, Italy, Japan, Malta, Netherlands, Norway, Republic of Korea, South Africa, Spain, Sweden, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America relating to the export of nuclear materials, equipment and technology. The purpose of the Notes Verbales is to provide further information on those Governments' guidelines for nuclear transfers. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full.

  5. Communications received from Member States regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1994-04-01

    The Director General has received letters concerning the export of nuclear material and of certain categories of equipment and other material from the following Resident Representatives to the International Atomic Energy Agency: a letter dated 28 February 1994 from the Resident Representative of France; letters dated 1 March 1994 from the Resident Representatives of Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, and the United States of America; and a letter dated 22 March 1994 from the Resident Representative of Romania. In the light of the wish expressed at the end of each letter, the text of the letters is attached hereto

  6. Communication received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology. Nuclear transfers

    International Nuclear Information System (INIS)

    1995-10-01

    The Director General has received notes verbales dated 30 June 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments' Guidelines for Nuclear Transfers. In the light of the wish expressed at the end of each note verbale, the text of the notes verbales is annexed hereto. The enclosure to these notes verbales is also reproduced in full in the Annex

  7. Communication received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology. Nuclear transfers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The Director General has received notes verbales dated 30 June 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments` Guidelines for Nuclear Transfers. In the light of the wish expressed at the end of each note verbale, the text of the notes verbales is annexed hereto. The enclosure to these notes verbales is also reproduced in full in the Annex.

  8. Communications received from certain Member States regarding Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2003-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 28 February 2003, from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Canada, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Kazakhstan, Latvia, Netherlands, Norway, Poland, Portugal, the Republic of Korea, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America, relating to the export of nuclear material, equipment and technology. The purpose of the Note Verbales is to provide further information on those Governments' Guidelines for Nuclear Transfers. In light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to the Notes Verbales is also reproduced in full

  9. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    2002-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbale, dated 31 August 2001, from the Resident Representatives to the Agency of Argentina, Austria, Belarus, Belgium, Brazil, Bulgaria, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Latvia, Luxembourg, Netherlands, New Zealand, Portugal, Republic of Korea, Romania, Russian Federation, Slovakia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United States and the United Kingdom, relating to the export of nuclear material, equipment and technology. The purpose of the Notes Verbale is to provide further information on those Governments' Guidelines for Nuclear Transfers. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbale is attached. The attachment to the Notes Verbale is also reproduced in full

  10. Communication of 15 November 2001 Received from the People's Republic of China regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    2002-01-01

    The Director General has received a letter of 15 November 2001 from the Resident Representative of the People's Republic of China concerning the export of nuclear material and of certain categories of equipment and other material

  11. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology: A further communication, dated 2 December 1992

    International Nuclear Information System (INIS)

    1993-01-01

    The document reproduces the Note Verbale dated 2 December 1992 received by the Director General of the IAEA from the Permanent Mission of Argentina and relating to the report of nuclear material, equipment and technology

  12. The basic discussion on nuclear power safety improvement based on nuclear equipment design

    International Nuclear Information System (INIS)

    Zhao Feiyun; Yao Yangui; Yu Hao; He Yinbiao; Gao Lei; Yao Weida

    2013-01-01

    The safety of strengthening nuclear power design was described based on nuclear equipment design after Fukushima nuclear accident. From these aspects, such as advanced standard system, advanced design method, suitable test means, consideration of beyond design basis event, and nuclear safety culture construction, the importance of nuclear safety improvement was emphatically presented. The enlightenment was given to nuclear power designer. (authors)

  13. Seismic effects on technological equipment and systems of nuclear power plants

    International Nuclear Information System (INIS)

    Masopust, R.; Pecinka, L.; Podrouzek, J.

    1983-01-01

    A survey is given of problems related to the construction of nuclear power plants with regard to seismic resistance. Sei--smic resistance of technological equipment is evaluated by experimental trials, calculation or the combination of both. Existing and future standards are given for the given field. The Czechoslovak situation is discussed as related to the construction of the Mochovce nuclear power plant. Procedures for testing seismic resistance, types of tests and methods of simulating seismic excitation are described. Antiseismic measures together with structural elements for limiting the seismic effects on technological equipment and nuclear power plant systems are summed up on the basis of foreign experience. (E.F.)

  14. Research on multi - channel interactive virtual assembly system for power equipment under the “VR+” era

    Science.gov (United States)

    Ren, Yilong; Duan, Xitong; Wu, Lei; He, Jin; Xu, Wu

    2017-06-01

    With the development of the “VR+” era, the traditional virtual assembly system of power equipment has been unable to satisfy our growing needs. In this paper, based on the analysis of the traditional virtual assembly system of electric power equipment and the application of VR technology in the virtual assembly system of electric power equipment in our country, this paper puts forward the scheme of establishing the virtual assembly system of power equipment: At first, we should obtain the information of power equipment, then we should using OpenGL and multi texture technology to build 3D solid graphics library. After the completion of three-dimensional modeling, we can use the dynamic link library DLL package three-dimensional solid graphics generation program to realize the modularization of power equipment model library and power equipment model library generated hidden algorithm. After the establishment of 3D power equipment model database, we set up the virtual assembly system of 3D power equipment to separate the assembly operation of the power equipment from the space. At the same time, aiming at the deficiency of the traditional gesture recognition algorithm, we propose a gesture recognition algorithm based on improved PSO algorithm for BP neural network data glove. Finally, the virtual assembly system of power equipment can really achieve multi-channel interaction function.

  15. Diagnosis device for abnormality of power plant equipment

    International Nuclear Information System (INIS)

    Matono, Chiemi; Okamachi, Masao.

    1995-01-01

    In a power plant, if contained water leaks in a condensate system, water is automatically supplied from a feedwater system in accordance with the leakage. Since the diameter of the pipeline of the supplementary feedwater system is generally small, the influence of the leakage of the contained water appears remarkably as a change of the amount of the feed water in the supplementary feed water system. The change of the supplementary state of water to the condensate system by the supplementary feed water system is monitored, to estimate the presence or absence of the leakage of water contained in the condensate system depending on the result of the monitoring, and then the results are informed. In addition, when leakage of water contained in the condensate system is estimated, guidance information is prepared and outputted for coping with the result of the estimation, and the result of the estimation and the guidance information are displayed auditory and visually. As a result, a plant operator can recognize the abnormality of water leakage in the condensate system rapidly and accurately without observing various states of the condensate system and with no knowledge or experiences at high levels, thereby enabling to conduct appropriate processing rapidly. (N.H.)

  16. The dose received by patients during dental X-ray examination and the technical condition of radiological equipment.

    Science.gov (United States)

    Bekas, Marcin; Pachocki, Krzysztof A

    2013-01-01

    Implementation of X-ray dental examination is associated with the patients exposure to ionizing radation. The size of the exposure depends on the type of medical procedure, the technical condition of the X-ray unit and selected exposure conditions. The aim of this study was to determine the dose received by patients during dental X-ray examination and the assessment of the technical condition of medical equipment, The study included a total number of 79 dental X-ray units located in the region of Mazovia. The test methods for the assessment of the technical condition of dental X-ray units and measurement of radiation dose received by patients were based on the procedures elaborated in the Department of Radiation Hygiene and Radiobiology in the National Institute of Public Health - National Institute of Hygiene (Warszawa, Poland) accredited for the certification of compliance with PN-EN 17025. The research found that 69.6% fully meets the criteria set out in the Polish legislation regarding the safe use of ionizing radiation in medicine, while 30.4% did not meet some of them. A tenfold difference in the size of the dose received by patients during dental X-ray examinations was discovered. For example, during a radiography of the canine teeth of a child, the recorded entrance surface dose (ESD) ranged from 72.8 to 2430 microGy with the average value of 689.1 microGy. Cases where the dose reference level defined in Polish legislation of 5 mGy was exceeded were also found. CONCKUSIONS: It is essential to constantly monitor the situation regarding the technical condition of X-ray units which affects the size of the population's exposure to ionizing radiation as well as raising dentists' awareness about the effects of X-rays on the human body.

  17. A Model of Intelligent Fault Diagnosis of Power Equipment Based on CBR

    Directory of Open Access Journals (Sweden)

    Gang Ma

    2015-01-01

    Full Text Available Nowadays the demand of power supply reliability has been strongly increased as the development within power industry grows rapidly. Nevertheless such large demand requires substantial power grid to sustain. Therefore power equipment’s running and testing data which contains vast information underpins online monitoring and fault diagnosis to finally achieve state maintenance. In this paper, an intelligent fault diagnosis model for power equipment based on case-based reasoning (IFDCBR will be proposed. The model intends to discover the potential rules of equipment fault by data mining. The intelligent model constructs a condition case base of equipment by analyzing the following four categories of data: online recording data, history data, basic test data, and environmental data. SVM regression analysis was also applied in mining the case base so as to further establish the equipment condition fingerprint. The running data of equipment can be diagnosed by such condition fingerprint to detect whether there is a fault or not. Finally, this paper verifies the intelligent model and three-ratio method based on a set of practical data. The resulting research demonstrates that this intelligent model is more effective and accurate in fault diagnosis.

  18. 12 CFR 650.20 - Powers and duties of the receiver.

    Science.gov (United States)

    2010-01-01

    ... directors of the Corporation under law and the charter, articles, and bylaws of the Corporation. (2) Take..., equipment, and supplies, and purchase insurance, professional, and technical services necessary for the... and demands against or in favor of the Corporation or receiver. (15) Pay, out of the assets of the...

  19. Study on the Selection of Equipment Suppliers for Wind Power Generation EPC Project

    Science.gov (United States)

    Yang, Yuanyue; Li, Huimin

    2017-12-01

    In the EPC project, the purchase cost of equipments accounted for about 60% of the total project cost, thus, the selection of equipment suppliers has an important influence on the EPC project. This paper, took EPC project for the phase I engineering of Guizhou Huaxi Yunding wind power plant as research background, constructed the evaluation index system for the selection of equipment suppliers for wind power generation EPC project from multiple perspectives, and introduced matter-element extension evaluation model to evaluate the selection of equipment suppliers for this project from the qualitative and quantitative point of view. The result is consistent with the actual situation, which verifies the validity and operability of this method.

  20. Improving the efficiency of thermal power equipment based on technologies using surfactants

    Science.gov (United States)

    Nikolaeva, L. A.; Zueva, O. S.

    2015-10-01

    The formation of deposits on the functional surfaces of the equipment of heating systems and their corrosion are one of the major energetic problems. To improve the operational efficiency of thermal power equipment, surface-active agents (surfactants) are widely used, which are applied for the treatment of the working surfaces before use, during use, to prevent the parking corrosion, as well as while performing periodic chemical cleanings of power equipment. The tests have been performed, and the technology of application of Auge Neo Ac 56 acid product (MAHIM, Kazan) has been developed, designed to remove mineral deposits and scale from cooling and boiler systems without mechanical influence on them and without disassembly of technological equipment.

  1. Uninterruptible power supply model of independent voltage inverter of NPP electrical equipment

    International Nuclear Information System (INIS)

    Rozhkov, V.V.; Ajdaralieva, V.Eh.

    2010-01-01

    A package of main transforming units models of advanced uninterruptible power supply systems of NPP electrical equipment was developed. The package of models allows investigating the basic modes of uninterruptible power supply systems operation by computer modeling. Simulation results were presented. Recommendations on choice of parameters of power circuit elements as well as on diagnostics and adjustment of regulators of converters control systems were given [ru

  2. The problems of the usage of powerful electrons accelerators for the irradiation of nuclear power stations' equipment and materials

    International Nuclear Information System (INIS)

    Kovalinska, T.V.; Khalova, N.V.; Ostapenko, I.A.; Sakhno, V.I.; Zelinsky, A.G.; Shlapatska, V.V.

    2012-01-01

    The possibilities of making the qualification of the materials and equipment of nuclear power stations on modern electrons accelerators of high power are researched. The problems of using this powerful sources of radiation for modern methods of nondestructive control of functional characteristics of the equipment and materials are discussed. The purpose of researches is the determination of the possibility of such works from the point of view of radiation safety of the personnel and the environment. First of all, this problem is connected with the increase of the intensity of secondary irradiation in such processes. The character of secondary irradiation is researched, as well as the dynamics of its energetic spectrum in rooms of powerful industrial accelerator (with beam power of more than 20 kW and average energy of electrons of 1.6 MeV) in regimes of irradiation of the equipment with contents of heavy elements. The original way of solving this problem is suggested. Experimentally proved, that during the usage of the set of compensatory measures, it is also possible to make tests of NPPs' materials and equipment on industrial accelerators of high power

  3. Development of digital power measuring and protecting equipment for SPRR-300 reactor

    International Nuclear Information System (INIS)

    Wang Xuejie; Li Xi'an; Zhu Shilei

    2005-01-01

    A measuring and protecting equipment of reactor power based on Single-Chip Microcomputer is introduced in this paper. The composition of hardware and the major control idea about the software for the equipment are presented. Digitizing the measuring data from nuclear instruments is precondition of reactor control and protection system which would be computerizing, and it is also an application of redundancy and variety of reactor protection system in nuclear measuring instruments. At last the working state is described. (authors)

  4. IEEE standard for qualifying class IE equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1974-01-01

    The Institute of Electrical and Electrical Engineers, Inc. (IEEE) standards for electrical equipment (Class IE) for nuclear power generating stations are given. The standards are to provide guidance for demonstrating and documenting the adequacy of electric equipment used in all Class IE and interface systems. Representative in containment design basis event conditions for the principal reactor types are included in the appendixes for guidance in enviromental simulation

  5. Seismic design of equipment and piping systems for nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Minematsu, Akiyoshi

    1997-01-01

    The philosophy of seismic design for nuclear power plant facilities in Japan is based on 'Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981' (referred to as 'Examination Guide' hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in 'Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association'. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

  6. Seismic design of equipment and piping systems for nuclear power plants in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Minematsu, Akiyoshi [Tokyo Electric Power Co., Inc. (Japan)

    1997-03-01

    The philosophy of seismic design for nuclear power plant facilities in Japan is based on `Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981` (referred to as `Examination Guide` hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in `Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association`. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

  7. Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

    Energy Technology Data Exchange (ETDEWEB)

    J. Cunningham and J. Shank

    2004-11-01

    To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I&C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner.

  8. Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

    International Nuclear Information System (INIS)

    Cunningham, J.; Shank, J.

    2004-01-01

    To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner

  9. IEEE recommended practices for seismic qualification of Class 1E equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    The IEEE has developed this document to provide direction for developing programs to seismically qualify Class 1E equipment for nuclear power generating stations. It supplements IEEE Std 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for equipment qualification. The Class 1E equipment to be qualified by produres or standards established by this document are of many forms, characteristics, and materials; therefore, the document presents many acceptable methods with the intent of permitting the user to make a judicious selection from among the various options. In making such a selection, the user should choose those that best meet a particular equipment's requirements. Further, in using this document as a specification for the purchase of equipment, the many options should also be recognized and the document invoked accordingly. It is recommended that the need for specific standards for the seismic qualifiction of particular kinds of equipment be evaluated by those responsible for such documents and that consideration be given to the application of particular methods from these documents which are most suitable

  10. Optimal Analytical Solution for a Capacitive Wireless Power Transfer System with One Transmitter and Two Receivers

    Directory of Open Access Journals (Sweden)

    Ben Minnaert

    2017-09-01

    Full Text Available Wireless power transfer from one transmitter to multiple receivers through inductive coupling is slowly entering the market. However, for certain applications, capacitive wireless power transfer (CWPT using electric coupling might be preferable. In this work, we determine closed-form expressions for a CWPT system with one transmitter and two receivers. We determine the optimal solution for two design requirements: (i maximum power transfer, and (ii maximum system efficiency. We derive the optimal loads and provide the analytical expressions for the efficiency and power. We show that the optimal load conductances for the maximum power configuration are always larger than for the maximum efficiency configuration. Furthermore, it is demonstrated that if the receivers are coupled, this can be compensated for by introducing susceptances that have the same value for both configurations. Finally, we numerically verify our results. We illustrate the similarities to the inductive wireless power transfer (IWPT solution and find that the same, but dual, expressions apply.

  11. The evaluation of equipment and Instrumentation Reliability Factors on Power Reactor

    International Nuclear Information System (INIS)

    Supriatna, Piping; Karlina, Itjeu; Widagdo, Suharyo; Santosa, Kussigit; Darlis; Sudiyono, Bambang; Yuniyanta, Sasongko; Sudarmin

    1999-01-01

    Equipment and instrumentation reliability on type power reactor control room was determined by its pattern and design. the principle of ergonomy applied on equipment and instrumentation layout in this ABWR type reactor are geometric pattern appropriate with economic body motion, average anthropometry data of operator especially operator hand-reach, range of vision, angle of vision, lighting, color arrangement and harmony as will as operator case in operating the equipment system. Limitation criteria of the parameter mentioned above are based on EPRI NP-3659, NURG 0700, and NUREG/CR-3331 documents. Besides that, the (working) physical environment parameter factor of the control room must be designed in order to fulfil the standard criteria of ergonomic condition based on NUREG-0800. The reliability evaluation of equipment and instrumentation system also occurs observed from man machine interaction side which happen between operator and equipment and instrumentation in the ABWR type power reactor control room. From the MMI analysis can be known the working failure possibility which is caused by the operator. The evaluation result of equipment and instrumentation reliability on ABWR type power reactor control room showed that the design of this ABWR control room is good and fulfils the ergonomy standard criteria have been determined

  12. IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

  13. Operational planning optimization of steam power plants considering equipment failure in petrochemical complex

    International Nuclear Information System (INIS)

    Luo, Xianglong; Zhang, Bingjian; Chen, Ying; Mo, Songping

    2013-01-01

    Highlights: ► We develop a systematic programming methodology to address equipment failure. ► We classify different operation conditions into real periods and virtual periods. ► The formulated MILP models guarantee cost reduction and enough operation safety. ► The consideration of reserving operation redundancy is effective. - Abstract: One or more interconnected steam power plants (SPPs) are constructed in a petrochemical complex to supply utility energy to the process. To avoid large economic penalties or process shutdowns, these SPPs should be flexible and reliable enough to meet the process energy requirement under varying conditions. Unexpected utility equipment failure is inevitable and difficult to be predicted. Most of the conventional methods are based on the assumption that SPPs do not experience any kind of equipment failure. Unfortunately, a process shutdown cannot be avoided when equipment fails unexpectedly. In this paper, a systematic methodology is presented to minimize the total cost under normal conditions while reserving enough flexibility and safety for unexpected equipment failure conditions. The proposed method transforms the different conditions into real periods to indicate normal scenarios and virtual periods to indicate unexpected equipment failure scenarios. The optimization strategy incorporating various operation redundancy scheduling, the transition constraints from equipment failure conditions to normal conditions, and the boiler load increase behavior modeling are presented to save cost and guarantee operation safety. A detailed industrial case study shows that the proposed systematic methodology is effective and practical in coping with equipment failure conditions with only few additional cost penalties

  14. Protecting power equipment against magnetohydrodynamic effects (MHD of electromagnetic pulses (EMP

    Directory of Open Access Journals (Sweden)

    Gurevich Vladimir

    2015-01-01

    Full Text Available The article is devoted to the effects of geomagnetic-induced currents (GIC on electrical equipment of power systems and analyzes technical measures for protection against such effects. It is noted that the difference between highaltitude nuclear detonation and solar storm GICs forces applying different methods of electrical equipment protection. It also illustrates that enhancement of transformer immunity to GICs without saturation prevention is not an effective measure to protect the power system. The article offers a special relay designed for fast disconnection of the transformer under GICs.

  15. Fault diagnosis of nuclear-powered equipment based on HMM and SVM

    International Nuclear Information System (INIS)

    Yue Xia; Zhang Chunliang; Zhu Houyao; Quan Yanming

    2012-01-01

    For the complexity and the small fault samples of nuclear-powered equipment, a hybrid HMM/SVM method was introduced in fault diagnosis. The hybrid method has two steps: first, HMM is utilized for primary diagnosis, in which the range of possible failure is reduced and the state trends can be observed; then faults can be recognized taking the advantage of the generalization ability of SVM. Experiments on the main pump failure simulator show that the HMM/SVM system has a high recognition rate and can be used in the fault diagnosis of nuclear-powered equipment. (authors)

  16. Industry sector analysis, Mexico: Electric power production and distribution equipment. Export Trade Information

    International Nuclear Information System (INIS)

    Wood, J.S.; Miller, R.W.

    1988-09-01

    The Industry Sector Analyses (I.S.A.) for electric power production and distribution equipment contains statistical and narrative information on projected market demand, end-users, receptivity of Mexican consumers to U.S. products, the competitive situation - Mexican production, total import market, U.S. market position, foreign competition, and competitive factors, and market access - Mexican tariffs, non-tariff barriers, standards, taxes and distribution channels. The I.S.A. provides the United States industry with meaningful information regarding the Mexican market for electric power production and distribution equipment

  17. Optimal power allocation of a single transmitter-multiple receivers channel in a cognitive sensor network

    KAUST Repository

    Ayala Solares, Jose Roberto; Rezki, Zouheir; Alouini, Mohamed-Slim

    2012-01-01

    The optimal transmit power of a wireless sensor network with one transmitter and multiple receivers in a cognitive radio environment while satisfying independent peak, independent average, sum of peak and sum of average transmission rate constraints

  18. Predictive Maintenance of Power Substation Equipment by Infrared Thermography Using a Machine-Learning Approach

    Directory of Open Access Journals (Sweden)

    Irfan Ullah

    2017-12-01

    Full Text Available A variety of reasons, specifically contact issues, irregular loads, cracks in insulation, defective relays, terminal junctions and other similar issues, increase the internal temperature of electrical instruments. This results in unexpected disturbances and potential damage to power equipment. Therefore, the initial prevention measures of thermal anomalies in electrical tools are essential to prevent power-equipment failure. In this article, we address this initial prevention mechanism for power substations using a computer-vision approach by taking advantage of infrared thermal images. The thermal images are taken through infrared cameras without disturbing the working operations of power substations. Thus, this article augments the non-destructive approach to defect analysis in electrical power equipment using computer vision and machine learning. We use a total of 150 thermal pictures of different electrical equipment in 10 different substations in operating conditions, using 300 different hotspots. Our approach uses multi-layered perceptron (MLP to classify the thermal conditions of components of power substations into “defect” and “non-defect” classes. A total of eleven features, which are first-order and second-order statistical features, are calculated from the thermal sample images. The performance of MLP shows initial accuracy of 79.78%. We further augment the MLP with graph cut to increase accuracy to 84%. We argue that with the successful development and deployment of this new system, the Technology Department of Chongqing can arrange the recommended actions and thus save cost in repair and outages. This can play an important role in the quick and reliable inspection to potentially prevent power substation equipment from failure, which will save the whole system from breakdown. The increased 84% accuracy with the integration of the graph cut shows the efficacy of the proposed defect analysis approach.

  19. Evaluation tests of the Instrumentation and Control equipment to use in nuclear power plants: its contribution to the improvement and quality certification of the Brazilian equipment

    International Nuclear Information System (INIS)

    Menezes, R.H.M. de; Peluso, M.A.V.

    1984-01-01

    This work presents the procedures used to evaluate Instrumentation Control equipment and reports the experience of integration among instrument user, manufacturer and test institution. It covers tests for equipments for conventional user and for specific application in Nuclear Power Stations. (Author) [pt

  20. Development of fragility descriptions of equipment for seismic risk assessment of nuclear power plants

    International Nuclear Information System (INIS)

    Hardy, G.S.; Campbell, R.D.

    1983-01-01

    Probabilistic risk assessment (PRA) of a nuclear power plant for postulated hazard requires the development of fragility relationships for the plants' safety related equipment. The objective of this paper is to present some general results and conclusions concerning the development of these seismic fragility levels. Participation in fragility-related research and experience gained from the completion of several PRA studies of a variety of nuclear power plants have provided much insight as to the most vulnerable equipment and the most efficient use of resources for development of fragilities. Plants studied had seismic design bases ranging from very simple equivalent static analysis for some of the earlier plants to state-of-the-art complex multimode dyanamic analyses for plants currently under construction. Increased sophistication and rigor in seismic qualification of equipment has resulted for the most part in increased seismic resistance. The majority of equipment has been found, however, to possess more than adequate resistance to seismic loading regardless of the degree of sophistication utilized in design as long as seismic loading was included in the design process. This paper presents conclusions of the authors as to which items of equipment typically require an individual ''plant-specific'' fragility analysis and which can be treated in a generic fashion. In addition, general conclusions on the relative seismic capacity levels and most frequent failure modes are summarized for generic equipment groups

  1. Application and issues of online maintenance for equipment of nuclear power plants

    International Nuclear Information System (INIS)

    Higasa, Hisakazu

    2011-01-01

    The maintenance systems for long-term safety and repair costs reduction of equipment of nuclear power plants are stated. Planned maintenance contained the breakdown maintenance (BM) and the preventive maintenance, which consists of the time based maintenance (MBM) and the condition based maintenance (CBM). Explained are the characteristics of equipments, maintenance methods, maintenance solutions and the self-evaluation maintenance power, damage mechanism and solutions, and monitoring tools and application. Stated are the maintenance system and application of monitoring technology, periodical maintenance, application of diagnosis, vibration monitoring techniques, decision of vibration monitoring, and application of monitoring techniques for improvement of maintenance. Illustrated are realization of planned maintenance by reorganization of maintenance, a trend of maintenance of equipments, table of classified maintenance systems, change of maintenance program, maintenance data and investigation of damage mechanism, examples of self-evaluation maintenance power, examples of analysis of damage of parts of equipments, evaluation of rotating machines by vibration method, examples of results of diagnosis of bearing of rotating machines, online maintenance system of Asahi Kasei Engineering Corporation, degradation pattern of pomp, estimation of lifetime by total vibration and vibration on acceleration, and improvement of equipments. (S.Y.)

  2. Anchorage of equipment - requirements and verification methods with emphasis on equipment of existing and constructed VVER-type nuclear power plants

    International Nuclear Information System (INIS)

    Masopust, R.

    1999-01-01

    Criteria and verification methods which are recommended for use in the capacity evaluation of anchorage of safety-related equipment at WWER-type nuclear power plants are presented. Developed in compliance with the relevant basic standards documents specifically for anchorage of WWER-type equipment components, the criteria and methods cover different types of anchor bolts and other anchorage elements which are typical of existing, constructed, or reconstructed WWER-type nuclear power plants

  3. Comparison of Square and Radial Geometries for High Intensity Laser Power Beaming Receivers

    Science.gov (United States)

    Raible, Daniel E.; Fast, Brian R.; Dinca, Dragos; Nayfeh, Taysir H.; Jalics, Andrew K.

    2012-01-01

    In an effort to further advance a realizable form of wireless power transmission (WPT), high intensity laser power beaming (HILPB) has been developed for both space and terrestrial applications. Unique optical-to-electrical receivers are employed with near infrared (IR-A) continuous-wave (CW) semiconductor lasers to experimentally investigate the HILPB system. In this paper, parasitic feedback, uneven illumination and the implications of receiver array geometries are considered and experimental hardware results for HILPB are presented. The TEM00 Gaussian energy profile of the laser beam presents a challenge to the effectiveness of the receiver to perform efficient photoelectric conversion, due to the resulting non-uniform illumination of the photovoltaic cell arrays. In this investigation, the geometry of the receiver is considered as a technique to tailor the receiver design to accommodate the Gaussian beam profile, and in doing so it is demonstrated that such a methodology is successful in generating bulk receiver output power levels reaching 25 W from 7.2 sq cm of photovoltaic cells. These results are scalable, and may be realized by implementing receiver arraying and utilizing higher power source lasers to achieve a 1.0 sq m receiver capable of generating over 30 kW of electrical power. This type of system would enable long range optical "refueling" of electric platforms, such as MUAV s, airships, robotic exploration missions and provide power to spacecraft platforms which may utilize it to drive electric means of propulsion. In addition, a smaller HILPB receiver aperture size could be utilized to establish a robust optical communications link within environments containing high levels of background radiance, to achieve high signal to noise ratios.

  4. Ultra-low power high precision magnetotelluric receiver array based customized computer and wireless sensor network

    Science.gov (United States)

    Chen, R.; Xi, X.; Zhao, X.; He, L.; Yao, H.; Shen, R.

    2016-12-01

    Dense 3D magnetotelluric (MT) data acquisition owns the benefit of suppressing the static shift and topography effect, can achieve high precision and high resolution inversion for underground structure. This method may play an important role in mineral exploration, geothermal resources exploration, and hydrocarbon exploration. It's necessary to reduce the power consumption greatly of a MT signal receiver for large-scale 3D MT data acquisition while using sensor network to monitor data quality of deployed MT receivers. We adopted a series of technologies to realized above goal. At first, we designed an low-power embedded computer which can couple with other parts of MT receiver tightly and support wireless sensor network. The power consumption of our embedded computer is less than 1 watt. Then we designed 4-channel data acquisition subsystem which supports 24-bit analog-digital conversion, GPS synchronization, and real-time digital signal processing. Furthermore, we developed the power supply and power management subsystem for MT receiver. At last, a series of software, which support data acquisition, calibration, wireless sensor network, and testing, were developed. The software which runs on personal computer can monitor and control over 100 MT receivers on the field for data acquisition and quality control. The total power consumption of the receiver is about 2 watts at full operation. The standby power consumption is less than 0.1 watt. Our testing showed that the MT receiver can acquire good quality data at ground with electrical dipole length as 3 m. Over 100 MT receivers were made and used for large-scale geothermal exploration in China with great success.

  5. Investigations of heat-hydraulic noises in the equipment for creation of power-saving technologies

    International Nuclear Information System (INIS)

    Proskuryakov, K.N.

    2000-01-01

    The results of experimental and theoretical studies on the parameters of vibroacoustic signals, originating in the TPP and NPP thermal energy equipment, are presented. The methods for calculation and identification of the heat-hydraulic perturbation sources, intended for improving the means of early diagnostics of anomalies in the technological process, forecasting their development, increasing the maintenance work efficiency and operational safety, as well as for creating power-saving technologies in the power engineering, are developed [ru

  6. Power Product Equipment Technician: Outboard-Engine Systems and Service. Teacher Edition [and] Student Edition.

    Science.gov (United States)

    Hilley, Robert

    This curriculum guide contains teacher and student materials for a course on outboard-engine boat systems and service for power product equipment technician occupations. The course contains the following four units of instruction: (1) Outboard-Engine Design and Identification; (2) Operation and Service of Engine-Support Systems; (3) Operation and…

  7. Power Product Equipment Technician: Outboard-Engine Boat Systems. Teacher Edition [and] Student Edition.

    Science.gov (United States)

    Hilley, Robert

    This curriculum guide contains teacher and student materials for a course on outboard-engine boat systems for power product equipment technician occupations. The course contains the following three units of instruction: (1) Orientation to Outboard-Engine Boat Systems and Rigging; (2) Trailers and Safe Towing and Boat Operation; and (3) Seasonal…

  8. 30 CFR 56.12005 - Protection of power conductors from mobile equipment.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Protection of power conductors from mobile equipment. 56.12005 Section 56.12005 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-SURFACE METAL AND NONMETAL...

  9. 30 CFR 57.12005 - Protection of power conductors from mobile equipment.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Protection of power conductors from mobile equipment. 57.12005 Section 57.12005 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND...

  10. Production capacity of equipment for medium and large hydroelectric power plant in China

    Energy Technology Data Exchange (ETDEWEB)

    Huang Shenyang [Ministry of Electric Power, Beijing (China). Bureau of Electric Power Machinery

    1995-07-01

    This document presents an overview on the production capacity of equipment for medium and large hydroelectric power plant in China. The document approaches general aspects, production capability and testing facilities related to Francis, Kaplan, tubular and impulse hydroelectric generating sets, and the introduction of main manufacturers as well.

  11. Harmonics in power systems of ships with electrical propulsion drives. Effects on the equipment

    Energy Technology Data Exchange (ETDEWEB)

    Lehtonen, M [VTT Energy, Espoo (Finland). Energy Systems

    1996-11-01

    In this report the effect of harmonics on the power system equipment and loads, with special attention given to the circumstances in ships, is discussed. Some guidelines are given for the computation of additional harmonic losses in power cables and transformers. It is also shown, that if the system is rich in harmonics, these losses must be taken into account when sizing the equipment. The effect of harmonics on electrical machines is also discussed. The influence on induction machines is usually small. However, in large synchronous machines a significant degree of harmonic losses may be expected. Especially in the high voltage system the harmonics must be taken into account when selecting the machine ratings. Also the harmonic resonances, which may arise when using reactive power compensation capacitors, are discussed. Due to the risk of harmonic resonances, the use of capacitors is not recommended in marine power systems. Also the immunity of different load devices to harmonic distortion is discussed. The equipment considered are resistive loads, discharge lamps, universal machines and electronic equipment. Finally a brief survey is given on the standards and recommendations for the maximum distortion levels allowed. (author)

  12. Solar power satellite rectenna design study: Directional receiving elements and parallel-series combining analysis

    Science.gov (United States)

    Gutmann, R. J.; Borrego, J. M.

    1978-01-01

    Rectenna conversion efficiencies (RF to dc) approximating 85 percent were demonstrated on a small scale, clearly indicating the feasibility and potential of efficiency of microwave power to dc. The overall cost estimates of the solar power satellite indicate that the baseline rectenna subsystem will be between 25 to 40 percent of the system cost. The directional receiving elements and element extensions were studied, along with power combining evaluation and evaluation extensions.

  13. METHODOLOGY OF DETERMINATION OF QUALITY INDEX OF MAINTENANCE SERVICE SYSTEM OF POWER EQUIPMENT OF TRACTION SUBSTATIONS

    Directory of Open Access Journals (Sweden)

    O.O. Matusevych

    2016-03-01

    Full Text Available Purpose. The purpose of this paper is development of methodology for definition of a quality system of maintenance and repair (M and P power equipment of traction substations (TS of electrified railways operating under conditions of uncertainty based on expert information. Methodology. The basic tenets of the theory of fuzzy sets and marks, linguistic and interval estimates of experts were applied to solve this problem. Results. Analysis of the existing diversity of approaches to development of modern methods of improvement of M and P allows us to conclude that the improvement in the quality of the system is achieved by solving individual problems increase the operational reliability of power equipment of traction substations in the following main interrelated areas. There are technical, economic and organizational. The basis of the quality evaluation system is initial data and expertise developed version of the document formalized quality evaluation of electrical equipment of traction substations by experts. The choice of determining the level of Quality service system based on the marks, linguistic and interval estimates of experts, which are reflected in quantitative and / or qualitative form was done. The possible options for expert data presentation and their corresponding quantitative methods of calculating the integral index of quality improvement system maintenance and P of traction substations were described. The methodology and the method of assessing the quality of system maintenance and P of TS allows quickly respond to changing operating conditions of power equipment of traction substations, and to determine the most effective strategies for maintenance of electrical and P TS under conditions of uncertainty functioning distance electricity. Originality. The method of a systematic approach to improve the quality of the system maintenance and P of power equipment of traction substation under conditions of uncertainty based on expert

  14. Guideline on dependability management for the power industry: detailed description of international power plant equipment dependability indicators

    International Nuclear Information System (INIS)

    Procaccia, H.; Silberberg, S.

    1997-01-01

    Dependability Management involves the management of reliability, availability maintainability and maintenance support, and in the power industry is necessary to ensure that plant meets the Reliability, Availability and Maintainability (RAM) targets set by the Utilities. In 1993, a joint Standard on Dependability Programme Management - Part 1: Dependability Programme Management), ISO 9000-': 1993 (Quality Management and Quality Assurance Standards - Part 4: Guide to Dependability Programme Management). UNIPEDE established a group of experts (Nulethermaint) to produce guidelines on its implementation specifically for use in the power industry. The present document comprises Part 2 OF THE UNIPEDE plant performance indicators and can be applied to both nuclear and fossil plant. There are five different equipment dependability indicators, all relating to equipment maintenance activities and the impact that these activities have on the loss of both system function and unit capability. Per year, each of the indicators can be applied separately to both preventive maintenance and corrective maintenance, giving rise to as many as ten indicator values for each item of equipment. Used in this way, the indicators provide a comprehensive picture of the maintenance strategy employed for key pieces of equipment, and its effectiveness. They are, therefore, a valuable managerial tool for improving maintenance activities at the unit level within a utility. This document provides guidance on the division of both nuclear and fossil power plant into their component parts and in each case the types of equipment having the most dominant effect on dependability are identified. These are the items which merit the greatest attention with regard to the equipment dependability indicators. (authors)

  15. Performance comparison of different thermodynamic cycles for an innovative central receiver solar power plant

    Science.gov (United States)

    Reyes-Belmonte, Miguel A.; Sebastián, Andrés; González-Aguilar, José; Romero, Manuel

    2017-06-01

    The potential of using different thermodynamic cycles coupled to a solar tower central receiver that uses a novel heat transfer fluid is analyzed. The new fluid, named as DPS, is a dense suspension of solid particles aerated through a tubular receiver used to convert concentrated solar energy into thermal power. This novel fluid allows reaching high temperatures at the solar receiver what opens a wide range of possibilities for power cycle selection. This work has been focused into the assessment of power plant performance using conventional, but optimized cycles but also novel thermodynamic concepts. Cases studied are ranging from subcritical steam Rankine cycle; open regenerative Brayton air configurations at medium and high temperature; combined cycle; closed regenerative Brayton helium scheme and closed recompression supercritical carbon dioxide Brayton cycle. Power cycle diagrams and working conditions for design point are compared amongst the studied cases for a common reference thermal power of 57 MWth reaching the central cavity receiver. It has been found that Brayton air cycle working at high temperature or using supercritical carbon dioxide are the most promising solutions in terms of efficiency conversion for the power block of future generation by means of concentrated solar power plants.

  16. Design of a compact low-power human-computer interaction equipment for hand motion

    Science.gov (United States)

    Wu, Xianwei; Jin, Wenguang

    2017-01-01

    Human-Computer Interaction (HCI) raises demand of convenience, endurance, responsiveness and naturalness. This paper describes a design of a compact wearable low-power HCI equipment applied to gesture recognition. System combines multi-mode sense signals: the vision sense signal and the motion sense signal, and the equipment is equipped with the depth camera and the motion sensor. The dimension (40 mm × 30 mm) and structure is compact and portable after tight integration. System is built on a module layered framework, which contributes to real-time collection (60 fps), process and transmission via synchronous confusion with asynchronous concurrent collection and wireless Blue 4.0 transmission. To minimize equipment's energy consumption, system makes use of low-power components, managing peripheral state dynamically, switching into idle mode intelligently, pulse-width modulation (PWM) of the NIR LEDs of the depth camera and algorithm optimization by the motion sensor. To test this equipment's function and performance, a gesture recognition algorithm is applied to system. As the result presents, general energy consumption could be as low as 0.5 W.

  17. Power management of a wind energy conversion system equipped by DFIG

    Directory of Open Access Journals (Sweden)

    Iman Zangiabadi

    2016-06-01

    Full Text Available Today wind is one of the attractive points of energy area which has got the noticeable amount of investment and studies in this field. Considering the importance of the wind energy and its potentials as one of the renewable energy sources, in this paper managing the production of active and reactive powers of a wind energy conversion system equipped with DFIG has been studied. In this regard, a structure based on vector control is offered to achieve an independent control of active and reactive powers. The strategy of managing the production of active and reactive power is applied to network by rotor side converter of a DFIG. The production of active power according to the maximum power point taking (MPPT strategy to get a maximum power of the wind energy has been done and also improvement of power quality based on strategies of power factor correction and harmonics reduction have been arranged for a power network. In order to evaluate the performance of the proposed method, a DFIG connected with a power network in different conditions of the reactive load has been simulated by MATLAB software.Obviously, the results state the proper operation of the power control of wind energy converting system , improvement of the network power factor, and Reduction of harmonic current of network based on the proposed method.

  18. Financing of power supply systems and pollution control equipment. Models, dimensions, developments

    Energy Technology Data Exchange (ETDEWEB)

    Radtke, G; Raabe, G

    1988-11-01

    The authors explain the bankers' point of view of the financial and economic aspects of developments in the energy sector, discussing the financing of natural gas pipelines (Muro, Megal, etc.), of nuclear power plant construction, of projects in the oil supply sector, and of pollution abatement measures and equipment for the power industry and other industries. The different financial situations of small firms or large firms supplying pollution control equipment are discussed referring to the financing schemes to be set up, explaining among other things the profitability assessment taking into account long-term development or delays in return on capital investment from borrowed funds as induced, e.g., by delays in the licensing procedure. Future demand for borrowed capital for pollution control or nuclear power plant development is difficult to assess by the banking circles. (orig./RST).

  19. Remote-automated inspection and maintenance of nuclear power plant equipment

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, Masayoshi; Nakano, Yoshiyuki

    1984-12-01

    Employing remote-control inspection and maintenance equipment in nuclear power plants increases the plant availability by decreasing the annual shutdown time (outage), as well as radiation exposure and man-power. This paper presents an outline of the latest designs for an automatic refueling machine, a control rod drive handling machine, a fuel preparation machine, and a main steam line plug, which were supplied to the Fukushima Dai-Ni No. 2 Plant of the Tokyo Electric Power Co., Inc. (Fukushima 2-2). Also, the up-to-date developments of other new automatic machines, such as a CRD disassembly and cleaning system, spent fuel channel box volume reduction equipment, and robotics for nuclear plant use are presented.

  20. Wireless power transmission to an electromechanical receiver using low-frequency magnetic fields

    International Nuclear Information System (INIS)

    Challa, Vinod R; Arnold, David P; Mur-Miranda, Jose Oscar

    2012-01-01

    A near-field, electrodynamically coupled wireless power transmission system is presented that delivers electrical power from a transmitter coil to a compact electromechanical receiver. The system integrates electromechanical energy conversion and mechanical resonance to deliver power over a range of distances using low-amplitude, low-frequency magnetic fields. Two different receiver orientations are investigated that rely on either the force or the torque induced on the receiver magnet at separation distances ranging from 2.2 to 10.2 cm. Theoretical models for each mode compare the predicted performance with the experimental results. For a 7.1 mA pk sinusoidal current supplied to a transmitter coil with a 100 cm diameter, the torque mode receiver orientation has a maximum power transfer of 150 μW (efficiency of 12%) at 2.2 cm at its resonance frequency of 38.4 Hz. For the same input current to the transmitter, the force mode receiver orientation has a maximum power transfer of 37 μW (efficiency of 4.1%) at 3.1 cm at its resonance frequency of 38.9 Hz. (paper)

  1. Compensation of Reactive Power from Wind Turbines with Power Electronics Equipment

    DEFF Research Database (Denmark)

    Pedersen, Jørgen Kaas

    1996-01-01

    Wind turbines with induction generators consume reactive power. Apart from the no load consumption, which is nearing constant and is being compensated for using capacitors, the consumption of reactive power varies almost proportional with the power production, which can vary immensely. Except tha...

  2. 30 CFR 75.1710-1 - Canopies or cabs; self-propelled diesel-powered and electric face equipment; installation...

    Science.gov (United States)

    2010-07-01

    ... and electric face equipment; installation requirements. (a) Except as provided in paragraph (f) of this section, all self-propelled diesel-powered and electric face equipment, including shuttle cars... and electric face equipment; installation requirements. 75.1710-1 Section 75.1710-1 Mineral Resources...

  3. Ideal Operation of a Photovoltaic Power Plant Equipped with an Energy Storage System on Electricity Market

    OpenAIRE

    Markku Järvelä; Seppo Valkealahti

    2017-01-01

    There is no natural inertia in a photovoltaic (PV) generator and changes in irradiation can be seen immediately at the output power. Moving cloud shadows are the dominant reason for fast PV power fluctuations taking place typically within a minute between 20 to 100% of the clear sky value roughly 100 times a day, on average. Therefore, operating a utility scale grid connected PV power plant is challenging. Currently, in many regions, renewable energy sources such as solar and wind receive fee...

  4. Maintenance management of emergency power supply equipment (uninterruptible power supply) in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Nishida, Kyosuke; Hiyama, Hisao; Shibata, Satomi; Iwasaki, Shogo; Inami, Shinichi

    2009-01-01

    Uninterruptible power supply systems are installed in the Tokai reprocessing plant in preparation for the emergency case that the commercial power supply is stopped by an accidental or intentional interruption in the supply of electricity. The uninterruptible power supply system particularly provides a temporary power source to the important devices for the radiation control of nuclear critical monitoring in the plant. Thus, the system is potentially important and essential for nuclear plants. The paper reports the current activities such as regular inspections, replacement of parts and system update, to maintain the function of uninterruptible power supply systems. (author)

  5. Three-phase receiving coil of wireless power transmission system for gastrointestinal robot

    Science.gov (United States)

    Jia, Z. W.; Jiang, T.; Liu, Y.

    2017-11-01

    Power shortage is the bottleneck for the wide application of gastrointestinal (GI) robot. Owing to the limited volume and free change of orientation of the receiving set in GI trace, the optimal of receiving set is the key point to promote the transmission efficiency of wireless power transmission system. A new type of receiving set, similar to the winding of three-phase asynchronous motor, is presented and compared with the original three-dimensional orthogonal coil. Considering the given volume and the space utilization ratio, the three-phase and the three-orthogonal ones are the parameters which are optimized and compared. Both the transmission efficiency and stability are analyzed and verified by in vitro experiments. Animal experiments show that the new one could provide at least 420 mW power in volume of Φ11 × 13mm with a uniformity of 78.3% for the GI robot.

  6. Verification of 3G and 4G Received Power Measurements in a Crowdsourcing Android App

    DEFF Research Database (Denmark)

    Lauridsen, Mads; Rodriguez, Ignacio; Mikkelsen, Lars Møller

    2016-01-01

    . In this paper we verify the crowdsourcing Android application NetMap’s ability to measure LTE Reference Signal Received Power by analyzing the Root Mean Squared Error, being 2-3 dB, and cross-correlation coefficient, being above 0.8, with measurements obtained by use of a professional radio network scanner......Many crowdsourcing Android applications are available for measuring network Key Performance Indicators such as received power, latency, and throughput. The data is useful for end-users, researchers, and Mobile Network Operators, but unfortunately the applications’ accuracy are rarely verified...... and measurement phones. In addition, the application is applicable, but less accurate, for 3G Received Signal Code Power measurements. The studies are made for various device speeds and in different scenarios including indoor, urban, and highway, where the NetMap application is showed to perform well....

  7. An Integrated Chip High-Voltage Power Receiver for Wireless Biomedical Implants

    Directory of Open Access Journals (Sweden)

    Vijith Vijayakumaran Nair

    2015-06-01

    Full Text Available In near-field wireless-powered biomedical implants, the receiver voltage largely overrides the compliance of low-voltage power receiver systems. To limit the induced voltage, generally, low-voltage topologies utilize limiter circuits, voltage clippers or shunt regulators, which are power-inefficient methods. In order to overcome the voltage limitation and improve power efficiency, we propose an integrated chip high-voltage power receiver based on the step down approach. The topology accommodates voltages as high as 30 V and comprises a high-voltage semi-active rectifier, a voltage reference generator and a series regulator. Further, a battery management circuit that enables safe and reliable implant battery charging based on analog control is proposed and realized. The power receiver is fabricated in 0.35-μm high-voltage Bipolar-CMOS-DMOStechnology based on the LOCOS0.35-μm CMOS process. Measurement results indicate 83.5% power conversion efficiency for a rectifier at 2.1 mA load current. The low drop-out regulator based on the current buffer compensation and buffer impedance attenuation scheme operates with low quiescent current, reduces the power consumption and provides good stability. The topology also provides good power supply rejection, which is adequate for the design application. Measurement results indicate regulator output of 4 ± 0.03 V for input from 5 to 30 V and 10 ± 0.05 V output for input from 11 to 30 V with load current 0.01–100 mA. The charger circuit manages the charging of the Li-ion battery through all if the typical stages of the Li-ion battery charging profile.

  8. Communications received from members regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1993-05-01

    The document reproduces the letter dated 11 February 1993 from the Resident Representative of the Russian Federation to the Agency concerning the export of nuclear material and of certain categories of equipment and other material

  9. Concentrating Solar Power Central Receiver Panel Component Fabrication and Testing FINAL REPORT

    Energy Technology Data Exchange (ETDEWEB)

    McDowell, Michael W [Pratt & Whitney Rocketdyne; Miner, Kris [Pratt & Whitney Rocketdyne

    2013-03-30

    The objective of this project is to complete a design of an advanced concentrated solar panel and demonstrate the manufacturability of key components. Then confirm the operation of the key components under prototypic solar flux conditions. This work is an important step in reducing the levelized cost of energy (LCOE) from a central receiver solar power plant. The key technical risk to building larger power towers is building the larger receiver systems. Therefore, this proposed technology project includes the design of an advanced molten salt prototypic sub-scale receiver panel that can be utilized into a large receiver system. Then complete the fabrication and testing of key components of the receive design that will be used to validate the design. This project shall have a significant impact on solar thermal power plant design. Receiver panels of suitable size for utility scale plants are a key element to a solar power tower plant. Many subtle and complex manufacturing processes are involved in producing a reliable, robust receiver panel. Given the substantial size difference between receiver panels manufactured in the past and those needed for large plant designs, the manufacture and demonstration on prototype receiver panel components with representative features of a full-sized panel will be important to improving the build process for commercial success. Given the thermal flux limitations of the test facility, the panel components cannot be rendered full size. Significance changes occurred in the projects technical strategies from project initiation to the accomplishments described herein. The initial strategy was to define cost improvements for the receiver, design and build a scale prototype receiver and test, on sun, with a molten salt heat transport system. DOE had committed to constructing a molten salt heat transport loop to support receiver testing at the top of the NSTTF tower. Because of funding constraints this did not happen. A subsequent plan to

  10. After-hours Power Status of Office Equipment in the USA

    Energy Technology Data Exchange (ETDEWEB)

    Webber, Carrie A.; Roberson, Judy A.; McWhinney, Marla C.; Brown,Richard E.; Pinckard, Margaret J.; Busch, John F.

    2005-10-13

    Office equipment is expected to be the fastest-growingsegment of commercial energy use over the next 20 years, yet many aspectsof office equipment energy use are poorly understood. User behavior, suchas turning off devices at night or enabling power management, influencesenergy use to a great extent. The computing environment also plays a roleboth in influencing user behavior and in the success of power management.Information about turn-off rates and power management rates for officeequipment was collected through a series of after-hours audits incommercial buildings. Sixteen businesses were recruited, includingoffices (small, medium and large offices in a variety of industries),schools, and medical buildings in California, Georgia, and Pennsylvania.The types and power states of office equipment found in these buildingswere recorded and analyzed. This article presents these data forcomputers, monitors, printers, copiers, fax machines, scanners andmulti-function devices. These data can be used to improve estimates ofboth energy consumption for these devices and savings from energyconservation efforts.

  11. The process control and management on equipment qualification of nuclear power plant

    International Nuclear Information System (INIS)

    Liu Dong; Wang Hongyin; Zhang Yong

    2013-01-01

    The equipment qualification (EQ) to the safety class equipment is an important safety measure for the nuclear power plants (NPP), and also reflects the nuclear safety culture. Along with the continuous constructions of NPP in China, it has become an important issue for NPP engineering company and equipment suppliers how to effectively establish standard EQ process control and management, and provide sufficient technical arrangements to maintain this EQ management system. This paper summarizes three process of EQ including Design Input, EQ Establishment and EQ Maintenance, proposes the measures and key points for EQ process control and management in phase of NPP construction, and introduces the documents management during the whole process of EQ. (authors)

  12. On reliability and maintenance modelling of ageing equipment in electric power systems

    International Nuclear Information System (INIS)

    Lindquist, Tommie

    2008-04-01

    Maintenance optimisation is essential to achieve cost-efficiency, availability and reliability of supply in electric power systems. The process of maintenance optimisation requires information about the costs of preventive and corrective maintenance, as well as the costs of failures borne by both electricity suppliers and customers. To calculate expected costs, information is needed about equipment reliability characteristics and the way in which maintenance affects equipment reliability. The aim of this Ph.D. work has been to develop equipment reliability models taking the effect of maintenance into account. The research has focussed on the interrelated areas of condition estimation, reliability modelling and maintenance modelling, which have been investigated in a number of case studies. In the area of condition estimation two methods to quantitatively estimate the condition of disconnector contacts have been developed, which utilise results from infrared thermography inspections and contact resistance measurements. The accuracy of these methods were investigated in two case studies. Reliability models have been developed and implemented for SF6 circuit-breakers, disconnector contacts and XLPE cables in three separate case studies. These models were formulated using both empirical and physical modelling approaches. To improve confidence in such models a Bayesian statistical method incorporating information from the equipment design process was also developed. This method was illustrated in a case study of SF6 circuit-breaker operating rods. Methods for quantifying the effect of maintenance on equipment condition and reliability have been investigated in case studies on disconnector contacts and SF6 circuit-breakers. The input required by these methods are condition measurements and historical failure and maintenance data, respectively. This research has demonstrated that the effect of maintenance on power system equipment may be quantified using available data

  13. 1 mm3-sized optical neural stimulator based on CMOS integrated photovoltaic power receiver

    Science.gov (United States)

    Tokuda, Takashi; Ishizu, Takaaki; Nattakarn, Wuthibenjaphonchai; Haruta, Makito; Noda, Toshihiko; Sasagawa, Kiyotaka; Sawan, Mohamad; Ohta, Jun

    2018-04-01

    In this work, we present a simple complementary metal-oxide semiconductor (CMOS)-controlled photovoltaic power-transfer platform that is suitable for very small (less than or equal to 1-2 mm) electronic devices such as implantable health-care devices or distributed nodes for the Internet of Things. We designed a 1.25 mm × 1.25 mm CMOS power receiver chip that contains integrated photovoltaic cells. We characterized the CMOS-integrated power receiver and successfully demonstrated blue light-emitting diode (LED) operation powered by infrared light. Then, we integrated the CMOS chip and a few off-chip components into a 1-mm3 implantable optogenetic stimulator, and demonstrated the operation of the device.

  14. Research on U.S. nuclear power plant major equipment aging

    International Nuclear Information System (INIS)

    Nakos, J.T.; Rosinski, S.T.

    1994-01-01

    The U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), in cooperation with nuclear power plant utilities and the Nuclear Energy Institute, have prepared equipment aging evaluations of nuclear power plant equipment for life extension considerations. Specifically, these evaluations focused on equipment considered important for plant license renewal (U.S. Code of Federal Regulations 10CFR54). open-quotes Industry Reportsclose quotes (IRs), jointly funded by DOE and EPRI, evaluated the aging of major systems, structures, and components (e.g., reactor pressure vessels, Class I structures, PWR and BWR containments, etc.) and contain a mixture of technical and licensing information. open-quotes Aging Management Guidelinesclose quotes (AMGs), funded by DOE, evaluate aging for commodity types of equipment (e.g., pumps, electrical switchgear, heat exchangers, etc.) and concentrate on technical issues only. AMGs are intended for systems engineers and plant maintenance staff. A significant number of technical issues were resolved during IR interactions with the U.S. Nuclear Regulatory Commission (NRC). However, certain technical issues have not been resolved and are considered open-quotes openclose quotes. Examples include certain issues related to fatigue, neutron irradiation embrittlement, intergranular stress corrosion cracking (IGSCC) and electrical cable equipment qualification. Direct NRC interaction did not take place during preparation of individual AMGs due to their purely technical nature. The eventual use of AMGs in a future license renewal application will likely require NRC interaction at that time. With a few noted exceptions, the AMG process indicated that current aging management practices of U.S. utilities were effective in preventing age-related degradation. This paper briefly describes the IR and AMG processes and summarizes the unresolved technical issues identified through preparation of the documents

  15. A new method of knowledge processing for equipment diagnosis of nuclear power plants

    International Nuclear Information System (INIS)

    Fujii, M.; Fukumoto, A.; Tai, I.; Morioka, T.

    1987-01-01

    In this work, the authors complete the development of a new knowledge processing method and representation for equipment diagnosis of nuclear power plants and evaluate its functions by applying to the maintenance and diagnosis support system of the reactor instrumentation. This knowledge processing method system is based on the Cause Generation and Checking concept and has sufficient performance not only in the diagnosis function but also in the man-machine interfacing function. The maintenance and diagnosis support system based on this method leads to the possibility for users to diagnose various phenomena occurred in an objective equipment to the considerable extent by consulting with the system, even if they don't have enough knowledge. With this system, it becomes easy for operators or plant engineers to take immediate actions to counteract against the abnormality. The maintainability of the equipments is improved and MTTR (Mean Time To Repair) is expected to be shorter. This new knowledge processing method is proved to be suited for fault diagnosis of the equipments of nuclear power plants

  16. Power electronic supply system with the wind turbine dedicated for average power receivers

    Science.gov (United States)

    Widerski, Tomasz; Skrzypek, Adam

    2018-05-01

    This article presents the original project of the AC-DC-AC converter dedicated to low power wind turbines. Such a set can be a good solution for powering isolated objects that do not have access to the power grid, for example isolated houses, mountain lodges or forester's lodges, where they can replace expensive diesel engine generators. An additional source of energy in the form of a mini-wind farm is also a good alternative to yachts, marinas and tent sites, which are characterized by relatively low power consumption. This article presents a designed low power wind converter that is dedicated to these applications. The main design idea of the authors was to create a device that converts the very wide range input voltage directly to a stable 230VAC output voltage without the battery buffer. Authors focused on maximum safety of using and service. The converter contains the thermal protection, short-circuit protection and overvoltage protection. The components have been selected in such a way as to ensure that the device functions as efficiently as possible.

  17. Rehabilitation of heat exchange equipment a key to power plant life extension and performance improvement

    Energy Technology Data Exchange (ETDEWEB)

    Taveau, F.; Huiban, A.M. [Alstom Power Heat Exchange, 78 - Velizy Villacoublay (France)

    2001-07-01

    With the current evolutions of the energy market and the life extension of the power plants, all the equipment initially supplied need one day or another partial or total rehabilitation. For heat exchange equipment, this includes the condensers, feed water heaters and various heat exchangers. Modernization is in particular necessary when in-service monitoring and periodic inspections show significant deteriorations of the tubes and cooling water leakages leading to forced outages or when tube and tube plate materials are no longer suited to cooling water characteristics or to updated specifications of the secondary system. Feedwater heaters and heat exchangers damaged by erosion/corrosion, vibrations, etc. can be re-designed, manufactured and replaced easily. The operation is more complex on condensers and requires technical surveys, study of alternative solutions and has a more direct impact on the global output of the power plant. That is why our conference will focus on the condenser refurbishment. (author)

  18. Rehabilitation of heat exchange equipment a key to power plant life extension and performance improvement

    International Nuclear Information System (INIS)

    Taveau, F.; Huiban, A.M.

    2001-01-01

    With the current evolutions of the energy market and the life extension of the power plants, all the equipment initially supplied need one day or another partial or total rehabilitation. For heat exchange equipment, this includes the condensers, feed water heaters and various heat exchangers. Modernization is in particular necessary when in-service monitoring and periodic inspections show significant deteriorations of the tubes and cooling water leakages leading to forced outages or when tube and tube plate materials are no longer suited to cooling water characteristics or to updated specifications of the secondary system. Feedwater heaters and heat exchangers damaged by erosion/corrosion, vibrations, etc. can be re-designed, manufactured and replaced easily. The operation is more complex on condensers and requires technical surveys, study of alternative solutions and has a more direct impact on the global output of the power plant. That is why our conference will focus on the condenser refurbishment. (author)

  19. Comparative research of finite element methods for perforated structures of nuclear power plant primary equipment

    International Nuclear Information System (INIS)

    Xiong Guangming; Deng Xiaoyun; Jin Ting

    2013-01-01

    Many perforated structures are used for nuclear power plant primary equipment, and they are complex, and have various forms. In order to explore the analysis and evaluation method, this paper used finite element method and equivalent analytic method to do the comparative analysis of perforated structures. The paper considered the main influence factors (including perforated forms, arrangements, and etc.), obtaining the systematic analysis methods of perforated structures. (authors)

  20. Use of complex electronic equipment within radiative areas of PWR power plants: feability study

    International Nuclear Information System (INIS)

    Fremont, P.; Carquet, M.

    1988-01-01

    EDF has undertaken a study in order to evaluate the technical and economical feasibility of using complex electronic equipment within radiative areas of PWR power plants. This study lies on tests of VLSI components (Random Access Memories) under gamma rays irradiations, which aims are to evaluate the radiation dose that they can withstand and to develop a selection method. 125 rad/h and 16 rad/h tests results are given [fr

  1. Development of equipment reliability process using predictive technologies at Hamaoka Nuclear Power Station

    International Nuclear Information System (INIS)

    Taniguchi, Yuji; Sakuragi, Futoshi; Hamada, Seiichi

    2014-01-01

    Development of equipment reliability(ER) process, specifically for predictive maintenance (PdM) technologies integrated condition based maintenance (CBM) process, at Hamaoka Nuclear Power Station is introduced in this paper. Integration of predictive maintenance technologies such as vibration, oil analysis and thermo monitoring is more than important to establish strong maintenance strategies and to direct a specific technical development. In addition, a practical example of CBM is also presented to support the advantage of the idea. (author)

  2. Cost Analysis of an Air Brayton Receiver for a Solar Thermal Electric Power System in Selected Annual Production Volumes

    Science.gov (United States)

    1981-01-01

    Pioneer Engineering and Manufacturing Company estimated the cost of manufacturing and Air Brayton Receiver for a Solar Thermal Electric Power System as designed by the AiResearch Division of the Garrett Corporation. Production costs were estimated at annual volumes of 100; 1,000; 5,000; 10,000; 50,000; 100,000 and 1,000,000 units. These costs included direct labor, direct material and manufacturing burden. A make or buy analysis was made of each part of each volume. At high volumes special fabrication concepts were used to reduce operation cycle times. All costs were estimated at an assumed 100% plant capacity. Economic feasibility determined the level of production at which special concepts were to be introduced. Estimated costs were based on the economics of the last half of 1980. Tooling and capital equipment costs were estimated for ach volume. Infrastructure and personnel requirements were also estimated.

  3. Cost determination of the electro-mechanical equipment of a small hydro-power plant

    Energy Technology Data Exchange (ETDEWEB)

    Ogayar, B.; Vidal, P.G. [Grupo de Investigacion IDEA, Escuela Politecnica Superior, University of Jaen, Campus de Las Lagunillas, s/n. 23071-Jaen (Spain)

    2009-01-15

    One of the most important elements on the recovery of a small hydro-power plant is the electro-mechanical equipment (turbine-alternator), since the cost of the equipment means a high percentage of the total budget of the plant. The present paper intends to develop a series of equations which determine its cost from basic parameters such as power and net head. These calculations are focused at a level of previous study, so it will be necessary to carry out the engineering project and request a budget to companies specialized on the construction of electro-mechanical equipment to know its cost more accurately. Although there is a great diversity in the typology of turbines and alternators, data from manufacturers which cover all the considered range have been used. The above equations have been developed for the most common of turbines: Pelton, Francis, Kaplan and semiKaplan for a power range below 2 MW. The obtained equations have been validated with data from real installations which have been subject to analysis by engineering companies working on the assembly and design of small plants. (author)

  4. Environmental and ventilation benefits for underground mining operations using fuel cell powered production equipment

    International Nuclear Information System (INIS)

    Kocsis, C.; Hardcastle, S.

    2007-01-01

    The benefits of replacing diesel engines with fuel cells in mine production equipment were discussed. The paper was part of a multi-year feasibility study conducted to evaluate the use of hydrogen fuel cell-powered equipment to replace diesel engine powered equipment in underground mining operations. The feasibility study demonstrated that fuel cells are capable of eliminating the unwanted by-products of combustion engines. However, the use of fuel cells also reduced the amount of ventilation that mines needed to supply, thereby further reducing energy consumption. This study examined the benefits of replacing diesel engines with fuel cells, and discussed the mitigating qualifiers that may limit ventilation energy savings. Solutions to retaining and maintaining additional ventilation in the event of hydrogen leaks from fuel cell stacks were also investigated. The analyses were conducted on 6 operating mines. Current operating costs were compared with future operating conditions using fuel cell powered production vehicles. Operating costs of the primary ventilation system were established with a mine ventilation simulator. The analysis considered exhaust shaft velocities, heating system air velocities, and levels of silica exposure. Canadian mine design criteria were reviewed. It was concluded that appropriate safeguards are needed along hydrogen distribution lines to lower the impacts of hydrogen leaks. Large financial commitments may also be required to ensure a spark-free environment. 20 refs., 6 tabs., 3 figs

  5. Some observations on stray magnetic fields and power outputs from short-wave diathermy equipment

    Energy Technology Data Exchange (ETDEWEB)

    Lau, R.W.M.; Dunscombe, P.B.

    1984-04-01

    Recent years have seen increasing interest in the possible hazards arising from the use of nonionizing electromagnetic radiation. Relatively large and potentially hazardous fields are to be found in the vicinity of short-wave and microwave equipment used in physiotherapy departments to produce therapeutic temperature rises. This note reports the results of measurements of the stray magnetic field and power output of a conventional short-wave diathermy unit when applied to tissue-equivalent phantoms. The dependence of these quantities on the variables, i.e. power setting of the unit, capacitor plate size, phantom size and phantom-capacitor plate separation, are discussed.

  6. Power saving control for the mobile DVB-H receivers based on H.264/SVC standard

    DEFF Research Database (Denmark)

    Belyaev, Evgeny; Grinko, Vitaly; Ukhanova, Ann

    2009-01-01

    This paper discusses the utilization of scalable extension of H.264/AVC standard in digital video broadcasting for handheld devices. In this area the problem of mobile receiver power consumption is critically important. This paper amplifies the well-known idea of the time-slicing and allows...

  7. Digital compensation of receiver clipping for DVB reception on low-power mobile

    NARCIS (Netherlands)

    Linnartz, J.P.M.G.; Rietman, R.

    2007-01-01

    Battery life-time is a critical issue for digital television (DVB) viewing on mobile phones. The number of quantization steps used in the analog-to-digital converter (ADC) is an important factor in the total power consumption of a DVB receiver. The OFDM signals require a large resolution of the ADC.

  8. Robust sigma delta converters : and their application in low-power highly-digitized flexible receivers

    NARCIS (Netherlands)

    Veldhoven, van R.H.M.; Roermund, van A.H.M.

    2011-01-01

    Sigma Delta converters are a very popular choice for the A/D converter in multi-standard, mobile and cellular receivers. Key A/D converter specifications are high dynamic range, robustness, scalability, low-power and low EMI. Robust Sigma Delta Converters presents a requirement derivation of a Sigma

  9. Generation of floor spectra compatible time histories for equipment seismic qualification in nuclear power plants

    International Nuclear Information System (INIS)

    Shyu, Y.-S.; Luh, Gary G.; Blum, Arie

    2004-01-01

    This paper proposes a procedure for generating floor response spectra compatible time histories used for equipment seismic qualification in nuclear power plants. From the 84th percentile power spectrum density function of an earthquake ensemble of four randomly generated time history motions, a statistically equivalent time history can be obtained by converting the power spectrum density function from the frequency domain into the time domain. With minor modification, if needed, the converted time history will satisfy both the spectral and the power spectrum density enveloping criteria, as required by the USNRC per Revision 2 of the Standard Review Plan, Section 3.7.1. Step-by-step generating procedures and two numerical examples are presented to illustrate the applications of the methodology. (author)

  10. Increasing reliability of nuclear energy equipment and at nuclear power plants

    International Nuclear Information System (INIS)

    Ochrana, L.

    1997-01-01

    The Institute of Nuclear Energy at the Technical University in Brno cooperates with nuclear power plants in increasing their reliability. The teaching programme is briefly described. The scientific research programme of the Department of Heat and Nuclear Power Energy Equipment in the field of reliability is based on a complex systematic concept securing a high level of reliability. In 1996 the Department prepared a study dealing with the evaluation of the maintenance system in a nuclear power plant. The proposed techniques make it possible to evaluate the reliability and maintenance characteristics of any individual component in a nuclear power plant, and to monitor, record and evaluate data at any given time intervals. (M.D.)

  11. Communications of 30 November 1995 received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-19

    The Director General has received notes verbales of 30 November 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, the Republic of Korea, Luxembourg, The Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments` Guidelines for transfers of nuclear-related dual-use equipment, material and related technology.

  12. Communications of 30 November 1995 received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1996-01-01

    The Director General has received notes verbales of 30 November 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, the Republic of Korea, Luxembourg, The Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments' Guidelines for transfers of nuclear-related dual-use equipment, material and related technology

  13. Wirelessly powered electrowetting-on-dielectric (EWOD) by planar receiver coils

    Science.gov (United States)

    Byun, Sang Hyun; Yuan, Junqi; Yoon, Myung Gon; Cho, Sung Kwon

    2015-03-01

    Electrowetting-on-dielectric (EWOD) is one of the most versatile methods used to control the wettability of liquids using electrical input. In most applications, EWOD is applied using physical wiring, which may restrict its application to implantable EWOD devices. In order to resolve this issue, we have studied and developed a wirelessly powered EWOD by using planar coils at the receiver that are fabricated out of a printed circuit board (PCB) by means of standard micro photolithography. Unlike conventional, bulky, spool coil type, the planar coil type lends itself to compact design and easy integration with EWOD chips. The present wireless powering principle is based on magnetic induction, which is very efficient when the transmitter and receiver coils are close to each other. The voltage obtained at the receiver is much higher than typically required EWOD voltages (>50 V) using a high transmission frequency (~MHz). The span of the EWOD contact angle is over 40°. In addition, amplitude modulation (AM) is implemented in the present wireless powering setup, followed by demodulation, in order to oscillate droplets at low frequency. This technique ensures smooth and reliable droplet movements. The wirelessly powered EWOD is used to transport a droplet and is mounted in a mini-boat which it powers and propels.

  14. Preliminary design of the Carrisa Plains solar central receiver power plant. Volume I. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    1983-12-31

    The design of the 30 MWe central receiver solar power plant to be located at Carrisa Plains, San Luis Obispo County, California, is summarized. The plant uses a vertical flat-panel (billboard) solar receiver located at the top of a tower to collect solar energy redirected by approximately 1900 heliostats located to the north of the tower. The solar energy is used to heat liquid sodium pumped from ground level from 610 to 1050/sup 0/F. The power conversion system is a non-reheat system, cost-effective at this size level, and designed for high-efficiency performance in an application requiring daily startup. Successful completion of this project will lead to power generation starting in 1986. This report also discusses plant performance, operations and maintenance, development, and facility cost estimate and economic analysis.

  15. Design of an effective energy receiving adapter for microwave wireless power transmission application

    Directory of Open Access Journals (Sweden)

    Peng Xu

    2016-10-01

    Full Text Available In this paper, we demonstrate the viability of an energy receiving adapter in a 8×8 array form with high power reception efficiency with the resonator of artificial electromagnetic absorber being used as the element. Unlike the conventional reported rectifying antenna resonators, both the size of the element and the separations between the elements are electrically small in our design. The energy collecting process is explained with an equivalent circuit model, and a RF combining network is designed to combine the captured AC power from each element to one main terminal for AC-to-DC conversion. The energy receiving adapter yields a total reception efficiency of 67% (including the wave capture efficiency of 86% and the AC-to-DC conversion efficiency of 78%, which is quite promising for microwave wireless power transmission.

  16. Performance analysis of a Kalina cycle for a central receiver solar thermal power plant with direct steam generation

    International Nuclear Information System (INIS)

    Modi, Anish; Haglind, Fredrik

    2014-01-01

    Solar thermal power plants have attracted increasing interest in the past few years – with respect to both the design of the various plant components, and extending the operation hours by employing different types of storage systems. One approach to improve the overall plant efficiency is to use direct steam generation with water/steam as both the heat transfer fluid in the solar receivers and the cycle working fluid. This enables operating the plant with higher turbine inlet temperatures. Available literature suggests that it is feasible to use ammonia-water mixtures at high temperatures without corroding the equipment by using suitable additives with the mixture. The purpose of the study reported here was to investigate if there is any benefit of using a Kalina cycle for a direct steam generation, central receiver solar thermal power plant with high live steam temperature (450 °C) and pressure (over 100 bar). Thermodynamic performance of the Kalina cycle in terms of the plant exergy efficiency was evaluated and compared with a simple Rankine cycle. The rates of exergy destruction for the different components in the two cycles were also calculated and compared. The results suggest that the simple Rankine cycle exhibits better performance than the Kalina cycle when the heat input is only from the solar receiver. However, when using a two-tank molten-salt storage system as the primary source of heat input, the Kalina cycle showed an advantage over the simple Rankine cycle because of about 33 % reduction in the storage requirement. The solar receiver showed the highest rate of exergy destruction for both the cycles. The rates of exergy destruction in other components of the cycles were found to be highly dependent on the amount of recuperation, and the ammonia mass fraction and pressure at the turbine inlet. - Highlights: •Kalina cycle for a central receiver solar thermal power plant with direct steam generation. •Rankine cycle shows better plant exergy

  17. Practical application of the benchmarking technique to increase reliability and efficiency of power installations and main heat-mechanic equipment of thermal power plants

    Science.gov (United States)

    Rimov, A. A.; Chukanova, T. I.; Trofimov, Yu. V.

    2016-12-01

    Data on the comparative analysis variants of the quality of power installations (benchmarking) applied in the power industry is systematized. It is shown that the most efficient variant of implementation of the benchmarking technique is the analysis of statistical distributions of the indicators in the composed homogenous group of the uniform power installations. The benchmarking technique aimed at revealing the available reserves on improvement of the reliability and heat efficiency indicators of the power installations of the thermal power plants is developed in the furtherance of this approach. The technique provides a possibility of reliable comparison of the quality of the power installations in their homogenous group limited by the number and adoption of the adequate decision on improving some or other technical characteristics of this power installation. The technique provides structuring of the list of the comparison indicators and internal factors affecting them represented according to the requirements of the sectoral standards and taking into account the price formation characteristics in the Russian power industry. The mentioned structuring ensures traceability of the reasons of deviation of the internal influencing factors from the specified values. The starting point for further detail analysis of the delay of the certain power installation indicators from the best practice expressed in the specific money equivalent is positioning of this power installation on distribution of the key indicator being a convolution of the comparison indicators. The distribution of the key indicator is simulated by the Monte-Carlo method after receiving the actual distributions of the comparison indicators: specific lost profit due to the short supply of electric energy and short delivery of power, specific cost of losses due to the nonoptimal expenditures for repairs, and specific cost of excess fuel equivalent consumption. The quality loss indicators are developed

  18. A low power 3-5 GHz CMOS UWB receiver front-end

    International Nuclear Information System (INIS)

    Li Weinan; Huang Yumei; Hong Zhiliang

    2009-01-01

    A novel low power RF receiver front-end for 3-5 GHz UWB is presented. Designed in the 0.13 μm CMOS process, the direct conversion receiver features a wideband balun-coupled noise cancelling transconductance input stage, followed by quadrature passive mixers and transimpedance loading amplifiers. Measurement results show that the receiver achieves an input return loss below -8.5 dB across the 3.1-4.7 GHz frequency range, maximum voltage conversion gain of 27 dB, minimum noise figure of 4 dB, IIP3 of -11.5 dBm, and IIP2 of 33 dBm. Working under 1.2 V supply voltage, the receiver consumes total current of 18 mA including 10 mA by on-chip quadrature LO signal generation and buffer circuits. The chip area with pads is 1.1 x 1.5 mm 2 .

  19. Performance of on-power fuelling equipment at Rajasthan Atomic Power Station

    International Nuclear Information System (INIS)

    Jayabarathan, S.; Gopalakrishnan, S.

    1977-01-01

    Natural uranium reactors on account of their intrinsically low reactivity need frequent refuelling. The Rajasthan Atomic Power Station based on natural uranium reactors has, therefore, been provided with on-power fuel handling system which was installed in 1972. Its performance has met the design intent and operational objectives which are enumerated. However, continuous fuelling 7 to 10 days has not been possible because frequent maintenance of refuelling system is needed on account of certain deficiencies major of which is the heavy water leakage. For better performance, installation of a programmable logic controller is suggested. Mention has also been made of inadequate number of skilled man-power required for maintenance which leads to quick depletion of man-rem of all the available personnel trained for maintenance work. (M.G.B.)

  20. Aseismatic design of electrical equipments and instruments for nuclear power stations

    International Nuclear Information System (INIS)

    Suzuki, Yasuharu; Nishizawa, Kazuo; Miyazaki, Yoshio; Miura, Takumi

    1977-01-01

    The aseismatic design of electrical instruments is carried out according to IEEE Standard 344-1971 in the USA. In Japan also, the method of aseismatic design of electrical instruments has been investigated by the representatives of electric power companies and electric machine makers since 1972. In Hitachi Ltd., the statical method of confirming aseismatic property was established on the basis of the rigid design for electrical instruments. It is convenient to examine the aseismatic property of electrical equipments by classifying them into control and switch boards, electrical appliances, equipments and circuits. It is possible to use the static method treating earthquake force as static load by avoiding resonance with the electrical equipments which have the higher natural frequency than that of buildings. The purposes of the vibration test are to prove the validity of the theoretical analysis, to clarify the vibration characteristics, and to confirm the maintenance of functions and the strength of the equipments. The vibration tests of control boards, the switch boards of enclosed type, motor control centers, the racks for instrumentation, storage batteries and electrical appliances are explained. Moreover, the vibration analysis with a computer according to finite element method is described. (Kako, I.)

  1. Oil leakage detection for electric power equipment based on ultraviolet fluorescence effect

    Science.gov (United States)

    Zhang, Jing; Wang, Jian-hui; Xu, Bin; Huang, Zhi-dong; Huang, Lan-tao

    2018-03-01

    This paper presents a method to detect the oil leakage of high voltage power equipment based on ultraviolet fluorescence effect. The method exploits the principle that the insulating oil has the fluorescent effect under the irradiation of specific ultraviolet light. The emission spectrum of insulating oil under excitation light with different wavelengths is measured and analyzed first. On this basis, a portable oil leakage detective device for high voltage power equipment is designed and developed with a selected 365 nm ultraviolet as the excitation light and the low light level camera as the fluorescence image collector. Then, the feasibility of the proposed method and device in different conditions is experimentally verified in the laboratory environment. Finally, the developed oil leakage detective device is applied to 500 kV Xiamen substation and Quanzhou substation. And the results show that the device can detect the oil leakage of high voltage electrical equipment quickly and conveniently even under the condition of a slight oil leakage especially in the low light environment.

  2. Program outline of seismic fragility capacity tests on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Lijima, T.; Abe, H.; Fujita, T.

    2004-01-01

    A seismic probabilistic safety assessment (PSA) is an available method to evaluate residual risk of nuclear plant that is designed with definitive seismic design condition. Seismic fragility capacity data are necessary for seismic PSA, but we don't have sufficient data of active components of nuclear plants in Japan. This paper describes a plan of seismic fragility capacity tests on nuclear power plant equipment. The purpose of those tests is to obtain seismic fragility capacity of important equipment from a safety design point of view. And the equipment for the fragility capacity tests were selected considering effect on core damage frequency (CDF) that was evaluated by our preliminary seismic PSA. Consequently horizontal shaft pump, electric cabinets, Control Rod Drive system (CRD system) of BWR and PWR plant and vertical shaft pump were selected. The seismic fragility capacity tests are conducted from phase-1 to phase-3, and horizontal shaft pump and electric cabinets are tested on phase-1. The fragility capacity test consists of two types of tests. One is actual equipment test and another is element test. On actual equipment test, a real size model is tested with high-level seismic motion, and critical acceleration and failure mode are investigated. Regarding fragility test phase-1, we selected typical type horizontal shaft pump and electric cabinets for the actual equipment test. Those were Reactor Building Closed Cooling Water (RCW) Pump and eight kinds of electric cabinets such as relay cabinet, motor control center. On the test phase-1, maximum input acceleration for the actual equipment test is intended to be 6-G-force. Since the shaking table of TADOTSU facility did not have capability for high acceleration, we made vibration amplifying system. In this system, amplifying device is mounted on original shaking table and it moves in synchronization with original table. The element test is conducted with many samples and critical acceleration, median and

  3. Joint Utility-Based Power Control and Receive Beamforming in Decentralized Wireless Networks

    Directory of Open Access Journals (Sweden)

    Angela Feistel

    2010-01-01

    Full Text Available This paper addresses the problem of joint resource allocation in general wireless networks and its practical implementation aspects. The objective is to allocate transmit powers and receive beamformers to the users in order to maximize a network-wide utility that represents the attained QoS and is a function of the signal-to-interference ratios. This problem is much more intricate than the corresponding QoS-based power control problem. In particular, it is not known which class of utility functions allows for a convex formulation of this problem. In case of perfect synchronization, the joint power and receiver control problem can be reformulated as a power control problem under optimal receivers. Standard gradient projection methods can be applied to solve this problem. However, these algorithms are not applicable in decentralized wireless networks. Therefore, we decompose the problem and propose a convergent alternate optimization that is amenable to distributed implementation. In addition, in real-world networks noisy measurements and estimations occur. Thus, the proposed algorithm has to be investigated in the framework of stochastic approximation. We discuss practical implementation aspects of the proposed stochastic algorithm and investigate its convergence properties by simulations.

  4. Communication Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment or Technology

    International Nuclear Information System (INIS)

    1978-02-01

    The Permanent Mission of ...... presents its compliments to the Director General of the International Atomic Energy Agency and has the honour to enclose copies of three documents which have been the subject of discussion between the Government of ....... and a number of other Governments. The Government of ........ has decided that, when considering the export of nuclear material, equipment or technology, it will act in accordance with the principles contained in the attached documents

  5. The seismic assessment of wheeled vehicle type equipment (e.g. emergency power supply vehicle) against severe accident for nuclear power plant in Japan

    International Nuclear Information System (INIS)

    Ikeda, Takuya; Mitsuzawa, Daisuke; Yamaguchi, Yoshikazu; Hasebe, Motohiko; Imamura, Ryutaro; Tomitani, Yuji; Ueyama, Ippei; Kawamoto, Takahiro

    2017-01-01

    After the events at the Fukushima Dai-ichi Nuclear Power Plant, the equipment to mitigate the effects of severe accidents has been installed in the domestic nuclear power plants. From the viewpoint of convenience for installation, etc., a number of industry standard-based wheeled vehicle type equipment has been placed. On the other hand, the new regulations require the equipment for severe accidents to withstand the Design Basis Earthquake. Therefore, the seismic qualification is essential item for wheeled vehicle type equipment according to the regulatory requirement. At that time, compared to the traditional safety-related equipment, there was not enough knowledge of seismic evaluation for vehicle type equipment. This paper reports the overview of wheeled vehicle type equipment and the seismic qualification by test. (author)

  6. Optimization of power take-off equipment for an oscillating water column wave energy plant

    Energy Technology Data Exchange (ETDEWEB)

    Gato, L.M.C.; Falcao, Antonio de F.O. [Dept. de Engenharia Mecanica do IST, Lisboa (Portugal); Paulo Alexandre Justino [INETI/DER, Lisboa (Portugal)

    2005-07-01

    The paper reports the optimization study of the electro-mechanical power take-off equipment for the OWC plant whose structure is a caisson forming the head of the new Douro breakwater. The stochastic approach is employed to model the wave-to-wire energy conversion. The optimization includes rotational speed (for each sea state), turbine geometry and size, and generator rated power. The procedure is implemented into a fully integrated computer code, that yields numerical results for the multi-variable optimization process and for the electrical power output (annual average and for different sea states) with modest computing time (much less than if a time-domain model were used instead). Although focused into a particular real case, the paper is intended to outline a design method that can be applied to a wider class of wave energy converters.

  7. Communication received from the Permanent Mission of New Zealand regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1995-01-01

    The Director General has received a note verbale dated 22 December 1994 from the Permanent Mission of New Zealand to the International Atomic Energy Agency providing information on the nuclear export policies and practices of the Government of New Zealand

  8. Thermoeconomic optimization of a Kalina cycle for a central receiver concentrating solar power plant

    DEFF Research Database (Denmark)

    Modi, Anish; Kærn, Martin Ryhl; Andreasen, Jesper Graa

    2016-01-01

    with direct vapour generation and without storage. The use of the ammonia-water mixture as the power cycle working fluid with non-isothermal evaporation and condensation presents the potential to improve the overall performance of the plant. This however comes at a price of requiring larger heat exchangers...... because of lower thermal pinch and heat transfer degradation for mixtures as compared with using a pure fluid in a conventional steam Rankine cycle, and the necessity to use a complex cycle arrangement. Most of the previous studies on the Kalina cycle focused solely on the thermodynamic aspects......Concentrating solar power plants use a number of reflecting mirrors to focus and convert the incident solar energy to heat, and a power cycle to convert this heat into electricity. This paper evaluates the use of a high temperature Kalina cycle for a central receiver concentrating solar power plant...

  9. Development of a standard equipment management model for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed.

  10. Challenges and Prospects of Equipment Health Monitoring with Wireless Sensor Network in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Chen, Dongyi; Jiang, Jin; Bari, Ataul; Wang, Quan; Hashemian, Hash-M.

    2014-01-01

    A wireless sensor network (WSN) system can offer tremendous benefits to equipment condition monitoring in newly-constructed and/or refurbished nuclear power plants (NPPs). However, it has not been widely accepted so far because of the following requirements by the NPP operators ectromagnetic (EM) emissions from the wireless transceivers must not interfere with the functionalities of the sensitive safety and protection systems in the plant, WSN must perform reliably in the presence of high levels of EM interference from devices such as relays and motor driven pumps, and ionizing radiation sources, dependable WSN performance in harsh industrial environments that are cluttered with cable trays, piping, valves, pumps, motors, and concrete and steel structures, and trict compliance with nuclear regulatory guidelines on EM emissions by the wireless devices. This paper will review the key issues associated with the deployment of WSN for equipment condition monitoring in NPPs. Some promising WSN technologies that can be used in NPP applications are also discussed

  11. Challenges and Prospects of Equipment Health Monitoring with Wireless Sensor Network in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Dongyi [University of Electronic Science and Technology of China, Chengdu (China); Jiang, Jin; Bari, Ataul; Wang, Quan [University of Western Ontario, Ontario (Canada); Hashemian, Hash-M. [AMS Technology Center Knoxville (United States)

    2014-08-15

    A wireless sensor network (WSN) system can offer tremendous benefits to equipment condition monitoring in newly-constructed and/or refurbished nuclear power plants (NPPs). However, it has not been widely accepted so far because of the following requirements by the NPP operators ectromagnetic (EM) emissions from the wireless transceivers must not interfere with the functionalities of the sensitive safety and protection systems in the plant, WSN must perform reliably in the presence of high levels of EM interference from devices such as relays and motor driven pumps, and ionizing radiation sources, dependable WSN performance in harsh industrial environments that are cluttered with cable trays, piping, valves, pumps, motors, and concrete and steel structures, and trict compliance with nuclear regulatory guidelines on EM emissions by the wireless devices. This paper will review the key issues associated with the deployment of WSN for equipment condition monitoring in NPPs. Some promising WSN technologies that can be used in NPP applications are also discussed.

  12. Development of automated equipment for reduction of personnel radiation exposure in nuclear power plants

    International Nuclear Information System (INIS)

    Ogushi, Akira; Fujii, Masaaki; Mizuno, Katsuhiro.

    1976-01-01

    Described are a mobile remote inspection system and an automatic analyzer for radioactive nuclides in reactor coolant now being developed as a means of reducing personnel radiation exposure in nuclear power plants. In the mobile remote inspection system ''TELEPAT'', a self-propelled vehicle equipped with a thermometer, accelerometer, microphone, ionization chamber, etc. is remote operated from the main control room to inspect the equipment in the reactor building. The automatic analyzer for radioactive nuclides in reactor coolant automates the series of operations ranging from sampling of reactor coolant to measurement of radioactivity and analyses of measured data, with a view to saving labor in radioactivity analysis work while reducing exposure of personnel to radiation. (auth.)

  13. System for remote routine monitoring of power equipment at TPP and NPP

    International Nuclear Information System (INIS)

    Kantsedalov, V.G.; Samojlenko, V.P.; Doroshenko, V.A.

    1988-01-01

    A system for remote routine monitoring of TPP and NPP pipeline metals is described. The principal functional unit of the system is the unit of remote routine methods and techniques for studying and monitoring the metal and properties. The system is equipped with 5 types of routine monitoring equipment: robots, remote aggregated complexes, periodical diagnostic monitors, other means of metal diagnostics (endoscopes, introscopes). All current information enters the unit for estimating and forecasting the service life of power unit, where it is compared with the standard indices of reliability, duravility and efficiency. The system considered permits to reduce significantly or minimize the scope of works on metal monitoring during overhauls, increase intermonitoring and interrepairing compaigns to 8 years

  14. Development of a standard equipment management model for nuclear power plants

    International Nuclear Information System (INIS)

    Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun

    2012-01-01

    Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed

  15. Communications Received from Members regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material. Two Further Communications dated 26 September 1975

    International Nuclear Information System (INIS)

    1975-01-01

    On 3 October 1975 the Director General received a letter from the Resident Representative of the Netherlands to the Agency transmitting two communications dated 10 September from the Minister for Foreign Affairs of Luxembourg dealing respectively with the export of nuclear material and the export of certain categories of equipment and other material. The Resident Representative requested that all Members be informed of the contents of the two communications, and they are accordingly reproduced below

  16. Communications of 15 November 1999 Received from Member States Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    2009-01-01

    The Director General of the International Atomic Energy Agency has received letters of 17 October 1996 from the Resident Representatives of Argentina, Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material [es

  17. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers

    International Nuclear Information System (INIS)

    1993-04-01

    The Director General has received a Note Verbale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Verbale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Note Verbale is annexed hereto [fr

  18. Communication received from the permanent mission of the Argentine Republic regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1994-11-01

    On 11 May 1994, the Director General received a note verbale from the Permanent Mission of Argentina to the International Atomic Energy Agency relating to the export of nuclear material, equipment and technology. The purpose of this note verbale is to provide further information on the nuclear export policies and practices of the Government of the Argentine Republic. In the light of the wish expressed at the end of the note verbale, the text of the note verbale is annexed hereto

  19. Communications of 15 November 1999 Received from Member States Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    2000-03-01

    The Director General of the International Atomic Energy Agency has received letters of 17 October 1996 from the Resident Representatives of Argentina, Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material [fr

  20. Is there an isotope on your books? Advice to receivers and liquidators on dealing with X-ray sources and X-ray equipment

    International Nuclear Information System (INIS)

    Colgan, Tony.

    1987-01-01

    The paper outlines advice to receivers and liquidators on dealing with radioactive sources and X-ray equipment. When companies go into liquidation it is important that the accountants handling the winding up are aware of the law and their responsibilities if radioactive materials are present. Guidelines are presented here which may help indicate to the accountant the likely presence of radioactive materials and the procedure which should be followed when arranging sale or disposal of these items

  1. Communications of 15 November 1999 Received from Member States Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    2009-01-01

    The Director General of the International Atomic Energy Agency has received letters of 17 October 1996 from the Resident Representatives of Argentina, Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material

  2. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers

    International Nuclear Information System (INIS)

    1993-04-01

    The Director General has received a Note Ver bale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Ver bale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Ver bale, the text of the Note Ver bale is annexed hereto

  3. Communications of 30 June 1995 received from Member States regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1995-10-01

    The Director General has received letters of 30 June 1995 from the Resident Representative of Argentina, Australia, Austria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary Ireland, Italy, Japan, Luxembourg, the Netherlands, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material

  4. Communication received from the permanent mission of the Argentine Republic regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1994-11-01

    On 11 May 1994, the Director General received a note verbale from the Permanent Mission of Argentina to the International Atomic Energy Agency relating to the export of nuclear material, equipment and technology. The purpose of this note verbale is to provide further information on nuclear export policies and practices of the Government of the Argentine Republic. In the light of the wish expressed at the end of the note verbale, the text of the note verbale is annexed hereto

  5. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers

    International Nuclear Information System (INIS)

    1993-04-01

    The Director General has received a Note Verbale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Verbale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Note Verbale is annexed hereto [es

  6. Communications of 15 November 1999 Received from Member States Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    2000-01-01

    The Director General of the International Atomic Energy Agency has received letters of 17 October 1996 from the Resident Representatives of Argentina, Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material

  7. Seismic qualification of equipment in operating nuclear power plants: Unresolved Safety Issue A-46

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1987-02-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46. In addition, the collection and review of seismic experience data and existing seismic test data are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experienced data base. The principal technical finding of USI A-46 is that seismic experience data, supplemented by existing seismic test data, applied in accordance with the guidelines developed, can be used to verify the seismic adequacy of mechanical and electrical equipment in operating nuclear plants. Explicit seismic qualification should be required only if seismic experience data or existing test data on similar components cannot be shown to apply

  8. Ageing of polymers in electrical equipment used in nuclear power plants

    International Nuclear Information System (INIS)

    Clavreul, R.

    1999-01-01

    Ageing of polymers in electrical equipment used in nuclear power plants has been studied in (Electricite de France) EDF for several years. The objective of such studies is to predict the polymers lifetime in normal and accidental conditions. The prediction of polymers behaviour in normal conditions requires accelerated tests in order to get rapidly experimental results. Experimental conditions must carefully be chosen and representative of real ageing. Accelerated ageing is usually done by applying higher temperature, (dose) or dose rate. When such experiments are done, the effects of temperature, (dose) or dose rate are first determined. In a second step, experimental results are extrapolated to real conditions. To predict lifetime of polymers, the following recommendations have to be checked: in order to assume that accelerated tests are representative of normal ageing, the observed mechanisms in experiments must be the same as those in real conditions. For accidental conditions, the same tests as those described in standards can be applied to polymers. The simulation of any accident occurring just after the installation of electrical equipment in nuclear power plants is easy to manage: only the accidental test can be carried out on the electrical equipment. To determine whether polymers in electrical equipment would have a good behaviour or not when an accident would occur after a period of several years or decades in normal conditions in a nuclear power plant, the accidental test must be done on aged materials; their physical, mechanical and electrical characteristics must be relevant to aged polymers in normal conditions. In order to detect any evolution of properties during ageing, the electrical, mechanical or chemical tests have to be proceeded on polymers samples. The characterisation tests which are applied on non-aged and aged samples depend on the nature of the polymers, their application in electrical equipment and their environment. The IEC 544

  9. Development of new-concept superconducting power equipment; Shinkino chodendo denryoku kiki no kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    Hamajima, T.; Tsurunaga, K.; Urata, M. [Toshiba Corp., Tokyo (Japan)

    1998-01-01

    The superconducting magnet energy storage (SMES) system has a function by which magnetic energy is stored in a superconducting coil without loss and discharged very rapidly into the power line when needed. The fault current limiter has a function by which transport current is passed without impedance and excessive fault current is restricted by generating large impedance in an emergency. These are the functions of new power equipment, which can not be realized by the conventional equipment. In the small-scale SMES project, Toshiba has fabricated 100 kWh-class element coils and 1 kWh/1 MW modules as the first step of practical application for power system control. For the superconducting fault current limiter, Toshiba has developed a 6.6 kV-1 kA class fault current limiter without supplying cooling medium such as helium, and limiting tests of fault current have been successfully conducted. Through the long-term tests of element coils for SMES and the system interconnection tests of module-type SMES, it is expected that the technological development for practical application is accelerated. 4 refs., 7 figs., 3 tabs.

  10. Grid-connected photovoltaic power systems: survey of inverter and related protection equipments

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, T

    2002-12-15

    This report for the International Energy Agency (IEA) made by Task 5 of the Photovoltaic Power Systems (PVPS) programme reports on a survey made on inverter and related protection equipment. The mission of the Photovoltaic Power Systems Programme is to enhance the international collaboration efforts which accelerate the development and deployment of photovoltaic solar energy. Task 5 deals with issues concerning grid-interconnection and distributed PV power systems. This report summarises the data obtained from survey of recent inverter technology and inverter protection equipment for grid interconnected PV systems. The results are based on the surveys using a questionnaire to identify the current status of grid-interconnection inverters. This report is to serve as a reference for those interested in installing grid-connected PV systems, electric utility company personnel, manufacturers and researchers. The results of the survey are presented and discussed. Technical and financial data is reviewed and two appendices provide details on the results obtained and those institutions involved in the survey.

  11. Seismic proving tests on the reliability for large components and equipment of nuclear power plants

    International Nuclear Information System (INIS)

    Ohno, Tokue; Tanaka, Nagatoshi

    1988-01-01

    Since Japan has destructive earthquakes frequently, the structural reliability for large components and equipment of nuclear power plants are rigorously required. They are designed using sophisticated seismic analyses and have not yet encountered a destructive earthquake. When nuclear power plants are planned, it is very important that the general public understand the structural reliability during and after an earthquake. Seismic Proving Tests have been planned by Ministry of International Trade and Industry (Miti) to comply with public requirement in Japan. A large-scale high-performance vibration table was constructed at Tasted Engineering Laboratory of Nuclear Power Engineering Test Center (NU PEC), in order to prove the structural reliability by vibrating the test model (of full scale or close to the actual size) in the condition of a destructive earthquake. As for the test models, the following four items were selected out of large components and equipment important to the safety: Reactor Containment Vessel; Primary Coolant Loop or Primary Loop Recirculation System; Reactor Pressure Vessel; and Reactor Core Internals. Here is described a brief of the vibration table, the test method and the results of the tests on PWR Reactor Containment Vessel and BWR Primary Loop Recirculation System (author)

  12. Optimal wireless receiver structure for omnidirectional inductive power transmission to biomedical implants.

    Science.gov (United States)

    Gougheri, Hesam Sadeghi; Kiani, Mehdi

    2016-08-01

    In order to achieve omnidirectional inductive power transmission to biomedical implants, the use of several orthogonal coils in the receiver side (Rx) has been proposed in the past. In this paper, the optimal Rx structure for connecting three orthogonal Rx coils and the power management is found to achieve the maximum power delivered to the load (PDL) in the presence of any Rx coil tilting. Unlike previous works, in which a separate power management has been used for each coil to deliver power to the load, different resonant Rx structures for connecting three Rx coils to a single power management are studied. In simulations, connecting three Rx coils with the diameters of 3 mm, 3.3 mm, and 3.6 mm in series and resonating them with a single capacitor at the operation frequency of 100 MHz led to the maximum PDL for large loads when the implant was tilted for 45o. This optimal Rx structure achieves higher PDL in worst-case scenarios as well as reduces the number of power managements to only one.

  13. Optimal power allocation of a single transmitter-multiple receivers channel in a cognitive sensor network

    KAUST Repository

    Ayala Solares, Jose Roberto

    2012-08-01

    The optimal transmit power of a wireless sensor network with one transmitter and multiple receivers in a cognitive radio environment while satisfying independent peak, independent average, sum of peak and sum of average transmission rate constraints is derived. A suboptimal scheme is proposed to overcome the frequency of outages for the independent peak transmission rate constraint. In all cases, numerical results are provided for Rayleigh fading channels. © 2012 IEEE.

  14. IEEE Std 323-1983: IEEE standard for qualifying Class 1E equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard describes the basic requirements for qualifying Class 1E equipment with interfaces that are to be used in nuclear power generating stations. The requirements presented include the principles, procedures, and methods of qualification. These qualification requirements, when met, will confirm the adequacy of the equipment design under normal, abnormal, design basis event, post design basis event, and in-service test conditions for the performance of safety function(s). The purpose of this standard is to identify requirements for the qualification of Class 1E equipment, including those interfaces whose failure could adversely affect the performance of Class 1E equipment and systems. The methods described shall be used for qualifying equipment, extending qualification, and updating qualification if the equipment is modified. Other issued IEEE standards which present qualification methods for specific equipment or components, or both, and those that deal with parts of the qualification program, may be used to supplement this standard, as applicable

  15. Combined cycle solar central receiver hybrid power system study. Final technical report. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-11-01

    This study develops the conceptual design for a commercial-scale (nominal 100 MWe) central receiver solar/fossil fuel hybrid power system with combined cycle energy conversion. A near-term, metallic heat pipe receiver and an advanced ceramic tube receiver hybrid system are defined through parametric and market potential analyses. Comparative evaluations of the cost of power generation, the fuel displacement potential, and the technological readiness of these two systems indicate that the near-term hybrid system has better potential for commercialization by 1990. Based on the assessment of the conceptual design, major cost and performance improvements are projected for the near-term system. Constraints preventing wide-spread use were not identified. Energy storage is not required for this system and analyses show no economic advantages with energy storage provisions. It is concluded that the solar hybrid system is a cost effective alternative to conventional gas turbines and combined cycle generating plants, and has potential for intermediate-load market penetration at 15% annual fuel escalation rate. Due to their flexibility, simple solar/nonsolar interfacing, and short startup cycles, these hybrid plants have significant operating advantages. Utility company comments suggest that hybrid power systems will precede stand-alone solar plants.

  16. Improvement of nuclear power plant monitor and control equipment. Computer application backfitting

    International Nuclear Information System (INIS)

    Hayakawa, H.; Kawamura, A.; Suto, O.; Kinoshita, Y.; Toda, Y.

    1985-01-01

    This paper describes the application of advanced computer technology to existing Japanese Boiling Water Reactor (BWR) nuclear power plants for backfitting. First we review the background of the backfitting and the objectives of backfitting. A feature of backfitting such as restrictions and constraints imposed by the existing equipment are discussed and how to overcome these restrictions by introduction of new technology such as highly efficient data transmission using multiplexing, and compact space saving computer systems are described. Role of the computer system in reliable NPS are described with a wide spectrum of TOSHIBA backfitting computer system application experiences. (author)

  17. Mathematical model for optimization of multilayer submerged-arc welding of frame equipment of power units

    International Nuclear Information System (INIS)

    Pankov, V.V.; Chernyshev, G.G.; Kozlov, N.E.

    1987-01-01

    A mathematical model for optimization of multilayer submerged arc welding of frame equipment of power units is constructed. The variation-energy method permits to construct the universal mathematical model for strengthening formation of a single bead; the method is reasonable for simulation of a multilayer welded joint. Minimization of the distance between maximum and minimum layer height of a built-up metal is the necessary condition for qualitative formation of the multilayer joint. One can calculate in real time scale the optimal vector of maximally ten parameters under the multilayer welding condition immediately after change in the grooving width using the developed mathematical model of optimization

  18. Loosening and damage mechanism of thread-joined structures in nuclear power equipment

    International Nuclear Information System (INIS)

    Tang Hui

    1999-01-01

    The author proposes a loosening mechanism of thread-joined structures under vibrate environments in the nuclear power equipment and structures, which is on the base of the macro and imperceptible-mechanics analysis. It has answered the problems on the seizing, the adhesive wearing, the generation of cracks, the thread-tooth fracture. So it has a conclusion that the loosening of thread-joined structures is essential trend, in other words, the locking property of thread-pair is failure under vibrate environments

  19. Application of ultrasonic inspection data in strength calculations for nuclear power plant equipment

    International Nuclear Information System (INIS)

    Ovchinnikov, A.V.; Rivkin, E.Yu.; Vasilchenko, G.S.; Zvezdin, Yu.I.

    1991-01-01

    Several kinds of test specimens were produced with three types of defects of defined sizes and positions in the particular localities of weld joints. Such specimens have been used for defect parameter characterization by ultrasonic testing. The principles for schematization of such defects and the formulae for the stress intensity factor calculations for elliptical and semielliptical cracks have been worked out. Methods for defining the sizes of defect which are acceptable have been designed for use for use on operational nuclear power plant equipment and take account of the mutual effects of the force, thermal and residual stresses. The method can be used in the brittle, transitional and tough material state. (author)

  20. Methods and equipment for diagnosis of components of Novovoronezh nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Prokop, K [Energoinvest, Dukovany (Czechoslovakia). Zavod Jaderna Elektrarna

    1981-12-01

    The results are reported obtained in applying diagnostic techniques adn diagnostic equipment in the Novovoronezh nuclear power plant. Vibroacoustic, neutron and hydrodynamic noiose of the installation was monitored. The test level method and the mean value comparison method were used for assessing the installation condition. Dispersion analysis methods are used for predicting the propagation of anomalies while for determining specific defects leading to the formation of anomalies the method is used based on the correlation analysis of vibroacoustic signals and other technological noise. The flow charts and descriptions are given of the systems of acoustic emission testing, reactor internals testing using neutron noise, pump testing, and the spectral analyzer.

  1. Active seismic response control systems for nuclear power plant equipment facilities

    International Nuclear Information System (INIS)

    Kobori, Takuji; Kanayama, Hiroo; Kamagata, Shuichi

    1989-01-01

    To sustain severe earthquake ground motion, a new type of anti-seismic structure is proposed, called a Dynamic Intelligent Building (DIB) system, which is positioned as an active seismic response controlled the structure. The structural concept starts from a new recognition of earthquake ground motion, and the structural natural frequency is actively adjusted to avoid resonant vibration, and similarly the external counter-force cancels the resonant force which comes from the dynamic structural motion energy. These concepts are verified using an analytical simulator program. The advanced application of the DIB system, is the Active Supporting system and the Active Stabilizer system for nuclear power plant equipment facilities. (orig.)

  2. Communication received from Members regarding Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    1984-02-01

    The Director General has received letters from the Resident Representatives to the Agency of the following Member States concerning the commitments of these Member States under Article III, paragraph 2, of the Treaty on the Non-Proliferation of Nuclear Weapons (the date of each letter is given in parentheses after the name of the Member State:

  3. Communications Received from Members Regarding the Export of Nuclear Material and of Certain Categories of Equipment and other Material

    International Nuclear Information System (INIS)

    1986-02-01

    The Director General has received a letter dated 28 January 1986 from the Permanent Representative of Hungary to the Agency concerning the commitments of Hungary under Article III, paragraph 2, of the Treaty on the Non-Proliferation of Nuclear Weapons

  4. Communications Received from Members regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    1978-12-01

    On 1 September 1978 the Director General received similar letters of that date from the Resident Representatives of Poland and the German Democratic Republic to the Agency relating to the commitments of these Members under Article III, paragraph 2, of the Treaty on the Non- Proliferation of Nuclear Weapons

  5. Ideal Operation of a Photovoltaic Power Plant Equipped with an Energy Storage System on Electricity Market

    Directory of Open Access Journals (Sweden)

    Markku Järvelä

    2017-07-01

    Full Text Available There is no natural inertia in a photovoltaic (PV generator and changes in irradiation can be seen immediately at the output power. Moving cloud shadows are the dominant reason for fast PV power fluctuations taking place typically within a minute between 20 to 100% of the clear sky value roughly 100 times a day, on average. Therefore, operating a utility scale grid connected PV power plant is challenging. Currently, in many regions, renewable energy sources such as solar and wind receive feed-in tariffs that ensure a certain price for the energy. On the other hand, electricity markets operate on a supply-demand principle and a typical imbalance settlement period is one hour. This paper presents the energy, power and corresponding requirements for an energy storage system in a solar PV power plant to feed the power to the grid meeting the electricity spot markets practices. An ideal PV energy production forecast is assumed to be available to define reference powers of the system for the studied imbalance settlement periods. The analysis is done for three different PV system sizes using the existing irradiance measurements of the Tampere University of Technology solar PV power station research plant.

  6. Solar central receiver hybrid power system, Phase I. Volume 3. Appendices. Final technical report, October 1978-August 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-09-01

    A design study for a central receiver/fossil fuel hybrid power system using molten salts for heat transfer and heat storage is presented. This volume contains the appendices: (A) parametric salt piping data; (B) sample heat exchanger calculations; (C) salt chemistry and salt/materials compatibility evaluation; (D) heliostat field coordinates; (E) data lists; (F) STEAEC program input data; (G) hybrid receiver design drawings; (H) hybrid receiver absorber tube thermal math model; (I) piping stress analysis; (J) 100-MWe 18-hour storage solar central receiver hybrid power system capital cost worksheets; and (K) 500-MWe 18-hour solar central receiver hybrid power system cost breakdown. (WHK)

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  8. Development of microstructure to optimise mechanical performance of power generation equipment

    International Nuclear Information System (INIS)

    Marshall, P.

    1986-11-01

    The factors responsible for the development of microstructure in CEGB construction ceramics and steels is assessed as a function of composition, thermomechanical treatment, thermal ageing and environmental degradation. The relationships between microstructure and mechanical properties (tensile, toughness, creep and fatigue) of relevance to structures operating in power generation equipment is then developed in quantitative terms. The conclusions from the assessment are as follows: 1 The relationship between microstructure and mechanical properties of construction ceramics and steels used in the power generation industry has been assessed. 2 Factors which significantly influence microstructure and thus mechanical properties are chemical composition, thermomechanical treatment, ageing and environmental degradation. The influence of such microstructural changes in tensile, toughness, fatigue and creep properties of ceramics and steels is assessed. 3 The benefits arising from an understanding of materials behaviour are discussed in terms of improved materials and the assessment of plant performance. (author)

  9. Report on assessment of electrical equipment aging for nuclear power plant (AEA), FY2011

    International Nuclear Information System (INIS)

    Minakawa, T.

    2012-11-01

    Electrical components with safety function used in nuclear power plants, such as cables, medium voltage motors, low voltage motors, electrical penetration of reactor containment vessel, motor operated valve, pressure transmitter, temperature detector, etc, are required to be operational under the environment of design basis event (DBE) to shut down a reactor safely and to prevent radioactive materials from being leaked to outside. Polymer materials used as parts of these equipments are gradually degraded by thermal and radiation environment in the normal operation. In addition, the degradation is thought to progress rapidly when they are exposed to the DBE environment and a decrease in performance of the equipment may be caused. From these reason, electrical components with safety function are tested for long-term integrity in accordance with IEEE standard. However, conventional method of accelerated aging which assumes thermal and radiation aging during normal operation is said to have uncertainty in simulating the degradation given in actual operating environment. To address this issue, the project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) was carried out and 'Guide for Cable Environmental Qualification Test for Nuclear Power Plant' was developed. The need for developing an aging evaluation method for other electrical and I and C components was pointed out in the 'Strategy maps 2007', prepared by the cooperation among government, industry and academia. Under the circumstance, the project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008. In this study, parts of electrical and I and C component with safety function used in nuclear power plant whose aging needs to be considered are employed as specimens, and their aging characteristics under the thermal environment and the combined radiation and thermal environment are obtained (herein after referred to as 'critical part test

  10. Prediction of Maintenance Period of Equipment Through Risk Assessment of Thermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Song, Gee Wook; Kim, Bum Shin; Choi, Woo Song; Park, Myung Soo [KEPCO Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    Risk-based inspection (RBI) is a well-known method that is used to optimize inspection activities based on risk analysis in order to identify the high-risk components of major facilities such as power plants. RBI, when implemented and maintained properly, improves plant reliability and safety while reducing unplanned outages and repair costs. Risk is given by the product of the probability of failure (Pof) and the consequence of failure (COF). A semi-quantitative method is generally used for risk assessment. Semi-quantitative risk assessment complements the low accuracy of qualitative risk assessment and the high expense and long calculation time of quantitative risk assessment. The first step of RB I is to identify important failure modes and causes in the equipment. Once these are defined, the Pof and COF can be assessed for each failure. During Pof and COF assessment, an effective inspection method and range can be easily found. In this paper, the calculation of the Pof is improved for accurate risk assessment. A modified semi-quantitative risk assessment was carried out for boiler facilities of thermal power plants, and the next maintenance schedules for the equipment were decided.

  11. Prediction of Maintenance Period of Equipment Through Risk Assessment of Thermal Power Plants

    International Nuclear Information System (INIS)

    Song, Gee Wook; Kim, Bum Shin; Choi, Woo Song; Park, Myung Soo

    2013-01-01

    Risk-based inspection (RBI) is a well-known method that is used to optimize inspection activities based on risk analysis in order to identify the high-risk components of major facilities such as power plants. RBI, when implemented and maintained properly, improves plant reliability and safety while reducing unplanned outages and repair costs. Risk is given by the product of the probability of failure (Pof) and the consequence of failure (COF). A semi-quantitative method is generally used for risk assessment. Semi-quantitative risk assessment complements the low accuracy of qualitative risk assessment and the high expense and long calculation time of quantitative risk assessment. The first step of RB I is to identify important failure modes and causes in the equipment. Once these are defined, the Pof and COF can be assessed for each failure. During Pof and COF assessment, an effective inspection method and range can be easily found. In this paper, the calculation of the Pof is improved for accurate risk assessment. A modified semi-quantitative risk assessment was carried out for boiler facilities of thermal power plants, and the next maintenance schedules for the equipment were decided

  12. Automation and mechanization of in-service inspection of selected equipment in FRG's nuclear power plants

    International Nuclear Information System (INIS)

    Metke, E.

    1988-01-01

    The procedures and equipment are described for the automation and mechanization of in-service inspection in nuclear power plants in the FRG, used by the KWU company. Checks of the pressure vessel are done by visual means using a colour tv camera, the method of eddy currents and the ultrasonic method. An analysis is made of the time schedule of ultrasonic inspections, and the central column manipulator is described which allows to check all internal regions of the pressure vessel. Attention is also devoted to other devices, e.g., those for prestressing shanks, cleaning shanks, cleaning thread apertures, etc. A combined probe using the ultrasonic method and the eddy current method serves the inspection of heat exchange tubes in the steam generator. For inspecting the primary circuit the KWU company uses devices for checking and working the inner surface of pipes. Briefly described are examples of using KWU equipment in nuclear power plants in CMEA countries. (Z.M.). 11 figs., 6 refs

  13. NEW TECHNOLOGIES FOR RESTORATION AND PROTECTION OF POWER EQUIPMENT WITH THE AID OF COMPOSITE MATERIALS

    Directory of Open Access Journals (Sweden)

    A. O. Ischenko

    2017-01-01

    Full Text Available The analysis of possible variants of reconstruction of the power equipment is fulfilled and the conclusion concerning the prospects of such work with the use of composite materials is reached. The data on the technical characteristics of composite repair materials for various purposes are presented, the results of repairs of power equipment, in particular the technology for the recovery of the boarding surfaces of the diffuser rings and protection of the pumps D1250 casings are provided. The technology of the recovery pneumatic cylinder, hydraulic cylinder rod, as well as the unique technology of restoration of working surfaces of the impeller vanes of transfer pump, that had been destroyed by corrosion in conjunction with the cavitation processes and were considered as not restorable is described. The restored impeller was in operation during a year and only thereafter it was removed for restoration. Another composite material discussed in the article – diagum – makes it possible to perform a series of repairs associated with restoration of the rubber-covered surfaces of pump casings as well as with restoration of various surfaces of the conveyor belts. Taking the excellent adhesive properties of this composite into account, restoration of worn stainless steel sieve screens to remove abrasive material was fulfilled with the aid of it. The restoration was accomplished via the use of the conveyor belt which application time had expired, that was glued to a metal sieve with diagum. The use of the composites is economically justified, because the application of them in repairs reduces, firstly, terms of restoration work and, secondly, the price of repairs. Third, equipment that was damaged beyond repair is being commissioned by the use of the mentioned composites. 

  14. Frequency Splitting Elimination and Cross-Coupling Rejection of Wireless Power Transfer to Multiple Dynamic Receivers

    Directory of Open Access Journals (Sweden)

    Narayanamoorthi R.

    2018-01-01

    Full Text Available Simultaneous power transfer to multiple receiver (Rx system is one of the key advantages of wireless power transfer (WPT system using magnetic resonance. However, determining the optimal condition to uniformly transfer the power to a selected Rx at high efficiency is the challenging task under the dynamic environment. The cross-coupling and frequency splitting are the dominant issues present in the multiple Rx dynamic WPT system. The existing analysis is performed by considering any one issue present in the system; on the other hand, the cross coupling and frequency splitting issues are interrelated in dynamic Rx’s, which requires a comprehensive design strategy by considering both the problems. This paper proposes an optimal design of multiple Rx WPT system, which can eliminate cross coupling, frequency splitting issues and increase the power transfer efficiency (PTE of selected Rx. The cross-coupling rejection, uniform power transfer is performed by adding an additional relay coil and independent resonance frequency tuning with capacitive compensation to each Rx unit. The frequency splitting phenomena are eliminated using non-identical transmitter (Tx and Rx coil structure which can maintain the coupling between the coil under the critical coupling limit. The mathematical analysis of the compensation capacitance calculation and optimal Tx coil size identification is performed for the four Rx WPT system. Finite element analysis and experimental investigation are carried out for the proposed design in static and dynamic conditions.

  15. Communications Received from Members Regarding the Export of Nuclear Material and of Certain Categories of Equipment and other Material

    International Nuclear Information System (INIS)

    1990-11-01

    The Director General has received letters dated 3 September 1990 from the Resident Representatives to the Agency of Australia, Canada, Czechoslovakia, Denmark, Finland, the German Democratic Republic, the Federal Republic of Germany, Greece, Hungary, Ireland, Japan, Luxembourg, the Netherlands, Norway, Poland, Sweden, the Union of Soviet Socialist Republics, the United Kingdom of Great Britain and Northern Ireland, and the United States of America concerning the commitments of these Member States under Article III, paragraph 2, of the Treaty on the Non-Proliferation of Nuclear Weapons

  16. Remote-automation of nuclear power plant equipment inspection and maintenance

    International Nuclear Information System (INIS)

    Sasaki, Masayoshi; Kawamura, Hironobu; Nakano, Yoshiyuki; Izumi, Shigeru.

    1984-01-01

    The remotely operated automation of the checkup and maintenance of nuclear power generation facilities has largely contributed to the rise of capacity ratio of plants due to the shortening of regular inspection period and to the reduction of radiation exposure dose during working, the labor saving in working and so on. In this paper, the new technologies adopted in an automatic fuel exchanger, a remotely operated automatic CRD exchanger, a new type channel handling machine, pressure-withstanding main steam line plugs and so on for No.2 plant in the Fukushima No.2 Nuclear Power Station, Tokyo Electric Power Co., Inc., are reported. Besides, the state of development of new remotely operated automatic machines for nuclear power use, such as CRD disassembling and cleaning device, volume reduction equipment for spent fuel channel boxes and control rods, multi-functional robots for use under high radiation and so on is described. Also the trend of development of latest robot technology which will be put in practical use in near future is outlined, such as a running manipulator for checkup and inspection, a variable form crawler vehicle and a five-leg movable manipulator. (Kako, I.)

  17. Impact of Auxiliary Equipments Consumption on Electricity Generation Cost in Selected Power Plants of Pakistan

    Directory of Open Access Journals (Sweden)

    DILEEP KUMAR

    2017-04-01

    Full Text Available This study focuses on higher generation cost of electricity in selected TPPs (Thermal Power Plants in Sindh, Pakistan. It also investigates the energy consumed by the auxiliary equipment of the selected TPPs in Sindh, Pakistan. The AC (Auxiliary Consumption of selected TPPs is compared with that in UK and other developed countries. Results show that the AC in selected TPPs in Sindh, Pakistan exceeds the average AC of the TPPs situated in developed countries. Many energy conservation measures such as impeller trimming and de-staging, boiler feed pump, high voltage inverter, variable frequency drive, and upgrading the existing cooling tower fan blades with fiber reinforced plastic are discussed to overcome higher AC. This study shows that harnessing various available energy conservative measures the AC and unit cost can be reduced by 4.13 and 8.8%; also adverse environmental impacts can be mitigated. Results show that the unit cost of electricity can be reduced from Rs.20 to19/kWh in JTPP (Jamshoro Thermal Power Plant, Rs.9 to 8.8/kWh in GTPS (Gas Turbine Power Station Kotri and Rs. 11 to 10.27/ kWh in LPS (Lakhara Power Station. Thus, electricity production can be improved with the existing capacity, which will eventually assist to manage the current energy crisis and ensure its conservation

  18. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    International Nuclear Information System (INIS)

    2003-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 28 February 2003 from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Canada, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Kazakhstan, Latvia, Netherlands, Norway, Portugal, Republic of Korea, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Note Verbales is to provide further information on those Governments' Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full

  19. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    International Nuclear Information System (INIS)

    2005-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 25 October 2004 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Canada, Cyprus, Czech Republic, Estonia, Finland, France, Greece, Hungary, Italy, Japan, Malta, Netherlands, Norway, Republic of Korea, South Africa, Spain, Sweden, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Notes Verbales is to provide further information on those Governments' guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full

  20. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-16

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 28 February 2003 from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Canada, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Kazakhstan, Latvia, Netherlands, Norway, Portugal, Republic of Korea, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Note Verbales is to provide further information on those Governments' Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full.

  1. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-02-23

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 25 October 2004 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Canada, Cyprus, Czech Republic, Estonia, Finland, France, Greece, Hungary, Italy, Japan, Malta, Netherlands, Norway, Republic of Korea, South Africa, Spain, Sweden, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Notes Verbales is to provide further information on those Governments' guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full.

  2. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology. Nuclear-related dual-use transfers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The Director General has received notes verbales dated 30 June 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments` Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material and related Technology. In the light of the wish expressed at the end of each note verbale, the text of the notes verbales is annexed hereto. The enclosure to these notes verbales is also reproduced in full in the Annex.

  3. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology. Nuclear-related dual-use transfers

    International Nuclear Information System (INIS)

    1995-10-01

    The Director General has received notes verbales dated 30 June 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments' Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material and related Technology. In the light of the wish expressed at the end of each note verbale, the text of the notes verbales is annexed hereto. The enclosure to these notes verbales is also reproduced in full in the Annex

  4. User's guide for MIRVAL: a computer code for comparing designs of heliostat-receiver optics for central receiver solar power plants

    Energy Technology Data Exchange (ETDEWEB)

    Leary, P L; Hankins, J D

    1979-02-01

    MIRVAL is a Monte Carlo program which simulates the heliostats and a portion of the receiver for solar energy central receiver power plants. Models for three receiver types and four kinds of heliostats are included in the code. The three receiver types modeled are an external cylinder, a cylindrical cavity with a downward-facing aperature, and a north-facing cavity. Three heliostats which track in elevation and azimuth are modeled, one of which is enclosed in a plastic dome. The fourth type consists of a rack of louvered reflective panels with the rack rotatable about a fixed horizontal axis. Phenomena whose effects are simulated are shadowing, blocking, mirror tracking, random errors in tracking and in the conformation of the reflective surface, optical figure of the reflective surface, insolation, angular distribution of incoming sun rays to account for limb darkening and scattering, attenuation of light between the mirrors and the receiver, reflectivity of the mirror surface, and mirror aiming strategy.

  5. X-band Robust AlGaN/GaN Receiver MMICs with over 41 dBm Power Handling

    NARCIS (Netherlands)

    Janssen, J.P.B.; Heijningen, M. van; Provenzano, G.; Visser, G.C.; Morvan, E.; Vliet, F.E. van

    2008-01-01

    Gallium-Nitride technology is known for its high power density and power amplifier designs, but is also very well suited to realize robust receiver components. This paper presents the design and measurement of a robust AlGaN/GaN Low Noise Amplifier and Transmit/Receive Switch MMIC. Two versions of

  6. X-Band Robust AlGaN/GaN Receiver MMICs with over 41 dBm Power Handling

    NARCIS (Netherlands)

    Janssen, J.P.B.; van Heijningen, M; Provenzano, G.; van Vliet, Frank Edward

    2008-01-01

    Abstract Gallium-Nitride technology is known for its high power density and power amplifier designs, but is also very well suited to realize robust receiver components. This paper presents the design and measurement of a robust AlGaN/GaN Low Noise Amplifier and Transmit/Receive Switch MMIC. Two

  7. Optimization of a recompression supercritical carbon dioxide cycle for an innovative central receiver solar power plant

    International Nuclear Information System (INIS)

    Reyes-Belmonte, M.A.; Sebastián, A.; Romero, M.; González-Aguilar, J.

    2016-01-01

    Peculiar thermodynamic properties of carbon dioxide (CO 2 ) when it is held at or above its critical condition (stated as supercritical CO 2 or sCO 2 ) have attracted the attention of many researchers. Its excellent thermophysical properties at medium-to-moderate temperature range have made it to be considered as the alternative working fluid for next power plant generation. Among those applications, future nuclear reactors, solar concentrated thermal energy or waste energy recovery have been shown as the most promising ones. In this paper, a recompression sCO 2 cycle for a solar central particles receiver application has been optimized, observing net cycle efficiency close to 50%. However, small changes on cycle parameters such as working temperatures, recuperators efficiencies or mass flow distribution between low and high temperature recuperators were found to drastically modify system overall efficiency. In order to mitigate these uncertainties, an optimization analysis based on recuperators effectiveness definition was performed observing that cycle efficiency could lie among 40%–50% for medium-to-moderate temperature range of the studied application (630 °C–680 °C). Due to the lack of maturity of current sCO 2 technologies and no power production scale demonstrators, cycle boundary conditions based on the solar application and a detailed literature review were chosen. - Highlights: • Mathematical modelling description for recompression sCO 2 cycle. • Split fraction and recuperators effectiveness effect into sCO 2 cycle performance. • Optimization methodology of sCO 2 cycle for an innovative solar central receiver. • Power generation using particles central receiver.

  8. Signal existence verification (SEV) for GPS low received power signal detection using the time-frequency approach.

    Science.gov (United States)

    Jan, Shau-Shiun; Sun, Chih-Cheng

    2010-01-01

    The detection of low received power of global positioning system (GPS) signals in the signal acquisition process is an important issue for GPS applications. Improving the miss-detection problem of low received power signal is crucial, especially for urban or indoor environments. This paper proposes a signal existence verification (SEV) process to detect and subsequently verify low received power GPS signals. The SEV process is based on the time-frequency representation of GPS signal, and it can capture the characteristic of GPS signal in the time-frequency plane to enhance the GPS signal acquisition performance. Several simulations and experiments are conducted to show the effectiveness of the proposed method for low received power signal detection. The contribution of this work is that the SEV process is an additional scheme to assist the GPS signal acquisition process in low received power signal detection, without changing the original signal acquisition or tracking algorithms.

  9. Communications of 15 November 1999 received from Member States regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    2000-01-01

    The document reproduces the text of the letters dated 15 November 1999 received by the Director General of the IAEA from the Resident Representatives of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Luxembourg, the Netherlands, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom, and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material

  10. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [es

  11. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-09

    The document reproduces the text of the Notes Verbales received by the Director General of the IAEA on 20 October 1999 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom, and the United States of America relating to the transfers of nuclear-related dual-use equipment, materials, software and related technology.

  12. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    International Nuclear Information System (INIS)

    2000-01-01

    The document reproduces the text of the Notes Verbales received by the Director General of the IAEA on 20 October 1999 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom, and the United States of America relating to the transfers of nuclear-related dual-use equipment, materials, software and related technology

  13. Communication received from the Permanent Mission of Denmark to the Agency regarding Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2007-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Czech Republic, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to the export of nuclear material, equipment and technology

  14. Communications of 17 October 1996 received from Member States regarding the export of nuclear material and of certain categories of equipment and other material

    International Nuclear Information System (INIS)

    1999-01-01

    The document reproduces the text of the letter received by the Director General of the IAEA on 17 October 1996 from the Resident Representatives of Argentina, Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, the Slovak Republic, South Africa, Spain, Sweden, the United Kingdom, and the United States of America, concerning the export of nuclear materials and of certain categories of equipment and other material

  15. Communication received from the Permanent Mission of Denmark to the Agency regarding Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2007-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Czech Republic, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to the export of nuclear material, equipment and technology [es

  16. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology

  17. Communication of 30 June 1995 Received from France Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    1995-10-01

    The Director General has received letters concerning the export of nuclear material and of certain categories of equipment and other material from the following Resident Representatives to the International Atomic Energy Agency: a letter dated 28 February 1994 from the Resident Representative of France; letters dated 1 March 1994 from the Resident Representatives of Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, and the United States of America; and a letter dated 22 March 1994 from the Resident Representative of Romania [ru

  18. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [fr

  19. Communication of 30 June 1995 Received from France Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    1995-01-01

    The Director General has received letters concerning the export of nuclear material and of certain categories of equipment and other material from the following Resident Representatives to the International Atomic Energy Agency: a letter dated 28 February 1994 from the Resident Representative of France; letters dated 1 March 1994 from the Resident Representatives of Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, and the United States of America; and a letter dated 22 March 1994 from the Resident Representative of Romania [es

  20. Communication of 30 June 1995 Received from France Regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material

    International Nuclear Information System (INIS)

    1995-01-01

    The Director General has received letters concerning the export of nuclear material and of certain categories of equipment and other material from the following Resident Representatives to the International Atomic Energy Agency: a letter dated 28 February 1994 from the Resident Representative of France; letters dated 1 March 1994 from the Resident Representatives of Australia, Austria, Bulgaria, Canada, the Czech Republic, Denmark, Finland, Germany, Greece, Hungary, Ireland, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Spain, Sweden, the United Kingdom of Great Britain and Northern Ireland, and the United States of America; and a letter dated 22 March 1994 from the Resident Representative of Romania

  1. Reviews Equipment: BioLite Camp Stove Game: Burnout Paradise Equipment: 850 Universal interface and Capstone software Equipment: xllogger Book: Science Magic Tricks and Puzzles Equipment: Spinthariscope Equipment: DC Power Supply HY5002 Web Watch

    Science.gov (United States)

    2013-05-01

    WE RECOMMEND BioLite CampStove Robust and multifaceted stove illuminates physics concepts 850 Universal interface and Capstone software Powerful data-acquisition system offers many options for student experiments and demonstrations xllogger Obtaining results is far from an uphill struggle with this easy-to-use datalogger Science Magic Tricks and Puzzles Small but perfectly formed and inexpensive book packed with 'magic-of-science' demonstrations Spinthariscope Kit for older students to have the memorable experience of 'seeing' radioactivity WORTH A LOOK DC Power Supply HY5002 Solid and effective, but noisy and lacks portability HANDLE WITH CARE Burnout Paradise Car computer game may be quick off the mark, but goes nowhere fast when it comes to lab use WEB WATCH 'Live' tube map and free apps would be a useful addition to school physics, but maths-questions website of no more use than a textbook

  2. Wide-Range Highly-Efficient Wireless Power Receivers for Implantable Biomedical Sensors

    KAUST Repository

    Ouda, Mahmoud

    2016-11-01

    Wireless power transfer (WPT) is the key enabler for a myriad of applications, from low-power RFIDs, and wireless sensors, to wirelessly charged electric vehicles, and even massive power transmission from space solar cells. One of the major challenges in designing implantable biomedical devices is the size and lifetime of the battery. Thus, replacing the battery with a miniaturized wireless power receiver (WPRx) facilitates designing sustainable biomedical implants in smaller volumes for sentient medical applications. In the first part of this dissertation, we propose a miniaturized, fully integrated, wirelessly powered implantable sensor with on-chip antenna, designed and implemented in a standard 0.18μm CMOS process. As a batteryless device, it can be implanted once inside the body with no need for further invasive surgeries to replace batteries. The proposed single-chip solution is designed for intraocular pressure monitoring (IOPM), and can serve as a sustainable platform for implantable devices or IoT nodes. A custom setup is developed to test the chip in a saline solution with electrical properties similar to those of the aqueous humor of the eye. The proposed chip, in this eye-like setup, is wirelessly charged to 1V from a 5W transmitter 3cm away from the chip. In the second part, we propose a self-biased, differential rectifier with enhanced efficiency over an extended range of input power. A prototype is designed for the medical implant communication service (MICS) band at 433MHz. It demonstrates an efficiency improvement of more than 40% in the rectifier power conversion efficiency (PCE) and a dynamic range extension of more than 50% relative to the conventional cross-coupled rectifier. A sensitivity of -15.2dBm input power for 1V output voltage and a peak PCE of 65% are achieved for a 50k load. In the third part, we propose a wide-range, differential RF-to-DC power converter using an adaptive, self-biasing technique. The proposed architecture doubles

  3. Integrated equipment for increasing and maintaining coolant pressure in primary circuit of PWR nuclear power plant

    International Nuclear Information System (INIS)

    Sykora, D.

    1986-01-01

    An open heat pump circuit is claimed connected to the primary circuit. The pump circuit consists of a steam pressurizer with a built-in steam distributor, a compressor, an expander, a reducing valve, an auxiliary pump, and of water and steam pipes. The operation is described and a block diagram is shown of integrated equipment for increasing and maintaining pressure in the nuclear power plant primary circuit. The appropriate entropy diagram is also shown. The advantage of the open pump circuit consists in reducing the electric power input and electric power consumption for the steam pressurizers, removing entropy loss in heat transfer with high temperature gradient, in the possibility of inserting, between the expander and the auxiliary pump, a primary circuit coolant treatment station, in simplified design and manufacture of the high-pressure steam pressurizer vessel, reducing the weight of the steam pressurizer by changing its shape from cylindrical to spherical, increasing the rate of pressure growth in the primary circuit. (E.S.)

  4. 30 CFR 77.906 - Trailing cables supplying power to low-voltage mobile equipment; ground wires and ground check...

    Science.gov (United States)

    2010-07-01

    ... portable or mobile equipment from low-voltage three-phase resistance grounded power systems shall contain... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Trailing cables supplying power to low-voltage... STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Low- and Medium-Voltage...

  5. Solar Central Receiver Hybrid Power Systems sodium-cooled receiver concept. Final report. Volume II, Book 2. Conceptual design, Sections 5 and 6

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    The overall, long-term objective of the Solar Central Receiver Hybrid Power System program is to identify, characterize, and ultimately demonstrate the viability and cost effectiveness of solar/fossil, steam Rankine cycle, hybrid power systems that: (1) consist of a combined solar central receiver energy source and a nonsolar energy source at a single, common site, (2) may operate in the base, intermediate, and peaking capacity modes, (3) produce the rated output independent of variations in solar insolation, (4) provide a significant savings (50% or more) in fuel consumption, and (5) produce power at the minimum possible cost in mills/kWh. It is essential that these hybrid concepts be technically feasible and economically competitive with other systems in the near to mid-term time period (1985-1990) on a commercial scale. The program objective for Phase I is to identify and conceptually characterize solar/fossil steam Rankine cycle, commercial-scale, power plant systems that are economically viable and technically feasible. This volume contains the detailed conceptual design and cost/performance estimates and an assessment of the commercial scale solar central receiver hybrid power system. (WHK)

  6. Structural steels for power generating equipment and heat and chemical heat treatments

    International Nuclear Information System (INIS)

    Astaf'ev, A.A.

    1979-01-01

    Development of structural steels for power generating equipment and for reactor engineering, in particular, is elucidated. Noted is utilization of the 15Kh2NMFA steels for the WWER-1000 reactor vessels, the 10GN2MFA steels for steam generators, pressurizers, vessels of the automatic emergency shut down and safety system; the 00Kh12N3DL steel for cast pump vessels and main locking bars. The recommendations on heat treatment of big forgings, for instance, ensuring the necessary complex of mechanical properties are given. Diffusion chromizing with subsequent nitriding of austenitic steels which increase durability of the components in BN reactors more than 4 times, is practised on a large scale

  7. Wideband Impulse Modulation and Receiver Algorithms for Multiuser Power Line Communications

    Directory of Open Access Journals (Sweden)

    Andrea M. Tonello

    2007-01-01

    Full Text Available We consider a bit-interleaved coded wideband impulse-modulated system for power line communications. Impulse modulation is combined with direct-sequence code-division multiple access (DS-CDMA to obtain a form of orthogonal modulation and to multiplex the users. We focus on the receiver signal processing algorithms and derive a maximum likelihood frequency-domain detector that takes into account the presence of impulse noise as well as the intercode interference (ICI and the multiple-access interference (MAI that are generated by the frequency-selective power line channel. To reduce complexity, we propose several simplified frequency-domain receiver algorithms with different complexity and performance. We address the problem of the practical estimation of the channel frequency response as well as the estimation of the correlation of the ICI-MAI-plus-noise that is needed in the detection metric. To improve the estimators performance, a simple hard feedback from the channel decoder is also used. Simulation results show that the scheme provides robust performance as a result of spreading the symbol energy both in frequency (through the wideband pulse and in time (through the spreading code and the bit-interleaved convolutional code.

  8. Improved high temperature solar absorbers for use in Concentrating Solar Power central receiver applications.

    Energy Technology Data Exchange (ETDEWEB)

    Stechel, Ellen Beth; Ambrosini, Andrea; Hall, Aaron Christopher; Lambert, Timothy L.; Staiger, Chad Lynn; Bencomo, Marlene

    2010-09-01

    Concentrating solar power (CSP) systems use solar absorbers to convert the heat from sunlight to electric power. Increased operating temperatures are necessary to lower the cost of solar-generated electricity by improving efficiencies and reducing thermal energy storage costs. Durable new materials are needed to cope with operating temperatures >600 C. The current coating technology (Pyromark High Temperature paint) has a solar absorptance in excess of 0.95 but a thermal emittance greater than 0.8, which results in large thermal losses at high temperatures. In addition, because solar receivers operate in air, these coatings have long term stability issues that add to the operating costs of CSP facilities. Ideal absorbers must have high solar absorptance (>0.95) and low thermal emittance (<0.05) in the IR region, be stable in air, and be low-cost and readily manufacturable. We propose to utilize solution-based synthesis techniques to prepare intrinsic absorbers for use in central receiver applications.

  9. Understanding cross-national trends in high-tech renewable power equipment exports to the United States

    International Nuclear Information System (INIS)

    Sawhney, Aparna; Kahn, Matthew E.

    2012-01-01

    We track US imports of advanced technology wind and solar power-generation equipment from a panel of countries during 1989–2010, and examine the determining factors including country size, sector-specific US FDI outflow, and domestic wind and solar power generation. Differentiating between the core high-tech and the balance of system equipment, we find US imports of both categories have grown at significantly higher rate from the relatively poorer countries, and particularly China and India. Larger countries are found to be exporting significantly more, and US FDI is found to play a significant positive role in the exports of high-tech equipment for the poor countries. For the core wind and solar high-tech equipment, we find domestic renewable power generation of the exporting countries also played a significant positive role. - Highlights: ► We track US imports of advanced technology wind and solar power-generation equipment. ► US imports of both categories have grown at significantly higher rate from China and India. ► US FDI is found to play a significant positive role in the exports of high-tech equipment.

  10. Development of Information Datasheets of Nuclear Power Plant (NPP) Equipment using cfiXLM schema

    International Nuclear Information System (INIS)

    Lee, Jaiho; Song, Eunhye

    2014-01-01

    In 2009, EPRI (Electrical Power Research Institute) published a new NPP information handover guide to provide NPP owners and operators with data handover templates in consistent format for effective delivery of information during all stages of the handover process. Another difficult concern for NPP data information management is to exchange the data information among many organizations such as NPP owners, operators, engineering companies, suppliers, and vendors. As a matter of fact, the improperly formatted handover of information sometimes occurs due to the discrepancy of data format (e. g., data description language type). This improper delivery can make negative effects on NPP integrity and safety. Thus, the lack of proper exchange for different data information systems of organizations should be resolved by using an international standard data format. The standard data format can reduce the cost and time for data exchange in each phase for design, procurement, delivery, installation, operation and maintenance of equipment. The AEX(automating equipment information exchange) pilot implementation project team under EPRI advanced nuclear technology (ANT) program has been conducted a research for the use of XML equipment schemas for electronic data exchange(EDE). They applied XML equipment schema for the design, selection, quotation, purchase and mock install of a safety injection centrifugal pump using EDE standard HI(hydraulic institute) 50.7. For data exchange, FIATECH, an industry consortium, has equally developed library of templates and reference data for ISO-15926, which is an international standard capable of reducing data-error and delivery time for exchanging data among different organizations. KHNP as an only owner/operator company has not experienced much difficulty in data interoperability with other organizations, but continued its unremitting exertions to develop a robust system capable of managing data information generated in all the stages of NPP

  11. Development of Information Datasheets of Nuclear Power Plant (NPP) Equipment using cfiXLM schema

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jaiho; Song, Eunhye [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    In 2009, EPRI (Electrical Power Research Institute) published a new NPP information handover guide to provide NPP owners and operators with data handover templates in consistent format for effective delivery of information during all stages of the handover process. Another difficult concern for NPP data information management is to exchange the data information among many organizations such as NPP owners, operators, engineering companies, suppliers, and vendors. As a matter of fact, the improperly formatted handover of information sometimes occurs due to the discrepancy of data format (e. g., data description language type). This improper delivery can make negative effects on NPP integrity and safety. Thus, the lack of proper exchange for different data information systems of organizations should be resolved by using an international standard data format. The standard data format can reduce the cost and time for data exchange in each phase for design, procurement, delivery, installation, operation and maintenance of equipment. The AEX(automating equipment information exchange) pilot implementation project team under EPRI advanced nuclear technology (ANT) program has been conducted a research for the use of XML equipment schemas for electronic data exchange(EDE). They applied XML equipment schema for the design, selection, quotation, purchase and mock install of a safety injection centrifugal pump using EDE standard HI(hydraulic institute) 50.7. For data exchange, FIATECH, an industry consortium, has equally developed library of templates and reference data for ISO-15926, which is an international standard capable of reducing data-error and delivery time for exchanging data among different organizations. KHNP as an only owner/operator company has not experienced much difficulty in data interoperability with other organizations, but continued its unremitting exertions to develop a robust system capable of managing data information generated in all the stages of NPP

  12. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  13. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  14. Reliability data of fire protection equipment and features in German nuclear power plants

    International Nuclear Information System (INIS)

    Roewekamp, M.; Riekert, T.; Sehrbrock, W.

    1997-01-01

    In order to perform probabilistic fire safety analyses, a comprehensive data base is needed including physical characteristics of fire compartments and their inventory, fire occurrence frequencies, technical reliability data for all fire-related equipment, human actions and human error probabilities, etc. In order to provide updated and realistic reliability data, the operational behaviour of different fire protection features in two German nuclear power plants was analysed in the framework of the study presented here. The analyses are based on the examination of reported results of the regular inspection and maintenance programs for nuclear power plants. Besides a plant specific assessment of the reliability data a generic assessment for an application as input data for fault tree analyses in the framework of probabilistic risk studies for other German plants was carried out. The analyses of failures and unavailabilities gave the impression that most of them are single failures without relevance for the plant safety. The data gained from NPPs were compared to reliability data of the German insurance companies for the same protection features installed in non-nuclear installations and to older nuclear specific reliability data. This comparison showed up a higher reliability. (orig.) [de

  15. A tool for Load Modeling in Induction Hardening Equipment Driven by Power Semiconductor Systems

    International Nuclear Information System (INIS)

    Suarez Antola, R.; Suarez Bagnasco, D.

    2006-01-01

    Kelvin effect (Skin effect) is used in surface hardening produced by induction heating of gears, camforms, camshafts and other work pieces of fairly complex geometries.The induction heating equipment for surface hardening of metals and alloys (using LF or medium frequencies in the jargon of induction heating) is composed by a coil or coil assembly and a power semiconductor driving system up to 50kHz. The load seen by the driving system is equivalent to a transformer. The primary corresponds to the excitation coil or coil assembly, and the work piece corresponds to a short-circuited secondary. To asses the electrical load it is necessary to determine the variations in skin depth from place to place due to local curvature effects in the work piece, and its variations in space and time due to variations in conductivity and magnetic properties coupled with thermal effects. In these and others technical applications of Kelvin effect it is often necessary to be able to relate local skin depths with local curvatures of the surface of electrically conductive bodies.The purpose of this paper is twofold. First, derive a closed form analytical formula that relates the local skin depth with the local mean curvature and the well known skin depth for a flat conductive body. The limits of applicability of this formula are discussed. The predicted skin depths are compared with available experimental results obtained in the framework of surface hardening processes. Second, apply the above mentioned formula to describe the electrical load of the induction heating equipment in the conditions used for surface hardening. In the choice or design of an induction heating system the parameters of the intended process (depth of Kelvin effect, temperatures to be reached and duration of the heating process, amongst others) put restrictions over the coils and the power driving system. To determine the best shape and size of induction coils or coil assemblies, the complex thermal and

  16. Bearing support for receiving used fuel elements of nuclear power stations

    International Nuclear Information System (INIS)

    Krieger, F.

    1979-01-01

    A bearing support for receiving used fuel elements of nuclear power stations includes a plurality of chambers which have square cross-sections and each include inner and outer spaced apart walls with screening plates therebetween for screening the radiating fuel elements. Each chamber is detachably secured at its underside to a common foot plate and is held in position at its upper side by spacer elements. The outer wall comprises two equal-sided angle sheets and the inner wall comprises a closed square tube. The thickness of the outer wall is smaller than that of the inner wall and the outer walls are held in spaced relationship to each other at their upper sides by detachable bar grates

  17. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    International Nuclear Information System (INIS)

    Korsah, K.

    2001-01-01

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in

  18. Survey and analysis on environmental and electromagnetic effect on instrumentation and control equipment of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, In Koo; Lee, Dong Young; Cha, Kyung Ho

    2001-03-01

    As the instrumentation and control (I and C) equipment suppliers tend to provide digital components rather than conventional analog type components for instrumentation and control systems of nuclear power plants(NPPs), it is unavoidable to adopt digital equipment for safety I and C systems as well as non-safety systems. However, the full introduction of digital equipment for I and C systems of nuclear power plants raises several concerns which have not been considered in conventional analog I and C equipment. The two major examples of the issues of digital systems are environmental/electromagnetic compatibility (EMC) and software reliability. This report presents the survey and research results on environmental and electromagnetic effect on I and C equipment of nuclear power plants to give a guideline for aging management and design process. Electromagnetic site surveys were conducted to be used as a part of technical basis to demonstrate that I and C systems are compatible with the ambient electromagnetic noise in Korean nuclear power plants.

  19. Analysis of impact of “strong DC and weak AC” on receiving-end power system

    Science.gov (United States)

    Wang, Qiang; Li, Tianran; Yang, Pengcheng

    2018-02-01

    The rapid development of UHVDC transmission project has brought abundant power supply to the receiving-end power system area, but also many security and stability problems. This paper summarizes four elements that affect the strength of AC system, and then simulates the most basic two-terminal single-pole UHV transmission system by MATLAB/Simulink. It analyses the impact of receiving-end AC power system strength on real-time power, frequency and voltage. Finally, in view of operation risk of “strong DC and weak AC”, this paper puts forward three countermeasures.

  20. 49 CFR 176.905 - Motor vehicles or mechanical equipment powered by internal combustion engines.

    Science.gov (United States)

    2010-10-01

    ... of ignition. A motor vehicle or mechanical equipment showing any signs of leakage or electrical fault... equipment is stowed. (f) Each hold or compartment must be ventilated and fitted with an overhead water... smoke or fire detection system capable of alerting personnel on the bridge. (h) All electrical equipment...

  1. THE OPERATION OF POWER EQUIPMENT DURING THE DISPOSAL OF COMBUSTIBLE GASES ASSOCIATED WITH GEOTHERMAL WATER

    Directory of Open Access Journals (Sweden)

    G. Ya. Akhmedov

    2017-01-01

    Full Text Available Objectives. The aim of the study is to assess the appropriateness of utilising combustible gases associated with geothermal water with  low gas factor and the possibility of its practical implementation with  the provision of power equipment operation of geothermal systems  with a nonscaling mode.Methods. The investigations were carried out by analysing the content of associated combustible gases in the underground  thermomineral waters of the Cis-Caucasian deposits on the basis of  an assessment of the feasibility of their utilisation for heating and  hot water supply.Results. A review of practically existing heat and power schemes  utilising geothermal water sources is carried out. Based on the  studies conducted, it is found that methane (70-90% is prevalent in the water under consideration; meanwhile, the content of heavy hydrocarbons does not exceed 10%. The concentration of carbon  dioxide is 3 ÷ 6%, nitrogen 1 ÷ 4%. Depending on the depth of the  aquifer, gas factors range from 1 to 5 m3/ m3. As a result of the  analysis of the operation of typical thermal distribution stations, it is  established that a violation of the carbon dioxide equilibrium in water leads to the formation of a solid phase of calcium carbonate on the  heat exchange surface. A technique for estimating the relationship between the partial pressure of methane and carbon dioxide with the total pressure in a solution of geothermal water is proposed. A  scheme for the efficient operation of thermal distribution stations  with the prevention of carbonate deposits formation by using the  combustion products of the used gas combined with the injection of waste water back into the aquifer is presented.Conclusion. As a result of the conducted studies, the possibility of  using associated combustible gases in geothermal wells is  established using differences in their solubility and that of carbon  dioxide. In this case, the protection of

  2. Solar Central Receiver Hybrid Power Systems sodium-cooled receiver concept. Final report. Volume II, Book 1. Conceptual design, Sections 1 through 4

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    The overall, long-term objective of the Solar Central Receiver Hybrid Power System program is to identify, characterize, and ultimately demonstrate the viability and cost effectiveness of solar/fossil, steam Rankine cycle, hybrid power systems that: (1) consist of a combined solar central receiver energy source and a nonsolar energy source at a single, common site, (2) may operate in the base, intermediate, and peaking capacity modes, (3) produce the rated output independent of variations in solar insolation, (4) provide a significant savings (50% or more) in fuel consumption, and (5) produce power at the minimum possible cost in mills/kWh. It is essential that these hybrid concepts be technically feasible and economically competitive with other systems in the near to mid-term time period (1985-1990) on a commercial scale. The program objective for Phase I is to identify and conceptually characterize solar/fossil steam Rankine cycle, commercial-scale, power plant systems that are economically viable and technically feasible. This volume presents in detail the market analysis, parametric analysis, and the selection process for the preferred system. (WHK)

  3. On the evolution of the regulatory guidance for seismic qualification of electric and active mechanical equipment for nuclear power plants

    International Nuclear Information System (INIS)

    Ng, Ching Hang; Chen, Pei-Ying

    2009-01-01

    All electric and active mechanical equipment important to safety for nuclear power plants must be seismically qualified by testing, analysis, or combined analysis and testing. The general requirements for seismic qualification of electric and active mechanical equipment in nuclear power plants are delineated in Appendix S, 'Earthquake Engineering Criteria for Nuclear Power Plants,' to Title 10, Part 50, 'Domestic Licensing of Production and Utilization Facilities,' of the Code of Federal Regulations (10 CFR Part 50), item 52.47(20) of 10 CFR 52.47, 'Contents of Applications; Technical Information,' and Appendix A, 'Seismic and Geologic Siting Criteria for Nuclear Power Plants,' to 10 CFR Part 100, 'Reactor Site Criteria.' The United States Nuclear Regulatory Commission (NRC) issued Revision 2 of Regulatory Guide (RG) 1.100, 'Seismic Qualification of Electric and Mechanical for Nuclear Power Plants' in 1988, which endorsed, with restrictions, exceptions, and clarifications, Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 'IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,' for use in seismic qualification of both electric and mechanical equipment. In 2008, the staff at the NRC drafted Revision 3 of RG 1.100 to endorse, with restrictions, exceptions, and clarifications, the IEEE Std 344-2004 and the American Society of Mechanical Engineers (ASME) QME-1-2007 'Qualification of Active Mechanical Equipment Used in Nuclear Power Plants.' IEEE Std 344-2004 was an update of Std 344-1987 and ASME QME-1-2007 was an update of QME-1-2002. The major changes in IEEE Std 344-2004 and ASME QME-1-2007 include the update and expansion of criteria and procedures describing the use of experience data as a method for seismic qualification of Class 1E electric equipment (including I and C components) as well as active mechanical equipment. In this paper, the staff will compare the draft Revision 3 to

  4. Insights into Dynamic Tuning of Magnetic-Resonant Wireless Power Transfer Receivers Based on Switch-Mode Gyrators

    Directory of Open Access Journals (Sweden)

    Mohamed Saad

    2018-02-01

    Full Text Available Magnetic-resonant wireless power transfer (WPT has become a reliable contactless source of power for a wide range of applications. WPT spans different power levels ranging from low-power implantable devices up to high-power electric vehicles (EV battery charging. The transmission range and efficiency of WPT have been reasonably enhanced by resonating the transmitter and receiver coils at a common frequency. Nevertheless, matching between resonance in the transmitter and receiver is quite cumbersome, particularly in single-transmitter multi-receiver systems. The resonance frequency in transmitter and receiver tank circuits has to be perfectly matched, otherwise power transfer capability is greatly degraded. This paper discusses the mistuning effect of parallel-compensated receivers, and thereof a novel dynamic frequency tuning method and related circuit topology and control is proposed and characterized in the system application. The proposed method is based on the concept of switch-mode gyrator emulating variable lossless inductors oriented to enable self-tunability in WPT receivers.

  5. Wireless Power Supply via Coupled Magnetic Resonance for on-line Monitoring Wireless Sensor of High-voltage Electrical Equipment

    DEFF Research Database (Denmark)

    Xingkui, Mao; Qisheng, Huang; Yudi, Xiao

    2016-01-01

    On-line monitoring of high-voltage electrical equipment (HV-EE) aiming to detect faults effectively has become crucial to avoid serious accidents. Moreover, highly reliable power supplies are the key component for the wireless sensors equipped in such on-line monitoring systems. Therefore......, in this paper, the wireless power supply via coupled magnetic resonance (MR-WPS) is proposed for powering the wireless sensor and the associated wireless sensor solution is also proposed. The key specifications of the MR-WPS working in switchgear cabinet with a harsh operation environment are analyzed...... power is able to be delivered to the wireless sensor through the designed MR-WPS, and therefore the theoretical analysis and design is verified....

  6. Development of 3 D Electric Field Analysis Program under Power System Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Myung, S. H.; Lee, K. C.; Lee, J. B.; Ha, T. H. [Korea Electrotechnology Research Institute, Changwon (Korea, Republic of)

    1996-12-01

    Recently, as the effects of electric fields on animals, human beings and sensitive equipment have been reported, the study on electric fields has become more important. Transmission lines and substation among power facilities are dominant parts related to electrical environment. Electric field analysis of transmission line has been made using image charge method or CSM since 1970`s, however electric field analysis in substation has been rarely studied due to the complexity of three dimensional evaluation of an electric field in substation. For the rather complicated and time-consuming three-dimensional electric field calculation in the vicinity of transmission lines and substations, this study proposes an effective numerical calculation method based on Charge Simulation Method(CSM). In order to represent non-uniform charge distribution on an electrode better, it is subdivided into small segments with linear charge density. Each segment with linear charge density can be easily represented by a generalized finite line type of charge whose expressions for potential and electric field were analytically derived and which was named {sup f}inite slant line charge in this study. As for the arrangement of small segments of a subdivided electrode, it has been found that unequally spaced arrangement method is superior to equally spaced one. In order to arrange segments fast and effectively, effective formulas were derived from multiple regression analysis of many simulations. The proposed method is applied to the electric field calculation around the transmission lines with significant change in direction and substation busbars. (author). refs., figs., tabs.

  7. The influence of molecular layers of amines on the hydraulic resistance of piping systems and power plant equipment

    Energy Technology Data Exchange (ETDEWEB)

    Ryzhenkov, Viacheslav A.; Ryzhenkov, Artem V. [Moscow Power Engineering Institute / Technical Univ. (Russian Federation). Dept. of Industrial Heat and Power Systems; Petrova, Tamara I. [Moscow Power Engineering Institute / Technical Univ. (Russian Federation). Water and Fuel Technology Dept.

    2012-07-15

    The current state of pipeline systems and power equipment has a high accident rate due to intense corrosion, the accumulation of deposits on heat and in-line transfer surfaces, and high hydraulic resistance. Analysis and synthesis of published results shows that the solution to improving the efficiency of pipeline systems and power equipment can be approached from two directions: (i) the impact on the properties of transported media and (ii) changes in the properties of functional surfaces of pipelines and equipment. Improving the ''quality'' of the technological agents involves very substantial capital and operating costs, so the most promising way is to modify the surface properties. Studies conducted at the National Research University MPEI showed that these problems are solved more effectively by means of molecular layers of adsorbed amines on the functional surfaces of pipes and equipment. When present in a certain way with the optimal number of molecular amine layers, these significantly alter the surface properties of conventional structural materials, which leads to very substantial improvement in the hydrodynamic characteristics: reduction of the hydraulic resistance of pipelines and equipment (up to 40 %), almost complete stoppage of corrosion processes (up to 7 times), and a multiple (up to 10-fold) reduction in the rate of deposit accumulation. The method of adsorption of molecular amine layers and the equipment for its implementation developed on the basis of this research will not only reduce flow resistance, but will also significantly improve the operating efficiency of pipeline systems and power equipment generally. (orig.)

  8. Optimisation of a Kalina cycle for a central receiver solar thermal power plant with direct steam generation

    DEFF Research Database (Denmark)

    Modi, Anish; Haglind, Fredrik

    2014-01-01

    Central receiver solar thermal power plants are regarded as one of the promising ways to generate electricity in near future. They offer the possibility of using high temperatures and pressures to achieve high efficiencies with standard power cycles. A direct steam generation approach can be used...

  9. Cycle chemistry monitoring system as means of improving the reliability of the equipment at the power plants

    Science.gov (United States)

    Yegoshina, O. V.; Voronov, V. N.; Yarovoy, V. O.; Bolshakova, N. A.

    2017-11-01

    There are many problems in domestic energy at the present that require urgent solutions in the near future. One of these problems - the aging of the main and auxiliary equipment. Wear of equipment is the cause of decrease reliability and efficiency of power plants. Reliability of the equipment are associated with the introduction of cycle chemistry monitoring system. The most damageable equipment’s are boilers (52.2 %), turbines (12.6 %) and heating systems (12.3 %) according to the review of failure rate on the power plants. The most part of the damageability of the boiler is heated surfaces (73.2 %). According to the Russian technical requirements, the monitoring systems are responsible to reduce damageability the boiler heating surfaces and to increase the reliability of the equipment. All power units capacity of over 50 MW are equipped with cycle chemistry monitoring systems in order to maintain water chemistry within operating limits. The main idea of cycle chemistry monitoring systems is to improve water chemistry at power plants. According to the guidelines, cycle chemistry monitoring systems of a single unit depends on its type (drum or once-through boiler) and consists of: 20…50 parameters of on-line chemical analyzers; 20…30 «grab» sample analyses (daily) and about 15…20 on-line monitored operating parameters. The operator of modern power plant uses with many data at different points of steam/water cycle. Operators do not can estimate quality of the cycle chemistry due to the large volume of daily and every shift information and dispersion of data, lack of systematization. In this paper, an algorithm for calculating the quality index developed for improving control the water chemistry of the condensate, feed water and prevent scaling and corrosion in the steam/water cycle.

  10. Qualification of Electrical Equipment in Nuclear Power Plants - Management of ageing

    International Nuclear Information System (INIS)

    Spaang, Kjell; Staahl, Gunnar

    2013-02-01

    The purpose of this report is to describe programs and tools for assessment of accomplished and documented qualification with respect to ageing of electrical equipment and for development of complimentary ageing management programs. In addition to description of complete programs for management of ageing, tools for validation of the status with regard to ageing of installed ('old') equipment and, where needed, for complementation of their qualification are also included. The report is restricted to safety related equipment containing ageing sensitive parts, mainly organic materials. To this category belong cables and cable joints and a number of equipment containing oils, seals (o-rings), etc. For equipment located in the containment, the possibilities of continuous supervision are limited. The accessibility for regular inspections is also limited in many cases. The main part of this report deals with the qualification of such equipment. Some safety related equipment outside the containment can be located in areas where they are subjected to high temperature and other excessive environmental stresses during normal operation and in areas affected by an accident. Therefore, some material is given also on qualification of equipment located outside containment with better possibilities for frequent inspection and supervision. Part 1 of the report is an executive summary with a general review of the methodologies and their application. The more detailed description of the programs and underlying material, useful data, etc. is given in Part 2

  11. Optimal Active Power Control of A Wind Farm Equipped with Energy Storage System based on Distributed Model Predictive Control

    DEFF Research Database (Denmark)

    Zhao, Haoran; Wu, Qiuwei; Guo, Qinglai

    2016-01-01

    This paper presents the Distributed Model Predictive Control (D-MPC) of a wind farm equipped with fast and short-term Energy Storage System (ESS) for optimal active power control using the fast gradient method via dual decomposition. The primary objective of the D-MPC control of the wind farm...... is power reference tracking from system operators. Besides, by optimal distribution of the power references to individual wind turbines and the ESS unit, the wind turbine mechanical loads are alleviated. With the fast gradient method, the convergence rate of the DMPC is significantly improved which leads...

  12. Combined prediction model for supply risk in nuclear power equipment manufacturing industry based on support vector machine and decision tree

    International Nuclear Information System (INIS)

    Shi Chunsheng; Meng Dapeng

    2011-01-01

    The prediction index for supply risk is developed based on the factor identifying of nuclear equipment manufacturing industry. The supply risk prediction model is established with the method of support vector machine and decision tree, based on the investigation on 3 important nuclear power equipment manufacturing enterprises and 60 suppliers. Final case study demonstrates that the combination model is better than the single prediction model, and demonstrates the feasibility and reliability of this model, which provides a method to evaluate the suppliers and measure the supply risk. (authors)

  13. Containment Response Analysis for Equipment Qualification of Kori Nuclear Power Plant Unit 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Byun, Choong Sup; Song, Dong Soo; Hwang, Yong Jun [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Seo, Kwi Hyun; Song, Wan Jung [ENERGEO Inc., Sungnam (Korea, Republic of)

    2006-07-01

    Equipment that is used to perform a necessary safety function must be capable of maintaining functional operability under all service condition postulated to occur during the installed life for the time it is required. The pressure and temperature analyses for loss of coolant accident and main steam line break accident provide the bounding test envelope inside containment for the operability evaluation of safety equipment in harsh environmental. This paper describes the results of the containment pressure and temperature analysis for the equipment qualification (EQ) envelopes of Kori unit 3 and 4.

  14. Assessing the dose values received by patients during conventional radiography X-ray examinations and the technical condition of the equipment used for this purpose.

    Science.gov (United States)

    Bekas, Marcin; Pachocki, Krzysztof A; Waśniewska, Elżbieta; Bogucka, Dagmara; Magiera, Andrzej

    2014-01-01

    X-ray examination is associated with patient exposure to ionizing radiation. Dose values depend on the type of medical procedure used, the X-ray unit technical condition and exposure conditions selected. The aim of this study was to determine the dose value received by patients during certain conventional radiography X-ray examinations and to assess the technical condition of medical equipment used for this purpose. The study covered the total number of 118 conventional diagnostic X-ray units located in the Masovian Voivodeship. The methodology used to assess the conventional diagnostic X-ray unit technical condition and the measurement of the radiation dose rate received by patients are based on test procedures developed by the Department of Radiation Protection and Radiobiology of the National Institute of Public Health - National Institute of Hygiene (Warszawa, Poland) accredited for compliance with PN-EN 17025 standard by the Polish Centre for Accreditation. It was found that 84.7% of X-ray units fully meet the criteria set out in the Polish legislation regarding the safe use of ionizing radiation in medicine, while 15.3% of the units do not meet some of them. The broadest dose value range was recorded for adult patients. Particularly, during lateral (LATl) lumbar spine radiography the recorded entrance surface dose (ESD) values ranged from 283.5 to 7827 µGy (mean: 2183.3 µGy). It is absolutely necessary to constantly monitor the technical condition of all X-ray units, because it affects population exposure to ionizing radiation. Furthermore, it is essential to raise radiographers' awareness of the effects that ionizing radiation exposure can have on the human body.

  15. TMI-2 [Three Mile Island Nuclear Power Station] fuel canister and core sample handling equipment used in INEL hot cells

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Shurtliff, W.T.; Lynch, R.J.; Croft, K.M.; Whitmill, L.J.; Allen, S.M.

    1987-01-01

    This paper describes the specialized remote handling equipment developed and used at the Idaho National Engineering Laboratory (INEL) to handle samples obtained from the core of the damaged Unit 2 reactor at Three Mile Island Nuclear Power Station (TM-2). Samples of the core were removed, placed in TMI-2 fuel canisters, and transported to the INEL. Those samples will be examined as part of the analysis of the TMI-2 accident. The equipment described herein was designed for removing sample materials from the fuel canisters, assisting with initial examination, and processing samples in preparation for detailed examinations. The more complex equipment used microprocessor remote controls with electric motor drives providing the required force and motion capabilities. The remaining components were unpowered and manipulator assisted

  16. A Low-Power WLAN Communication Scheme for IoT WLAN Devices Using Wake-Up Receivers

    Directory of Open Access Journals (Sweden)

    Hanseul Hong

    2018-01-01

    Full Text Available In this paper, we propose a delay- and power-efficient, multi-user, low-power wireless local area network (WLAN communication scheme for Internet of Things (IoT WLAN devices. Extremely low-power operation is one of the key requirements of emerging IoT devices. However, the current duty-cycle-based power saving approach may incur large access delay times owing to the trade-offs between the power consumption and the access delay. In order to reduce this delay and enhance the power-saving performance, wake-up receiver-based schemes have been proposed. However, because wake-up receiver-based schemes do not consider multiuser operation in dense communication environments, large delays are inevitable in the case of multiuser operation. In order to provide extremely low-power operation and under 1-mW standby power with reduced delay, we employed the optimized multiuser transmission scheduling of IEEE 802.11ax in the proposed scheme and proper enhanced distributed channel access (EDCA parameter settings. This is with the aim to reduce the delay caused by long wake-up times, and to avoid collisions caused by simultaneous transmission in uplink multiuser scenario. By using the proposed scheme, simultaneous IoT communication with multiple mobile IoT devices is possible while providing low-power operation. Simulation results verified the outstanding delay performance of the proposed scheme.

  17. Ultrasonic power transfer from a spherical acoustic wave source to a free-free piezoelectric receiver: Modeling and experiment

    Energy Technology Data Exchange (ETDEWEB)

    Shahab, S.; Gray, M.; Erturk, A., E-mail: alper.erturk@me.gatech.edu [G. W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States)

    2015-03-14

    Contactless powering of small electronic components has lately received growing attention for wireless applications in which battery replacement or tethered charging is undesired or simply impossible, and ambient energy harvesting is not a viable solution. As an alternative to well-studied methods of contactless energy transfer, such as the inductive coupling method, the use of ultrasonic waves transmitted and received by piezoelectric devices enables larger power transmission distances, which is critical especially for deep-implanted electronic devices. Moreover, energy transfer by means of acoustic waves is well suited in situations where no electromagnetic fields are allowed. The limited literature of ultrasonic acoustic energy transfer is mainly centered on proof-of-concept experiments demonstrating the feasibility of this method, lacking experimentally validated modeling efforts for the resulting multiphysics problem that couples the source and receiver dynamics with domain acoustics. In this work, we present fully coupled analytical, numerical, and experimental multiphysics investigations for ultrasonic acoustic energy transfer from a spherical wave source to a piezoelectric receiver bar that operates in the 33-mode of piezoelectricity. The fluid-loaded piezoelectric receiver under free-free mechanical boundary conditions is shunted to an electrical load for quantifying the electrical power output for a given acoustic source strength of the transmitter. The analytical acoustic-piezoelectric structure interaction modeling framework is validated experimentally, and the effects of system parameters are reported along with optimal electrical loading and frequency conditions of the receiver.

  18. Ultrasonic power transfer from a spherical acoustic wave source to a free-free piezoelectric receiver: Modeling and experiment

    International Nuclear Information System (INIS)

    Shahab, S.; Gray, M.; Erturk, A.

    2015-01-01

    Contactless powering of small electronic components has lately received growing attention for wireless applications in which battery replacement or tethered charging is undesired or simply impossible, and ambient energy harvesting is not a viable solution. As an alternative to well-studied methods of contactless energy transfer, such as the inductive coupling method, the use of ultrasonic waves transmitted and received by piezoelectric devices enables larger power transmission distances, which is critical especially for deep-implanted electronic devices. Moreover, energy transfer by means of acoustic waves is well suited in situations where no electromagnetic fields are allowed. The limited literature of ultrasonic acoustic energy transfer is mainly centered on proof-of-concept experiments demonstrating the feasibility of this method, lacking experimentally validated modeling efforts for the resulting multiphysics problem that couples the source and receiver dynamics with domain acoustics. In this work, we present fully coupled analytical, numerical, and experimental multiphysics investigations for ultrasonic acoustic energy transfer from a spherical wave source to a piezoelectric receiver bar that operates in the 33-mode of piezoelectricity. The fluid-loaded piezoelectric receiver under free-free mechanical boundary conditions is shunted to an electrical load for quantifying the electrical power output for a given acoustic source strength of the transmitter. The analytical acoustic-piezoelectric structure interaction modeling framework is validated experimentally, and the effects of system parameters are reported along with optimal electrical loading and frequency conditions of the receiver

  19. EMI environment EMC considerations concerning equipment upgrades at a nuclear utility power generating station a case history

    International Nuclear Information System (INIS)

    Metcalf, M.J.

    1993-01-01

    As equipment is upgraded during scheduled power outages in nuclear power generating stations, more and more utilities will be faced with the problem of dealing with Electromagnetic Compatibility (EMC) issues that have evolved with the trend of manufacturers designing equipment based around state-of-the-art high technology logic devices. This paper lists Commonwealth Edison Company (CECO) equipment that was scrutinized by National Technical Systems (NTS) for its EMI impact. The test requirements and test procedures for assessing EMI and EMC are outlined. Although on-site mapping data was gathered to assist CECO for the upgrade described here of the Auxiliary Electric Equipment Room of a Westinghouse Eagle 21 Reactor Protection System at the Zion Unit No.1 Station, blanket mapping of every location for every upgrade is a short term, expensive solution to the EMI problem. It is concluded that the primary problem of lack of system and component level EMI specifications must be addressed by a governing body. 7 refs., 2 figs

  20. 12 CFR 627.2725 - Powers and duties of the receiver.

    Science.gov (United States)

    2010-01-01

    ... of the institution under law and the charter, articles, and bylaws of the institution. (2) Take any... intangible). (13) Purchase or lease office space, automobiles, furniture, equipment, and supplies, and..., release, or obtain release of, for cash or other consideration, claims and demands against or in favor of...

  1. A Novel WPT System Based on Dual Transmitters and Dual Receivers for High Power Applications: Analysis, Design and Implementation

    Directory of Open Access Journals (Sweden)

    Yong Li

    2017-02-01

    Full Text Available Traditional Wireless Power Transfer (WPT systems only have one energy transmission path, which can hardly meet the power demand for high power applications, e.g., railway applications (electric trains and trams, etc. due to the capacity constraints of power electronic devices. A novel WPT system based on dual transmitters and dual receivers is proposed in this paper to upgrade the power capacity of the WPT system. The reliability and availability of the proposed WPT system can be dramatically improved due to the four energy transmission paths. A three-dimensional finite element analysis (FEA tool ANSYS MAXWELL (ANSYS, Canonsburg, PA, USA is adopted to investigate the proposed magnetic coupling structure. Besides, the effects of the crossing coupling mutual inductances among the transmitters and receivers are analyzed. It shows that the same-side cross couplings will decrease the efficiency and transmitted power. Decoupling transformers are employed to mitigate the effects of the same-side cross couplings. Meanwhile, the output voltage in the secondary side can be regulated at its designed value with a fast response performance, and the system can continue work even with a faulty inverter. Finally, a scale-down experimental setup is provided to verify the proposed approach. The experimental results indicate that the proposed method could improve the transmitted power capacity, overall efficiency and reliability, simultaneously. The proposed WPT structure is a potential alternative for high power applications.

  2. Optimal design of wind power generation equipment%风力发电设备的优化设计

    Institute of Scientific and Technical Information of China (English)

    宗倩

    2016-01-01

    风能清洁无污染,是人们梦寐以求的新能源。风力发电是一种有效利用风能的新形式,风力发电设备决定着发电效率与发电成本,因此优化发电设备至关重要。通过阐述风力发电基本原理及现代风机的基本组成,提出风力发电设备优化设计的几点思路,为提高风力发电可利用价值提供参考。%Wind power is clean and pollution-free, which is the new energy people want to use. Wind power generation is aneffectivenewformofusingwindenergy,windpowergenerationequipmentdeterminestheefficiencyandcostofpower generation, therefore to optimize power generation equipment is essential. Through elaborating basic composition of wind power generation and basic principles of modern wind turbines, this paper proposed a few ideas on optimal design of wind power generation equipment, which provided reference for increasing its use value.

  3. Assessing the impact of space weather on the electric power grid based on insurance claims for industrial electrical equipment

    Science.gov (United States)

    Schrijver, C. J.; Dobbins, R.; Murtagh, W.; Petrinec, S. M.

    2014-07-01

    Geomagnetically induced currents are known to induce disturbances in the electric power grid. Here we perform a statistical analysis of 11,242 insurance claims from 2000 through 2010 for equipment losses and related business interruptions in North American commercial organizations that are associated with damage to, or malfunction of, electrical and electronic equipment. We find that claim rates are elevated on days with elevated geomagnetic activity by approximately 20% for the top 5% and by about 10% for the top third of most active days ranked by daily maximum variability of the geomagnetic field. When focusing on the claims explicitly attributed to electrical surges (amounting to more than half the total sample), we find that the dependence of claim rates on geomagnetic activity mirrors that of major disturbances in the U.S. high-voltage electric power grid. The claim statistics thus reveal that large-scale geomagnetic variability couples into the low-voltage power distribution network and that related power-quality variations can cause malfunctions and failures in electrical and electronic devices that, in turn, lead to an estimated 500 claims per average year within North America. We discuss the possible magnitude of the full economic impact associated with quality variations in electrical power associated with space weather.

  4. Conceptual design of advanced central receiver power systems sodium-cooled receiver concept. Volume 2, Book 1. Commercial plant conceptual design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-03-01

    The conceptual design of the 100-MW solar tower focus commercial power plant is described in detail. Sodium is pumped up to the top of a tall tower where the receiver is located. The sodium is heated in the receiver and then flows down the tower, through a pressure reducing device, and thence into a large, hot storage tank which is located at ground level and whose size is made to meet a specific thermal energy storage capacity requirement. From this tank, the sodium is pumped by a separate pump, through a system of sodium-to-water steam generators. The steam generator system consists of a separate superheater and reheater operating in parallel and an evaporator unit operating in series with the other two units. The sodium flowing from the evaporator unit is piped to a cold storage tank. From the cold storage tank, sodium is then pumped up to the tip of the tower to complete the cycle. The steam generated in the steam generators is fed to a conventional off-the-shelf, high-efficiency turbine. The steam loop operates in a conventional rankine cycle with the steam generators serving the same purpose as a conventional boiler and water being fed to the evaporator with conventional feedwater pumps. The pressure reducing device (a standard drag valve, for example) serves to mitigate the pressure caused by the static head of sodium and thus allows the large tanks to operate at ambient pressure conditions. (WHK)

  5. A Low-Power High-Dynamic-Range Receiver System for In-Probe 3-D Ultrasonic Imaging.

    Science.gov (United States)

    Attarzadeh, Hourieh; Xu, Ye; Ytterdal, Trond

    2017-10-01

    In this paper, a dual-mode low-power, high dynamic-range receiver circuit is designed for the interface with a capacitive micromachined ultrasonic transducer. The proposed ultrasound receiver chip enables the development of an in-probe digital beamforming imaging system. The flexibility of having two operation modes offers a high dynamic range with minimum power sacrifice. A prototype of the chip containing one receive channel, with one variable transimpedance amplifier (TIA) and one analog to digital converter (ADC) circuit is implemented. Combining variable gain TIA functionality with ADC gain settings achieves an enhanced overall high dynamic range, while low power dissipation is maintained. The chip is designed and fabricated in a 65 nm standard CMOS process technology. The test chip occupies an area of 76[Formula: see text] 170 [Formula: see text]. A total average power range of 60-240 [Formula: see text] for a sampling frequency of 30 MHz, and a center frequency of 5 MHz is measured. An instantaneous dynamic range of 50.5 dB with an overall dynamic range of 72 dB is obtained from the receiver circuit.

  6. Compact Low-Power-Consumption 28-Gbaud QPSK/16-QAM Integrated Silicon Photonic/Electronic Coherent Receiver

    NARCIS (Netherlands)

    Zhang, J.; Verbist, J.; Moeneclaey, B.; van Weerdenburg, J.; van Uden, R.G.H.; Chen, H.; van Campenhout, J.; Okonkwo, C; Yin, X; Bauwelinck, J.; Roelkens, G.

    2016-01-01

    We demonstrate the codesign and cointegration of an ultracompact silicon photonic receiver and a low-power-consumption (155 mW/channel) two-channel linear transimpedance amplifier array. Operation below the forward error coding (FEC) threshold both for quadrature phase-shift keying (QPSK) and

  7. Effects of supporting structures on dynamic response of nuclear power plant equipment and piping systems

    International Nuclear Information System (INIS)

    Stoykovich, M.

    1982-01-01

    This paper presents the evaluation of the effects of supporting structures in dynamic analysis of equipment or piping systems, which involves formulations for determining reduced stiffness and mass matrices associated with the number of degrees of freedom corresponding to the support nodal points of a finite element model. Also, evaluation of a composite damping matrix associated with different damping properties of supporting structures, equipment, and piping systems is considered. Determination of spring constants, effective masses and mass moments of inertia, and damping values as fractions of critical damping on the basis of the theory of rigid bases on the surfaces of an elastic halfspace is demonstrated

  8. Thermal design of a fully equipped solar-powered desert home

    KAUST Repository

    Serag-Eldin, M.A.

    2010-01-01

    The paper presents a conceptual design and thermodynamic analysis of a solar-powered desert home. The home is airconditioned and provides all modern comforts and facilities. Electrical power, which drives the entire energy system, is generated

  9. Plasma and process characterization of high power magnetron physical vapor deposition with integrated plasma equipment--feature profile model

    International Nuclear Information System (INIS)

    Zhang Da; Stout, Phillip J.; Ventzek, Peter L.G.

    2003-01-01

    High power magnetron physical vapor deposition (HPM-PVD) has recently emerged for metal deposition into deep submicron features in state of the art integrated circuit fabrication. However, the plasma characteristics and process mechanism are not well known. An integrated plasma equipment-feature profile modeling infrastructure has therefore been developed for HPM-PVD deposition, and it has been applied to simulating copper seed deposition with an Ar background gas for damascene metalization. The equipment scale model is based on the hybrid plasma equipment model [M. Grapperhaus et al., J. Appl. Phys. 83, 35 (1998); J. Lu and M. J. Kushner, ibid., 89, 878 (2001)], which couples a three-dimensional Monte Carlo sputtering module within a two-dimensional fluid model. The plasma kinetics of thermalized, athermal, and ionized metals and the contributions of these species in feature deposition are resolved. A Monte Carlo technique is used to derive the angular distribution of athermal metals. Simulations show that in typical HPM-PVD processing, Ar + is the dominant ionized species driving sputtering. Athermal metal neutrals are the dominant deposition precursors due to the operation at high target power and low pressure. The angular distribution of athermals is off axis and more focused than thermal neutrals. The athermal characteristics favor sufficient and uniform deposition on the sidewall of the feature, which is the critical area in small feature filling. In addition, athermals lead to a thick bottom coverage. An appreciable fraction (∼10%) of the metals incident to the wafer are ionized. The ionized metals also contribute to bottom deposition in the absence of sputtering. We have studied the impact of process and equipment parameters on HPM-PVD. Simulations show that target power impacts both plasma ionization and target sputtering. The Ar + ion density increases nearly linearly with target power, different from the behavior of typical ionized PVD processing. The

  10. Combined cycle solar central receiver hybrid power system study. Volume III. Appendices. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-11-01

    A design study for a 100 MW gas turbine/steam turbine combined cycle solar/fossil-fuel hybrid power plant is presented. This volume contains the appendices: (a) preconceptual design data; (b) market potential analysis methodology; (c) parametric analysis methodology; (d) EPGS systems description; (e) commercial-scale solar hybrid power system assessment; and (f) conceptual design data lists. (WHK)

  11. Construction of Power Receiving Rectenna Using Mars- In-Situ Materials; A Low Energy Materials Processing Approach

    Science.gov (United States)

    Curreri, Peter A.; Rose, M. Franklin (Technical Monitor)

    2001-01-01

    It is highly desirable to have a non-nuclear power rich option for the human exploration of Mars. Utilizing a Solar Electric Propulsion, SEP, / Power Beaming architecture for a non-nuclear power option for a human Mars base potentially avoids the weather and dust sensitivities of the surface photovoltaic option. Further from Mars areosynchronous orbit near year round power can be provided. Mission analysis, however, concludes that ultra high (245 GHz) frequencies or laser transmission technologies are required for Mars landed mass competitiveness with the surface photovoltaic option if the receiving rectifying antenna "rectenna" is transported from Earth. It is suggested in this paper that producing rectenna in situ on Mars surface might make a more conventional 5.8 GHz system competitive with surface PV. The premium of a competitive, robust, continuous base power might make the development of a 10 plus MWe class SEP for human Mars mission a more attractive non-nuclear option.

  12. Application of new control technology during the maintenance of equipment in the Laguna Verde nuclear power plant

    International Nuclear Information System (INIS)

    Ojeda R, M. A.

    2008-01-01

    In the nuclear power plant of Laguna Verde, in normal operation and recharges are carried out activities of preventive maintenance and corrective to different equipment, due to the one displacement of radioactive materials from the vessel of the reactor until the one system of vapor, different radiation levels are generated (from low until very high) in the circuits of vapor and water, the particles can be incrusted on those interior surfaces of the pipes and equipment, creating this way a potential risk of contamination and exhibition during the maintenance of equipment. To help to optimize the dose to the personnel the use of new technology the has been implemented which besides contributing an absolute control of the work, it offers bigger comfort to the one worker during the development of their work, also contributing a supervision more effective of the same one. Using the captured and processed information of the work developed you can use for the personnel's capacitation and feedback of the work for the continuous improvement of the same one. During a reduction of programmed power and normal operation are carried out maintenance correctives and specific works to preserve the readiness and ability of the equipment and with this to maintain the security of the nuclear power plant. The development of the theme it is showing the advances and commitments of personnel to take to excellence to the nuclear power plant of Laguna Verde showing to the obtained results of the dose and benefits of 2 works carried out in the nuclear power plant where tools ALARA were applied as well as the use of the new technology (Video Equipment of Tele dosimetry and Audio 'VETA') in works carried out in the building of purification level 10.15, change and cuts of filter of the prefilters of system G16, as well as,the retirement and transfer for its decay of High Integrity Container (HIC) of the building of purification level -0.55 to the Temporary Warehouse in Site. Works of high

  13. Fire extinguishing of electrical equipment under voltage at nuclear power plants

    International Nuclear Information System (INIS)

    Capek, Josef

    2009-01-01

    Fire extinguishing on equipment that is under voltage is always hazardous. Conventional fire fighting equipment applicable to this task includes powder and gas extinguishers, which, however, have some drawbacks. Therefore, attention has been increasingly devoted to high-pressure fire extinguishing, whose assets include better heat removal as compared to a full water flow where the majority of the water runs off without any cooling effect. This article describes the testing of some types and combinations of extinguishing techniques and their interpretation based on earth-leakage current measurement and determination of a safe distance for fire extinguishing. Methodology described in CSN IEC 60-1:1994 and CSN EN 3-7:2004 was applied. To meet the criterion, none of the tests was to exhibit an earth-leakage current higher than 0.5 mA. In the accredited laboratory test room setup, 3 extinguishing equipment arrangements proved to extinguish fire on electrical equipment under voltage at a safe distance of 1 m (or 3 m). (orig.)

  14. 30 CFR 75.1909 - Nonpermissible diesel-powered equipment; design and performance requirements.

    Science.gov (United States)

    2010-07-01

    ... energy, or leakage; (4) Releases only by a manual control that does not operate any other equipment...; and (xi) A water separator and fuel filter(s) must be provided. (4) A sensor to monitor the..., and accelerator pedals, controls which are of automobile orientation; (4) An audible warning device...

  15. Wideband Modeling of Power Transformers Using Commercial sFRA Equipment

    DEFF Research Database (Denmark)

    Holdyk, Andrzej; Gustavsen, B.; Arana Aristi, Ivan

    2014-01-01

    is light-weight and considerably less expensive than dedicated high precision laboratory equipment. The use of 50 Ω termination resistors allows measuring the terminal admittance matrix without a need for correcting for the measurement cables. The measured admittance matrix is next subjected to rational...

  16. On safety 1E qualification of electrical equipment for nuclear power stations

    International Nuclear Information System (INIS)

    Segarceanu, D.; Geambasu, C.; Avramescu, M.

    1995-01-01

    Electrical equipment and systems for the emergency shutdown of a nuclear reactor are qualified according to safety class 1E. Methods of qualification meeting the requirements should be used, either individually or in combination include, type-test qualification, qualification by operating experience, qualification by analysis, combined qualification. These methods qualification principles, procedures and documents are discussed. (N.T.). 1 fig

  17. In situ measurement of dynamic characteristics of atomic power plant equipment

    International Nuclear Information System (INIS)

    Arya, A.S.; Gupta, S.P.; Shrivastava, S.K.

    1977-01-01

    For the realistic assessment of stiffness and damping, full scale free vibration tests have been carried out on various pieces of equipment located in plant buildings both during the construction stage and after they are erected. Initial displacement or initial velocity was used to excite the free vibrations. Initial displacement was imparted by means of steel rope pulled with chain pulley block. The sudden release was achieved by means of a clutch system. Acceleration transducer with amplifier and ink writting oscillograph was used for recording the vibrations. Frequency and damping was evaluated from the acceleration records. Observed values for some equipment are given. For some equipment, it has been possible to obtain the values with and without pipe connections. The frequency of L.P. Heater in longitudinal and transverse directions without pipe connection were 17.86 and 10.04 Hz but with pipe connections the values increased to 26.74 and 17.85 Hz. Similarly there has been increase in the damping values too. Thus both the frequency and damping increases substantially with the addition of pipe connections. Moreover, their values are quite different in the two principal directions, pointing out to the importance of in situ measurements on prototype equipment

  18. Concept of diagnostic monitoring of condition of selected equipment for V-1 nuclear power plant

    International Nuclear Information System (INIS)

    Jaros, I.

    1981-01-01

    The vibroacoustic method based on picking up and processing vibrations, shocks and structural noise from the outer surface of equipment was chosen for testing the mechanical conditions of the reactor and of the main circulating pumps. The location of vibration pickups on the primary circuit components, their specifications, signal processing and evaluation are described. (M.D.)

  19. Approach to the assessment of the performance of nondestructive test methods in the manufacture of nuclear power station equipment

    International Nuclear Information System (INIS)

    Michaut, J.P.

    1996-01-01

    The safety of a nuclear power station lies largely in the possibility of ensuring, at the time of in service inspections on major equipment, that the extent of faults which may appear or develop is not greater than that of faults detrimental to behavior in service. This assurance is based on performance demonstration of the nondestructive test methods used for inspecting the equipment in service. This is the subject of numerous studies in various countries. To ensure that manufacturing faults likely to downgrade the safety of the equipment are not discovered in service, it seems desirable to make sure that the performance of the nondestructive test (NDT) methods which are going to be used in manufacture will be at least as high as those used in service and that they are therefore capable of guaranteeing detection of faults clearly less important than really harmful faults. The performance of NDT methods and their consistency with those which can be used in service is evaluated before the start of manufacture on a mock-up representative of the equipment itself. Information is given on research in progress on the bimetal welding of a pressurizer spray nozzle

  20. Seismic qualification of equipment in operating nuclear power plants. Unresolved safety issue A-46, draft report for comment

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1985-08-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants should be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46 by the Nuclear Regulatory Commission staff and its contractors, Idaho National Engineering Laboratory, Southwest Research Institute, Brookhaven National Laboratory, and Lawrence Livermore National Laboratory. In addition, the collection and review of seismic experience data by the Seismic Qualification Utility Group and the review and recommendations of a group of seismic consultants, the Senior Seismic Review Advisory Panel, are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experience data base

  1. Analysis of Technical State of Thermal and Mechanical Equipment of Thermal Power Stations in the Republic of Belarus under Conditions of Investment Deficit

    Directory of Open Access Journals (Sweden)

    S. N. Shichko

    2004-01-01

    Full Text Available The paper contains an analysis of the equipment state at a number of thermal power stations. This analysis is made on the basis of indifferent curves. Relationship of two factors is taken as a criterion for estimation of the equipment state. These factors are faultiness (parameter of failure fi"equency and operating time from the moment when the equipment was put into operation. It is noted that operation of the equipment in excess of specified life without replacement of so-called «weab> elements and estimation of metal state will lead to conditions of high risk in opieration of such equipment.

  2. Single-Stage Low-Power Quadrature RF Receiver Front-End: The LMV Cell

    DEFF Research Database (Denmark)

    Liscidini, Antonio; Mazzanti, Andrea; Tonietto, Riccardo

    2006-01-01

    a compact and low-power solution compatible with low-voltage technologies. A 0.13um CMOS prototype tailored to the GPS application is presented. The experimental results exhibit a noise figure of 4.8 dB, a gain of 36 dB, an IIP3 of -19 dBm with a total power consumption of only 5.4 mW from a voltage supply...

  3. Potentialities of fluorography in radiographic testing of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Gromov, Yu.V.; Kapustin, V.I.

    1984-01-01

    Results of fluorography of steel 5-250 mm thick with the application of different radiation sources in accordance with existing test requirements and standards for NPP equipment under industrial conditions, are presented. Sensitivity curves of fluorographic and radiographic testing methods using the RUP-150/300-10 X-ray device, LUEh-15-15000 D linear accelerator flaw detectors with 192 Yr, 60 Co, 137 Cs sources, are given. The radiation energy range is 24O keV-8 MeV. It is shown that fluorographic method meets the requirements of sensitivity and is recommended to test welded joints 5-220 mm thick in NPP equipment under laboratory and industrial conditions

  4. The problem of ensuring the seismic stability of atomic electric power plant equipment and ways of solving it

    International Nuclear Information System (INIS)

    Kaznovskii; Filippov, G.A.

    1983-01-01

    By seismic stability the authors mean the ability of the equipment and buildings to retain certain properties when subjected to seismic loads: leakproofness, strength, the absence of any residual changes of shape, which interfere with normal operation, ability to be repaired, nuclear and radiation safety. The latter requirement is the main thing which differentiates atomic electric power plants from other constructions, including other power-generation plants. Whereas, for example, an accident in the event of an earthquake in a thermal electric power plant can be regarded as a local accident, and the measures to ensure seismic stability are determined by economic factors and safety requirements for the operating staff, to ensure the seismic stability of an AES it is essential to take account in the first instance of the possibility of dangerous radiation effects both in the AES and in the vast area around it

  5. The Bosnian Train and Equip Program: A Lesson in Interagency Integration of Hard and Soft Power

    Science.gov (United States)

    2014-03-01

    even before Bos- nia officially declared independence. Most of the weaponry and commanders from the former Yugoslav People’s Army in Bosnia, which was...ability, and disposition.” 505 It covers characteristics that research indicates affect team performance including attitudinal, de- mographic, and...The Train and Equip Program reduced foreign influence in the Federation, which helped remove impediments to reconciliation and integration in Bos- nia

  6. Study on the Management for the Nuclear Power Plant Maintenance and Equipment Reliability

    International Nuclear Information System (INIS)

    Yoon, Kyeongseop; Lee, Sangheon; Kim, Myungjin; Lee, Unjang

    2015-01-01

    In our country, many studies on the regulatory policy of the plant maintenance have ever been performed since 1998, but the relevant regulatory requirements were not established yet. These background mentioned above request us to study on the regulation policy and maintenance plan to improve the safety, reliability and efficiency of NPP. To solve these problems, in this study, we deduct the management methodology for the improvement of NPP maintenance and equipment reliability that is essential to secure the safety and efficiency of the commercial NPP. For analysis the maintenance and equipment reliability management methodology in overseas NPP. We studied maintenance and equipment reliability of USA, Canada and Europe(France, England, German). We also studied status and application condition of Korean NPP maintenance management technical development. We deducted an effective maintenance methodology that is needed to Korean NPP, as a result of comparison on the technical trend of the maintenance management between overseas and Korean, such like following. - Regulation form ·Specific provision of regulation requirement and application of form that is clarifying application standard - Maintenance management methodology, Maintenance management program. This results of study could be applied for regulation policy, law and guideline establishment of NPP maintenance, operation, supervision and a system establishment for maintenance management, education data about maintenance for NPP employees

  7. Power supplies and equipment for military field research: lessons from the British Service Dhaulagiri Research Expedition 2016.

    Science.gov (United States)

    Howard, Matt; Bakker-Dyos, J; Gallagher, L; O'Hara, J P; Woods, D; Mellor, A

    2018-02-01

    The British Service Dhaulagiri Research Expedition (BSDMRE) took place from 27 March to 31 May 2016. The expedition involved 129 personnel, with voluntary participation in nine different study protocols. Studies were conducted in three research camps established at 3600, 4600 and 5140 m and involved taking and storing blood samples, cardiac echocardiography and investigations involving a balance plate. Research in this remote environment requires careful planning in order to provide a robust and resilient power plan. In this paper we aim to report the rationale for the choices we made in terms of power supply, the equipment used and potential military applicability. This is a descriptive account from the expedition members involved in planning and conducting the medical research. Power calculations were used to determine estimates of requirement prior to the expedition. The primary sources used to generate power were internal combustion engine (via petrol fuelled electric generators) and solar panels. Having been generated, power was stored using lithium-ion batteries. Special consideration was given to the storage of samples taken in the field, for which electric freezers and dry shippers were used. All equipment used functioned well during the expedition, with the challenges of altitude, temperature and transport all overcome due to extensive prior planning. Power was successfully generated, stored and delivered during the BSDMRE, allowing extensive medical research to be undertaken. The challenges faced and overcome are directly applicable to delivering military medical care in austere environments, and lessons learnt can help with the planning and delivery of future operations, training exercises or expeditions. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  8. Optimization of the operating conditions of gas-turbine power stations considering the effect of equipment deterioration

    Science.gov (United States)

    Aminov, R. Z.; Kozhevnikov, A. I.

    2017-10-01

    In recent years in most power systems all over the world, a trend towards the growing nonuniformity of energy consumption and generation schedules has been observed. The increase in the portion of renewable energy sources is one of the important challenges for many countries. The ill-predictable character of such energy sources necessitates a search for practical solutions. Presently, the most efficient method for compensating for nonuniform generation of the electric power by the renewable energy sources—predominantly by the wind and solar energy—is generation of power at conventional fossil-fuel-fired power stations. In Russia, this problem is caused by the increasing portion in the generating capacity structure of the nuclear power stations, which are most efficient when operating under basic conditions. Introduction of hydropower and pumped storage hydroelectric power plants and other energy-storage technologies does not cover the demand for load-following power capacities. Owing to a simple design, low construction costs, and a sufficiently high economic efficiency, gas turbine plants (GTPs) prove to be the most suitable for covering the nonuniform electric-demand schedules. However, when the gas turbines are operated under varying duty conditions, the lifetime of the primary thermostressed components is considerably reduced and, consequently, the repair costs increase. A method is proposed for determination of the total operating costs considering the deterioration of the gas turbine equipment under varying duty and start-stop conditions. A methodology for optimization of the loading modes for the gas turbine equipment is developed. The consideration of the lifetime component allows varying the optimal operating conditions and, in some cases, rejecting short-time stops of the gas turbine plants. The calculations performed in a wide range of varying fuel prices and capital investments per gas turbine equipment unit show that the economic effectiveness can

  9. Lightweight MAC-Spoof Detection Exploiting Received Signal Power and Median Filtering

    DEFF Research Database (Denmark)

    Papini, Davide

    2011-01-01

    this kind of attack based on signal power monitoring. The main contribution of our work is the introduction of a median l- ter that enables the detection of the attack by looking at the variance of the signal power. We take into account two types of references for the samples, time and number of frames......IEEE 802.11 networks are subject to MAC-spoof attacks. An attacker can easily steal the identity of a legitimate station, even Access Points, thus enabling him to take full control over network basic mech- anisms or even access restricted resources. In this paper we propose a method to detect...

  10. Comparative analysis of collective doses received since 1976 at the Ardennes nuclear power plant

    International Nuclear Information System (INIS)

    Aye, Louis

    1980-01-01

    The analysis of the collective doses at the Centrale nucleaire des Ardennes povides valuable data about the origin of exposures in P.W.R. reactors and their evolution regarding the increase of activity of the circuits after more than 10 years of operation. The investigations led for most of the works since 1976 reveals that, in some cases, the use of sophisticated implements combined with modifications of equipments and procedures may bring appreciable savings on doses during normal operation as well as maintenance and refuelings shut-down. However, the study gives the 'reasonably achievable' limits than can be aimed in a plant on operation, the doses resulting mainly from problems that should be taken into account at design [fr

  11. Communication of 29 April 1996 received from the Permanent Mission of the Russian Federation to the International Atomic Energy Agency regarding guidelines for the export of nuclear material, equipment and technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-07

    The document contains the text of a note verbale dated 29 April 1996 received by the Director General of IAEA from the Permanent Mission of the Russian Federation which provides information on the export policies and practices of the Government of the Russian Federation with respect to transfer of nuclear-related dual-use equipment, material and related technology.

  12. Communication of 29 April 1996 received from the Permanent Mission of the Russian Federation to the International Atomic Energy Agency regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1996-01-01

    The document contains the text of a note verbale dated 29 April 1996 received by the Director General of IAEA from the Permanent Mission of the Russian Federation which provides information on the export policies and practices of the Government of the Russian Federation with respect to transfer of nuclear-related dual-use equipment, material and related technology

  13. Comparison between Japan and the United States in the frequency of events in equipment and components at nuclear power plants

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2007-01-01

    The Institute of Nuclear Safety System, Incorporated (INSS) conducted trend analyses until 2005 to compare the frequency of events in certain electrical components and instrumentation components at nuclear power plants between Japan and the United States. The results revealed that events have occurred approximately an order of magnitude less often in Japan than in the United States. This paper compared Japan and the United States in more detail in terms of how often events - events reported under the reporting standards of the Nuclear Information Archive (NUCIA) or the Institute of Nuclear Power Operations (INPO) - occurred in electrical components, instrumentation components and mechanical components at nuclear power plants. The results were as follows: (1) In regard to electrical components and instrumentation components, events have occurred one-eighth less frequently in Japan than in the United States, suggesting that the previous results were correct. (2) Events have occurred more often in mechanical components than electrical components and instrumentation components in both Japan and the United States, and there was a smaller difference in the frequency of events in mechanical components between the two countries. (3) Regarding mechanical components, it was found that events in the pipes for critical systems and equipment, such as reactor coolant systems, emergency core cooling systems, instrument and control systems, ventilating and air-conditioning systems, and turbine equipment, have occurred more often in Japan than in the United States. (4) The above observations suggest that there is little scope for reducing the frequency of events in electrical components and instrumentation components, but that mechanical components such as pipes for main systems like emergency core cooling systems and turbine equipment in the case of PWRs, could be improved by re-examining inspection methods and intervals. (author)

  14. 30 CFR 75.811 - High-voltage underground equipment; grounding.

    Science.gov (United States)

    2010-07-01

    ...-voltage equipment supplying power to such equipment receiving power from resistance grounded systems shall... 30 Mineral Resources 1 2010-07-01 2010-07-01 false High-voltage underground equipment; grounding... COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Underground High-Voltage...

  15. Chemical decontamination of non-dismounted equipment of nuclear power stations

    International Nuclear Information System (INIS)

    Oertel, K.; Dietrich, P.; Hildebrandt, N.

    1979-01-01

    Reasons for performing system chemical decontaminations are considered, some cases of practical application to water cooled power reactors are discussed, radical and soft decontamination techniques are compared with each other, and evaluation criteria for decontaminations are studied. (author)

  16. THE POWER FACTOR IMPROVING OF THE MOTORS IN ENTERPRISES WITH REPAIR OF RAILWAY EQUIPMENT

    Directory of Open Access Journals (Sweden)

    O. L. Marenych

    2008-03-01

    Full Text Available In this article the following problem has been considered: ways of power factor increase for electric drives installed at the railway machinery repair enterprises with taking into account the specific conditions of technological processes.

  17. New technology for optimized I and C maintenance and management of ageing of critical equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2000-01-01

    Advanced sensors and new testing and maintenance technologies have become available over the last ten years for nuclear power plants (NPPs) to replace outdated, obsolete, and troublesome instruments, provide for management of ageing of critical plant equipment, optimize maintenance activities, reduce maintenance costs and personnel radiation exposure, and at the same time, improve plant safety and availability. These new developments are reviewed in this TECDOC. The material covered here has been summarized from NUREG/CR-5501, a 1998 report written by H.M. Hashemian and his co-authors for the US Nuclear Regulatory Commission. (author)

  18. Learning and technological capability building in emerging economies: The case of the biomass power equipment industry in Malaysia

    DEFF Research Database (Denmark)

    Hansen, Ulrich Elmer; Ockwell, David

    2014-01-01

    There is increasing recognition that the transfer of foreign technology to developing countries should be considered in light of broader processes of learning, technological capability, formation and industrial development. Previous studies that have looked at this in the context of cleantech...... capabilities. This is explored via an examination of eight firms in the biomass power equipment industry in Malaysia during the period 1970–2011. The paper finds that firms relying on a combination of learning from foreign technology partners and internal learning by planned experimentation make most progress...

  19. The methodology of root cause analysis for equipment failure and its application at Guangdong nuclear power stations

    International Nuclear Information System (INIS)

    Gao Ligang; Lu Qunxian

    2004-01-01

    The methodology of Equipment Failure Root Cause Analysis (RCA) is described, as a systematic analysis methodology, it includes 9 steps. Its process is explained by some real examples, and the 6 precautions applying RCA is pointed out. The paper also summarizes the experience of RCA application at Daya Bay Nuclear Power Station, and the 7 key factors for RCA success is emphasized, that mainly concerns organization, objective, analyst, analysis technique, external technical supporting system, corrective actions developing and monitoring system for corrective actions. (authors)

  20. Solar central receiver hybrid power system, Phase I. Volume 2. Conceptual design. Final technical report, October 1978-August 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-09-01

    The objectives of this study were to develop a hybrid power system design that (1) produces minimum cost electric power, (2) minimizes the capital investment and operating cost, (3) permits capacity displacement, (4) and achieves utility acceptance for market penetration. We have met the first three of these objectives and therefore believe that the fourth, utility acceptance, will become a reality. These objectives have been met by utilizing the Martin Marietta concept that combines the alternate central receiver power system design and a high-temperature salt primary heat transfer fluid and thermal storage media system with a fossil-fired nonsolar energy source. Task 1 reviewed the requirements definition document and comments and recommendations were provided to DOE/San Francisco. Task 2 consisted of a market analysis to evaluate the potential market of solar hybrid power plants. Twenty-two utilities were selected within nine regions of the country. Both written and verbal correspondence was used to assess solar hybrid power plants with respect to the utilities' future requirements and plans. The parametric analysis of Task 3 evaluated a wide range of subsystem configurations and sizes. These analyses included subsystems from the solar standalone alternate central receiver power system using high-temperature molten salt and from fossil fuel nonsolar subsystems. Task 4, selection of the preferred commerical system configuration, utilized the parametric analyses developed in Task 3 to select system and subsystem configurations for the commercial plant design. Task 5 developed a conceptual design of the selected commercial plant configuration and assessed the related cost and performance. Task 6 assessed the economics and performance of the selected configuration as well as future potential improvements or limitations of the hybrid power plants.

  1. Instantaneous response spectrum in seismic testing of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Morrone, A.

    1977-01-01

    Seismic response spectra, as used in seismic analyses, give the maximum responses of single degree of freedom oscillators without consideration of the different time in the seismic time history at which each of the maximum responses occur. For response spectrum seismic analysis, the use of time-independent maximum responses is appropriate. The time dependece is considered in a statistical manner, for multi-degree of freedom systems, usually by combining the modal effects by the square root of the sum of the squares. For seismic testing of electrical equipment. IEEE Std. 344-1975 makes use of the response spectrum to define the input motion of the shake table. One of the basic requirements is that the test response spectrum (TRS) that is, the response spectrum produced by the shake table motion, should envelop the required response spectrum (RRS) calculated from the building analysis at the support point of the equipment being tested. This paper presents the concept of instantaneous response spectrum (IRS) as the response of single degree of freedom oscillators at a particular time. It demonstrates that a shake table random motion whose standard TRS envelops the RRS does not necessarily satisfy the enveloping requirement instantaneously. (Auth.)

  2. FUNDAMENTALS OF RADIO CONTROL OF FAULTY EQUIPMENT AND ICE REGIMES ARC ABUSES OF POWER COLLECTION

    Directory of Open Access Journals (Sweden)

    Yu. I. Zharkov

    2009-03-01

    Full Text Available The principles of construction and the structure of radio system for detecting damaged current collectors and glaze-ice regimes on arc breaking of current collection as well as the peculiarities of received radio signals and the basics of their identification are presented.

  3. A high-efficiency, low-noise power solution for a dual-channel GNSS RF receiver

    International Nuclear Information System (INIS)

    Shi Jian; Mo Taishan; Gan Yebing; Ma Chengyan; Ye Tianchun; Le Jianlian

    2012-01-01

    A high-efficiency low-noise power solution for a dual-channel GNSS RF receiver is presented. The power solution involves a DC—DC buck converter and a followed low-dropout regulator (LDO). The pulse-width-modulation (PWM) control method is adopted for better noise performance. An improved low-power high-frequency PWM control circuit is proposed, which halves the average quiescent current of the buck converter to 80 μA by periodically shutting down the OTA. The size of the output stage has also been optimized to achieve high efficiency under a light load condition. In addition, a novel soft-start circuit based on a current limiter has been implemented to avoid inrush current. Fabricated with commercial 180-nm CMOS technology, the DC—DC converter achieves a peak efficiency of 93.1% under a 2 MHz working frequency. The whole receiver consumes only 20.2 mA from a 3.3 V power supply and has a noise figure of 2.5 dB. (semiconductor integrated circuits)

  4. Preliminary design of the Carrisa Plains solar central receiver power plant. Volume III, Book 1. Design description

    Energy Technology Data Exchange (ETDEWEB)

    1983-12-31

    The design of the 30 MWe central receiver solar power plant to be located at Carrisa Plains, San Luis Obispo County, California, is summarized. The plant uses a vertical flat-panel (billboard solar receiver located at the top of a tower to collect solar energy redirected by approximately 1900 heliostats located to the north of the tower. The solar energy is used to heat liquid sodium pumped from ground level from 610 to 1050/sup 0/F. The power conversion system is a non-reheat system, cost-effective at this size level, and designed for high-efficiency performance in an application requiring daily startup. Successful completion of this project will lead to power generation starting in 1986. This report discusses in detail the design of the collector system, heat transport system, thermal storage subsystem, heat transport loop, steam generation subsystem, electrical, instrumentation, and control systems, power conversion system, master control system, and balance of plant. The performance, facility cost estimate and economic analysis, and development plan are also discussed.

  5. Thermal Power Systems, Point-Focusing Distributed Receiver Technology Project. Annual technical report, Fiscal Year 1978. Volume II. Detailed report

    Energy Technology Data Exchange (ETDEWEB)

    1979-03-15

    Thermal or electrical power from the sun's radiated energy through Point-Focusing Distributed Receiver technology is the goal of this Project. The energy thus produced must be economically competitive with other sources. This Project supports the industrial development of technology and hardware for extracting energy from solar power to achieve the stated goal. Present studies are working to concentrate the solar energy through mirrors or lenses, to a working fluid or gas, and through a power converter change it to an energy source useful to man. Rankine-cycle and Brayton-cycle engines are currently being developed as the most promising energy converters for our near future needs. Accomplishments on point-focusing technology in FY 1978 are detailed.

  6. The injection equipment of future high-speed DI diesel engines with respect to power and pollution requirements

    Energy Technology Data Exchange (ETDEWEB)

    Dolenc, A. (Monobloc Dieselmotoren GmbH, Vienna (AT))

    1990-01-01

    The development of high specific output DI diesel engines started at the low-speed end some 50 years ago primarily for marine and traction applications. Movement towards the high-speed end has been slow but steady with the majority of truck engines being very conservatively rated. There has been recent major effort on the automotive car and light commercial vehicle diesel application leading to lightweight DI diesel engines with an engine speed of 4000-5000 r/min and a rated power of 50 kW/litre displacement. These are expected to be on the market in a short period of time. The key point of this development has been the injection equipment including combustion control. In this area the use of modulated injection has the possibility of solving power and pollution requirements. (author).

  7. New Approach to Enhance an Effect of Condition Monitoring of Mid/Small Size Rotating Equipment in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Shin You Soo; Chang, Hee Seung [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    Condition monitoring for small and medium-size rotating equipment is mainly done by a patrol inspection and a vibration measurement. These methods are useful to recognize a significant change in a sound, temperature and vibration amplitude on the bearing housing. However, such a significant change shows an abnormal condition just before failure so that there is not much time to take a right action to recover. In other words, there is a severe damage when someone detects the phenomenon. These methods are good way to detect a flaw but too late to fix. It can't detect early recognition of defect To enhance the effect of condition monitoring and recognize a defect earlier, an integrated measurement including high band frequency analysis is required. It will be implemented at one of nuclear power plants in Korea as a pilot to verify an effect and applicability at nuclear power plants.

  8. Performance simulation of the JPL solar-powered distiller. Part 1: Quasi-steady-state conditions. [for cooling microwave equipment

    Science.gov (United States)

    Yung, C. S.; Lansing, F. L.

    1983-01-01

    A 37.85 cu m (10,000 gallons) per year (nominal) passive solar powered water distillation system was installed and is operational in the Venus Deep Space Station. The system replaced an old, electrically powered water distiller. The distilled water produced with its high electrical resistivity is used to cool the sensitive microwave equipment. A detailed thermal model was developed to simulate the performance of the distiller and study its sensitivity under varying environment and load conditions. The quasi-steady state portion of the model is presented together with the formulas for heat and mass transfer coefficients used. Initial results indicated that a daily water evaporation efficiency of 30% can be achieved. A comparison made between a full day performance simulation and the actual field measurements gave good agreement between theory and experiment, which verified the model.

  9. Use of Small-Scale Wind Energy to Power Cellular Communication Equipment

    Directory of Open Access Journals (Sweden)

    B. Plourde

    2011-12-01

    Full Text Available The recent increase in cellular communication coverage and usage has been remarkable. The increase has occurred throughout the globe, in both developed and developing regions. In fact, in some regions of the world, land-line communications are being avoided altogether as countries move into primarily mobile communication technologies. In order for cellular communication to function adequately, communication towers must be built with sufficient density to provide coverage. These towers have electrical requirements which are often not met with grid-based power. This study presents a novel design of a wind turbine which is designed to be positioned atop existing communication towers in order to provide local power for the tower. These turbines have vertical axes of rotation and other features which suit them for this highly specialized application. The study carried out here shows that these turbines are able to provide the required electrical power to fully satisfy the communication-tower electronics.

  10. The Transfer efficiency analysis and modeling technology of new non - contact power transmission equipment

    Directory of Open Access Journals (Sweden)

    Cao Shi

    2017-01-01

    Full Text Available Due to the shortcomings of current power transmission which is used in ultrasound - assisted machining and the different transfer efficiency caused by the related parameters of the electromagnetic converter, this paper proposes an analysis model of the new non-contact power transmission device with more stable output and higher transmission efficiency. Then By utilizing Maxwell finite element analysis software, this paper studies the law of the transfer efficiency of the new non-contact transformer and compares new type with traditional type with the method of setting the boundary conditions of non-contact power supply device. At last, combining with the practical application, the relevant requirements which have a certain reference value in the application are put forward in the actual processing.

  11. Plant equipment integrity monitoring and diagnosing method and device therefor, plant equipment maintenance and inspection time determining method and device therefor, as well as nuclear power plant

    International Nuclear Information System (INIS)

    Kato, Takahiko; Ando, Masashi; Osumi, Katsumi; Horiuchi, Tetsuo; Asakura, Yamato; Akamine, Kazuhiko.

    1995-01-01

    The present invention can accurately forecast a time for occurrence of troubles of plant equipments in contact with recycling water, to conduct its maintenance and inspection before occurrence of the troubles. Namely, change of water quality in plant equipments caused by corrosion of recycling water occurred in constitutional parts of the plant equipments is measured. The time upon occurrence of the troubles of the plant equipments to corrosion of the recycling water is forecast based on the measured value. A time till the occurrence of the change of water quality after starting the use of the plant equipments is calculated based on the measured value. The calculated time is compared with a correlation between the time of occurrence of the troubles after starting the use of the plant equipments and the time of occurrence of change of the water quality, to forecast the time of occurrence of the troubles. Preferably, electroconductivity and pH of recycling water in the inside or at the exit of the plant equipments are measured as an object for the measurement of change of water quality. (I.S.)

  12. Thermal design of a fully equipped solar-powered desert home

    KAUST Repository

    Serag-Eldin, M.A.

    2010-03-01

    The paper presents a conceptual design and thermodynamic analysis of a solar-powered desert home. The home is airconditioned and provides all modern comforts and facilities. Electrical power, which drives the entire energy system, is generated by roof mounted photovoltaic modules. A detailed dynamic heat transfer analysis is conducted for the building envelope, coupled with a solar radiation model. A dynamic heat balance for a typical Middle-Eastern desert site, reveals that indeed such a design is feasible with present day technology; and should be even more attractive with future advances in technology.

  13. Reliability analysis of the automatic control and power supply of reactor equipment

    International Nuclear Information System (INIS)

    Monori, Pal; Nagy, J.A.; Meszaros, Zoltan; Konkoly, Laszlo; Szabo, Antal; Nagy, Laszlo

    1988-01-01

    Based on reliability analysis the shortcomings of nuclear facilities are discovered. Fault tree types constructed for the technology of automatic control and for power supply serve as input data of the ORCHARD 2 computer code. In order to charaterize the reliability of the system, availability, failure rates and time intervals between failures are calculated. The results of the reliability analysis of the feedwater system of the Paks Nuclear Power Plant showed that the system consisted of elements of similar reliabilities. (V.N.) 8 figs.; 3 tabs

  14. Fire protection equipment in the area of control of the Neckar Community Nuclear Power Station

    International Nuclear Information System (INIS)

    Bernhardt, S.; Grauf, E.

    1976-01-01

    In the Neckar Community Nuclear Power Station - an 805 MW pressurised water reactor shortly to reach the stage of nuclear operation - fire protection measures have been realised to an extent hitherto uncommon in German nuclear power plants. The reason is to be sought from the authorities who have become more sensitive because of a fire in a reactor vessel during the construction stage and the fire at Browns Ferry and have consequently become extremely expert. Apart from the fire regulations hitherto normal further subregulations have been created in order to be able to make better provision of extinguishing devices against fire hazards. (orig.) [de

  15. Study on Communication Methods for Electric Power High-voltage Equipment Monitoring System

    Directory of Open Access Journals (Sweden)

    Jia Yu Chen

    2018-02-01

    Full Text Available Real-time monitoring of high-voltage equipment in substations is beneficial for early detection of faults. The use of wireless sensor networks to build monitoring system is an effective way, but the data collection is a difficult task. The author introduces a real-time monitoring system based on ZIGBEE and mobile communication technology. The system includes multiple monitoring points and terminal platforms. Each monitoring point consists of a number of sensor nodes to form a ZIGBEE network, detecting relevant parameters, coordinator node data collected one by one, known as linear transmission, and finally to the monitoring platform through the mobile communication network. This paper presents a fusion algorithm for monitoring cell data acquisition to reduce the amount of data uploaded to the base station. In addition, multi-hop routing algorithm based on opportunistic routing is proposed to balance network energy and improve network transmission rate and efficiency.

  16. Single-purpose welding machines used in the manufacture of power equipment

    International Nuclear Information System (INIS)

    Bartak, J.

    1988-01-01

    A dedicated welding machine based on submerged arc welding with a wire electrode was developed for welding pipe sockets, spacers and other rotary parts to pressure vessel bodies. Two modifications of this apparatus were devised: one is designed for welding low-alloy carbon steels, where preheating is requisite, the other, for welding austenitic materials, requiring vigorous cooling. The single-purpose ADFS-1 device is designed for surfacing rings 200 to 1200 mm in diameter; it consists of a pillar with a drive, a rotary console, a collector, a horizontal support, a console with a vertical motor support, and a welding head with a feed equipment. Submerged arc welding using a 20x0.5 mm strip electrode is applied. Another dedicated welding machine employing submerged arc welding with a strip electrode was developed for the continuous welding of inner surfaces of pressure vessels in the sites of holes for flares. (Z.M.). 3 figs., 3 refs

  17. Dose received during work in the active zone of the BIBLIS power plant, instalment A, 1977

    International Nuclear Information System (INIS)

    Kallmeyer, D.; Ambros, R.; Schroeder, H.J.; Kausch, S.

    1978-01-01

    In the Biblis station, instalment A, of the Rheinisch-Wesfaelisches-Elektrizitaetswerk, a study was conducted in 1977 to determine the doses received as a function of work carried out. The aim was to establish in a general study the dose which appears in each case during work on systems (or components of systems) in the active zone. An attempt was made as far as possible to relate the doses to specific occupations. This correlation is governed in two ways by conditions inherent in the organisation of the Biblis station a) maintenance and repair work are carried out under work contracts; the dose can be related to this work by the order number of the contract in question. b) Some activities, apart from maintenance and repair may be carried out without a contract. The dose which then appears is related to the type of activity concerned

  18. Dependency Traits, Relationship Power, and Health Risks in Women Receiving Sexually-Transmitted Infection Clinic Services.

    Science.gov (United States)

    Benotsch, Eric G; Sawyer, Ashlee N; Martin, Aaron M; Allen, Elizabeth S; Nettles, Christopher D; Richardson, Doug; Rietmeijer, Cornelis A

    2017-01-01

    In prior research, having traits consistent with a personality disorder has been shown to be related to substance use and high-risk sexual activity; however, few studies have examined relationships between dependency traits and health-jeopardizing behaviors. Individuals with traits consistent with dependent personality disorder may be more likely to be in a primary relationship characterized by unhealthy conditions, including physical abuse from a partner, low assertiveness in sexual situations, and partner infidelity. In addition, dependency traits may be associated with unhealthy coping (e.g., through substance use). To examine associations between dependent personality traits and these types of health-related behaviors, 198 women seeking sexually transmitted infection clinic services completed a computer-assisted assessment of dependent personality traits, substance use, unhealthy conditions in primary relationships, perceived sexual and relationship power, and sexual risk related to condom use. Dependency trait scores were correlated with the use of cocaine, heroin, and methamphetamine. Participants high in dependency traits reported low perceived power within their relationships and less say in sexual behaviors, including condom use. In a series of multivariate analyses, dependency traits significantly predicted having been hit by a partner, staying with a partner after he cheated, having sex because of threats, and fear of asking a partner to use a condom. Dependency traits were also associated with lower past condom use and lower future condom use intentions. Results suggest that dependent personality traits may place women at higher risk for physical abuse and harmful health behaviors.

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

    International Nuclear Information System (INIS)

    Hampe, E.; Schwarz, J.

    1984-01-01

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

  20. IEEE Std 1205-1993: IEEE guide for assessing, monitoring, and mitigating aging effects on Class 1E equipment used in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The guidelines are provided for assessing, monitoring, and mitigating degradation of Class 1E equipment used in nuclear power generating stations due to aging. The methods described can be used to identify the performance capability of Class 1E equipment beyond its qualified life. A discussion of stressors and aging mechanisms is included. If aging considerations have been satisfactorily addressed through other means (e.g., equipment qualification), then use of this guide may not be warranted. For some equipment, only partial application of this guide may be warranted

  1. Thermal performance prediction and sensitivity analysis for future deployment of molten salt cavity receiver solar power plants in Algeria

    International Nuclear Information System (INIS)

    Boudaoud, S.; Khellaf, A.; Mohammedi, K.; Behar, O.

    2015-01-01

    Highlights: • Performance of power plant with molten salt cavity receiver is assessed. • A method has been used to optimize the plant solar multiple, capacity factor and LEC. • Comparison of the simulated results to those of PS20 has shown good agreement. • Higher fossil fuel fraction reduces the LEC and increases the capacity factor. • Highland and Sahara regions are suitable for CRS plants deployment. - Abstract: Of all Concentrating Solar Power (CSP) technologies available today, the molten salt solar power plant appears to be the most important option for providing a major share of the clean and renewable electricity needed in the future. In the present paper, a technical and economic analysis for the implementation of a probable molten salt cavity receiver thermal power plant in Algeria has been carried out. In order to do so, we have investigated the effect of solar field size, storage capacity factor, solar radiation intensity, hybridization and power plant capacity on the thermal efficiency and electricity cost of the selected plant. The system advisor model has been used to perform the technical performance and the economic assessment for different locations (coastal, highland and Sahara regions) in Algeria. Taking into account various factors, a method has been applied to optimize the solar multiple and the capacity factor of the plant, to get a trade-off between the incremental investment costs of the heliostat field and the thermal energy storage. The analysis has shown that the use of higher fossil fuel fraction significantly reduces the levelized electricity cost (LEC) and sensibly increases the capacity factor (CF). The present study indicates that hybrid molten salt solar tower power technology is very promising. The CF and the LEC have been found to be respectively of the order of 71% and 0.35 $/kW e . For solar-only power plants, these parameters are respectively about 27% and 0.63 $/kW e . Therefore, hybrid central receiver systems are

  2. Survival of juvenile fishes receiving thermal and mechanical stresses in a simulated power plant condenser

    International Nuclear Information System (INIS)

    Kedl, R.J.; Coutant, C.C.

    Experiments were conducted in a water-recirculating loop to determine the effects of fluid-induced stresses (e.g., turbulence, pressure, and vacuum) on six species of larval fish and one species each of frog tadpoles and zooplankton. These stresses simulate the insults developed in the condenser portion, but not including the pump, of a steam power plant. Some experiments were conducted with thermal stresses superimposed on fluid-induced stresses. Fluid-induced stresses of the magnitude developed in these experiments were generally not fatal to the larval fish within the precision of the experiments, although some sublethal effects were noted. When thermal stress was superimposed on the fluid-induced stresses, the mortalities were equivalent to those resulting from thermal stress alone. Fluid-induced stresses of low magnitude were not fatal to Daphnia magna, but fluid-induced stresses of higher magnitude were responsible for significant mortalities. (U.S.)

  3. Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde; Implementacion del proyecto de confiabilidad de equipo en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rios O, J. E.; Martinez L, A. G. [CFE, Central Laguna Verde, Subgerencia General de Operacion, Veracruz (Mexico)]. e-mail: jrios@cfe.gob.mx

    2008-07-01

    A equipment is reliable if it fulfills the function for which was designed and when it is required. To implement a project of reliability in a nuclear power plant this associate to a process of continuous analysis of the operation, of the conditions and faults of the equipment. The analysis of the operation of a system, of the equipment of the same faults and the parts that integrate to equipment take to identify the potential causes of faults. The predictive analysis on components and equipment allow to rectify and to establish guides to optimize the maintenance and to guarantee the reliability and function of the same ones. The reliability in the equipment is without place to doubts a wide project that embraces from the more small component of the equipment going by the proof of the parts of reserve, the operation conditions until the operative techniques of analysis. Without place of doubt for a nuclear power plant the taking of decisions based on the reliability of their systems and equipment will be the appropriate for to assure the operation and reliability of the same one. In this work would appear the project of reliability its processes, criteria, indicators action of improvement and the interaction of the different disciplines from the Nuclear Power Plant of Laguna Verde like a fundamental point for it put in operation. (Author)

  4. IEEE No. 323, IEEE trial-use standard: General guide for qualifying Class I electric equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This document describes the basic requirements for the qualification of Class I electric equipment. This is equipment which is essential to the safe shutdown and isolation of the reactor or whose failure or damage could result in significant release of radioactive material. The purpose of this document is to provide guidance for demonstrating the qualifications of electrical equipment as required in the IEEE Std 279 -- Criteria for Nuclear Power Generating Station Protection Systems, and IEEE Std 308 -- Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations. The qualification methods described may be used in conjunction with the Guides for qualifying specific types of equipment, (see Foreword), for updating qualification following modifications or for qualifying equipment for which no applicable Guide exists

  5. Painting for nuclear power stations and machinery and equipments according to quality assurance program of ANSI

    International Nuclear Information System (INIS)

    Fukuda, Shinzo; Tsuchiya, Yukikazu.

    1979-01-01

    Recently, painting for nuclear power stations is carried out with the paints made domestically, and these paints are tested and judged generally according to the items of performance evaluation decided by the American National Standard Institute. In Japan, there is no standard regarding the paints for nuclear power stations. Painting is very important process, and it is appropriate to introduce quality assurance program into it. In this paper, the contents of ANSI standard concerning the paints and painting for nuclear power stations are explained, and the outline of the painting of heat exchangers carried out in accordance with the quality assurance program in the Tamano Shipyard, Mitsui Shipbuilding and Engineering Co., Ltd., is described. The test items for evaluating the general performance of the paints, the testing method for evaluating the endurance at the time of an accident, the quality assurance for the paints used for the facilities handling radiation and others are explained. Various problems arise when the quality assurance program of ANSI is applied actually to painting. It is difficult to judge the quality of paints and painting with numerical values, and much efforts were required to establish the quality assurance organization. The conditions for painting, the handling of many documents, the measures to unsatisfactory painting and so on caused much difficulties. (Kako, I.)

  6. NN-Es Fault Diagnosis Method in Nuclear Power Equipment Based on Concept Lattice

    International Nuclear Information System (INIS)

    Liu Yongkuo; Xie Chunli; Xia Hong

    2010-01-01

    In order to improve the fault diagnosis accuracy of nuclear power plant,neural network and expert systems were combined to give full play to their advantages. In this paper, the concept lattice was applied to get the object properties, extracting the core attributes, dispensable attributes and relative necessary attributes from a large number raw data of fault symptoms.Based on these attributes, neural networks with different levels of importance were designed to improve the learning speed and diagnosis accuracy, and the diagnosis results of the neural networks were verified by using rule-based reasoning expert system. To verify the accuracy of this method, some simulation experiments about the typical faults of nuclear power plant were conducted. And the simulation results show that it is feasible to diagnose nuclear power plant faults with the confederation diagnosis methods combined the neural networks based on the concept lattice theory and expert system, with the distinctive features such as the efficiency of neural network learning, less calculation and reliability of diagnosis results and so on. (authors)

  7. Study concerning the power plant control and safety equipment by integrated distributed systems

    International Nuclear Information System (INIS)

    Optea, I.; Oprea, M.; Stanescu, P.

    1995-01-01

    The paper deals with the trends existing in the field of nuclear control and safety equipment and systems, proposing a high-efficiency integrated system. In order to enhance the safety of the plant and reliability of the structure system and components, we present a concept based on the latest computer technology with an open, distributed system, connected by a local area network with high redundancy. A modern conception for the control and safety system is to integrate all the information related to the reactor protection, active engineered safeguard and auxiliary systems parameters, offering a fast flow of information between all the agencies concerned so that situations can be quickly assessed. The integrated distributed control is based on a high performance operating system for realtime applications, flexible enough for transparent networking and modular for demanding configurations. The general design considerations for nuclear reactors instrumentation reliability and testing methods for real-time functions under dynamic regime are presented. Taking into account the fast progress in information technology, we consider the replacement of the old instrumentation of Cernavoda-1 NPP by a modern integrated system as an economical and efficient solution for the next units. (Author) 20 Refs

  8. Methodology and measures for preventing unacceptable flow-accelerated corrosion thinning of pipelines and equipment of NPP power generating units

    Science.gov (United States)

    Tomarov, G. V.; Shipkov, A. A.; Lovchev, V. N.; Gutsev, D. F.

    2016-10-01

    Problems of metal flow-accelerated corrosion (FAC) in the pipelines and equipment of the condensate- feeding and wet-steam paths of NPP power-generating units (PGU) are examined. Goals, objectives, and main principles of the methodology for the implementation of an integrated program of AO Concern Rosenergoatom for the prevention of unacceptable FAC thinning and for increasing operational flow-accelerated corrosion resistance of NPP EaP are worded (further the Program). A role is determined and potentialities are shown for the use of Russian software packages in the evaluation and prediction of FAC rate upon solving practical problems for the timely detection of unacceptable FAC thinning in the elements of pipelines and equipment (EaP) of the secondary circuit of NPP PGU. Information is given concerning the structure, properties, and functions of the software systems for plant personnel support in the monitoring and planning of the inservice inspection of FAC thinning elements of pipelines and equipment of the secondary circuit of NPP PGUs, which are created and implemented at some Russian NPPs equipped with VVER-1000, VVER-440, and BN-600 reactors. It is noted that one of the most important practical results of software packages for supporting NPP personnel concerning the issue of flow-accelerated corrosion consists in revealing elements under a hazard of intense local FAC thinning. Examples are given for successful practice at some Russian NPP concerning the use of software systems for supporting the personnel in early detection of secondary-circuit pipeline elements with FAC thinning close to an unacceptable level. Intermediate results of working on the Program are presented and new tasks set in 2012 as a part of the updated program are denoted. The prospects of the developed methods and tools in the scope of the Program measures at the stages of design and construction of NPP PGU are discussed. The main directions of the work on solving the problems of flow

  9. Preliminary design of the Carrisa Plains solar central receiver power plant. Volume III, Book 3. Appendices, Part 1

    Energy Technology Data Exchange (ETDEWEB)

    Mouradian, E. M.

    1983-12-31

    Thermal analyses for the preliminary design phase of the Receiver of the Carrizo Plains Solar Power Plant are presented. The sodium reference operating conditions (T/sub in/ = 610/sup 0/F, T/sub out/ = 1050/sup 0/F) have been considered. Included are: Nominal flux distribution on receiver panal, Energy input to tubes, Axial temperature distribution; sodium and tubes, Sodium flow distribution, Sodium pressure drop, orifice calculations, Temperature distribution in tube cut (R-0), Backface structure, and Nonuniform sodium outlet temperature. Transient conditions and panel front face heat losses are not considered. These are to be addressed in a subsequent design phase. Also to be considered later are the design conditions as variations from the nominal reference (operating) condition. An addendum, designated Appendix C, has been included describing panel heat losses, panel temperature distribution, and tube-manifold joint thermal model.

  10. Radiation effects on electronic equipment: a designers'/users' guide for the nuclear power industry

    International Nuclear Information System (INIS)

    Sharp, R.E.; Garlick, D.R.

    1994-01-01

    The Designers'/Users' Guide to the effects of radiation on electronics is published by the Radiation Testing Service of AEA Technology. The aim of the Guide is to document the available information that we have generated and collected over some ten years whilst operating as a radiation effects and design consultancy to the nuclear power industry. We hope that this will enable workers within the industry better to understand the likely effects of radiation on the system or plant being designed and so minimise the problems that can arise. (Author)

  11. IEC 61850. Integrated supervision of auxiliary power equipment; IEC 61850. Prozess und Eigenbedarf wachsen zusammen

    Energy Technology Data Exchange (ETDEWEB)

    Ostertag, Robert; Jung, Matthias [Siemens AG, Erlangen (Germany)

    2009-07-01

    It is state of technology today: Having process control and auxiliary power control integrated in one DCS. The integration is based on the international standard IEC 61850 which allows standardization of electrical structures from the process interface up to the DCS level. Modern control systems are designed to realize a system structure according to IEC 61850. A wide range of systems is available from systems with interfaces to realize a standardized data exchange up to systems with a complete integration of the standard IEC 61850. (orig.)

  12. Ultra sensitive sea water radioactivity monitoring system. Autonomous low power consumption equipped with wireless data communication

    International Nuclear Information System (INIS)

    Bonet, H.; Debauche, A.; Lellis, C. de; Adam, V.; Lacroix, J.P.; Put, P. van

    2003-01-01

    Following the recognition of their usefulness by the States and the scientific community, the automatic water monitoring networks were developed again to be able to measure sea water. For that purpose they had to be fully autonomous, have low power consumption (solar panels power supply), use wireless communicating (satellite, GSM, Radio) and be very sensitive (few Bq/m 3 ). It is important to note that radioactivity detection in sea has many constraints: The detection system sensitivity must be very high because of the dilution factor of the ocean. The analysis method has to be adapted: the detection of very low levels of artificial contamination is made difficult due to the natural radioactivity in seawater (i.e., more than 10 kBq of 40 K/m 3 ). The system has to be completely autonomous, 'wireless'. Additional conventional measuring probes must be connected to the system to increase its interest (pH, t deg, salinity, position, meteorology). The system maintenance must be very limited (1/year). Wind and corrosion resistance must be high. The probe must be installed on a buoy. Moreover, some improvements are needed to allow: Amplification Gain drifts due to NaI sensitivity to t deg to be compensated. Net peak area computation in a specific energy range. Interference correction to prevent false alarms due to natural radiation. Very long counting time. (author)

  13. A Multiagent Energy Management System for a Small Microgrid Equipped with Power Sources and Energy Storage Units

    Science.gov (United States)

    Radziszewska, Weronika; Nahorski, Zbigniew

    An Energy Management System (EMS) for a small microgrid is presented, with both demand and production side management. The microgrid is equipped with renewable and controllable power sources (like a micro gas turbine), energy storage units (batteries and flywheels). Energy load is partially scheduled to avoid extreme peaks of power demand and to possibly match forecasted energy supply from the renewable power sources. To balance the energy in the network on line, a multiagent system is used. Intelligent agents of each device are proactively acting towards balancing the energy in the network, and at the same time optimizing the cost of operation of the whole system. A semi-market mechanism is used to match a demand and a production of the energy. Simulations show that the time of reaching a balanced state does not exceed 1 s, which is fast enough to let execute proper balancing actions, e.g. change an operating point of a controllable energy source. Simulators of sources and consumption devices were implemented in order to carry out exhaustive tests.

  14. Communication received from the Member States of the European Community regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material

    International Nuclear Information System (INIS)

    1992-12-01

    The document reproduces the text of the note verbale received by the Director General on 30 November 1992 from the Permanent Missions to the Agency of Belgium, Denmark, France, Germany, Greece, Ireland, Italy, Luxembourg, Netherlands, Portugal, Spain and the United Kingdom of Great Britain and Northern Ireland, relating to the provision of certain additional information on production, inventories and international transfer of nuclear material and on exports of certain relevant equipment and non-nuclear material. The note verbale dated 23 November 1992, received by the Director General from the Commission of the European Communities and relating to the same subject, is reproduced as well

  15. Evaluation of a Trapezoidal Predictive Controller for a Four-Wire Active Power Filter for Utility Equipment of Metro Railway, Power-Land Substations

    Directory of Open Access Journals (Sweden)

    Sergio Salas-Duarte

    2016-01-01

    Full Text Available The realization of an improved predictive current controller based on a trapezoidal model is described, and the impact of this technique is assessed on the performance of a 2 kW, 21.6 kHz, four-wire, Active Power Filter for utility equipment of Metro Railway, Power-Land Substations. The operation of the trapezoidal predictive current controller is contrasted with that of a typical predictive control technique, based on a single Euler approximation, which has demonstrated generation of high-quality line currents, each using a 400 V DC link to improve the power quality of an unbalanced nonlinear load of Metro Railway. The results show that the supply current waveforms become virtually sinusoidal waves, reducing the current ripple by 50% and improving its power factor from 0.8 to 0.989 when the active filter is operated with a 1.6 kW load. The principle of operation of the trapezoidal predictive controller is analysed together with a description of its practical development, showing experimental results obtained with a 2 kW prototype.

  16. Communication received from the permanent mission of Austria regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material

    International Nuclear Information System (INIS)

    1996-01-01

    The Director General received a note verbale of 13 June 1996 from Permanent Mission of Austria regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material. In the light of the request expressed at the end of the note verbale, the text of the note verbale is being circulated

  17. Communication received from the Permanent Mission of Sweden regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material

    International Nuclear Information System (INIS)

    1996-01-01

    The document reproduces the text of a note verbale dated 28 June 1996 received by the Director General of IAEA from the Permanent Mission of Sweden through which the Government of Sweden provides, on a voluntary basis, certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material, in order to assist the Agency in the discharge of its safeguards responsibilities

  18. Communication received from the permanent mission of Finland regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material

    International Nuclear Information System (INIS)

    1996-01-01

    The Director General received a note verbale of 8 February 1996 from Permanent Mission of Finland regarding the provision of certain additional information on production, inventories and international transfers of nuclear material and on exports of certain relevant equipment and non-nuclear material. In the light of the request expressed at the and of the note verbale, the text of the note verbale is being circulated

  19. Fast diagnosis and treatment of cracklike defect injuriousness in PWR power plant equipment

    International Nuclear Information System (INIS)

    Benchimol, M.; Boneh, B.; Gilles, P.

    1983-08-01

    Defects detected in nuclear power plant components in the course of periodic inspections may have been formed during fabrication, at installation or in service. In order to accelerate decision-making subsequent to defect detection and increase the effectiveness of inspection programs, it is proposed in this paper that a package be prepared for each main system at the design stage to permit immediate diagnosis of defect injuriousness and to offer guidelines for mitigating action. The paper comprises: description of such a package, hereafter referred to as ''Defect Injuriousness Diagnosis and Treatment Package'' (DIDTP); breakdown of a DIDTP and demonstration of the computational methods used in its elaboration; presentation of the computer codes (ANODE, TITAN) used for automatic compilation of DIDTP's; example of DIDTP application

  20. Wireless power transfer electric vehicle supply equipment installation and validation tool

    Science.gov (United States)

    Jones, Perry T.; Miller, John M.

    2015-05-19

    A transmit pad inspection device includes a magnetic coupling device, which includes an inductive circuit that is configured to magnetically couple to a primary circuit of a charging device in a transmit pad through an alternating current (AC) magnetic field. The inductive circuit functions as a secondary circuit for a set of magnetically coupled coils. The magnetic coupling device further includes a rectification circuit, and includes a controllable load bank or is configured to be connected to an external controllable load back. The transmit pad inspection device is configured to determine the efficiency of power transfer under various coupling conditions. In addition, the transmit pad inspection device can be configured to measure residual magnetic field and the frequency of the input current, and to determine whether the charging device has been installed properly.

  1. Seismic isolation floor and vibration control equipment for nuclear power plant

    International Nuclear Information System (INIS)

    Niwa, H.; Fujimoto, S.; Aida, Y.; Miyano, H.

    1996-01-01

    We have developed a seismic isolation floor to improve protection against earthquakes for process computer systems, and a magnetic dynamic damper to reduce the mechanical vibrations of piping systems and pumps in nuclear power plants. Seismic excitation tests of the seismic isolation floor, on which process computer systems were installed, were performed using large earthquake simulators. The test results proved that the seismic isolation floor significantly reduced seismic forces. To control mechanical vibrations, a magnetic dynamic damper was designed using permanent magnets. This magnetic dynamic damper does not require mechanical springs, dampers and supports in the floors and walls of the building. Vibration tests using a rotating machine model confirmed that the magnetic dynamic damper effectively controlled vibrations in such a rotating machine model. (author)

  2. Redesigning transport equipment – comparative analysis of energy expenditure (power and water in refrigerators

    Directory of Open Access Journals (Sweden)

    Lisiane Ilha Librelotto

    2015-12-01

    Full Text Available Sustainability is defined as an approach that integrates social, economic and environmental concerns (SEE. This philosophy carries several implications for daily factory work, where culturally, the economic issue is considered most important. This paper provides a case study at a meat and bone-meal (MBM factory, and the preliminary studies of the adaptation of this factory to the SEE philosophy, focusing initially on economic aspect, and its relationship with the two other aspects. It also shows how the design of a conveyor belt - used to transport entrails and feathers from the slaughter site to the byproducts production site - could improve the consumption of power and water resources at the factory studied. Currently, this transport is accomplished manually (for feathers and by pneumatic conveying (for entrails. As a result, it was found that a change in the transport processes to align with the SEE philosophy would allow an 18% reduction of water use.

  3. Development of an acoustic emission equipment for valves of the Nuclear Power Station Atucha 1

    International Nuclear Information System (INIS)

    Giaccheta, R.; Lopez Pumarega, I.; Straus, A.; Ruzzante, J.; Herzovich, P.

    1994-01-01

    A four channel Acoustic Emission was developed by the Acoustic Emission Group, INEND Department, of the Atomic Energy Commission of Argentina, for the detection of leaks in valves of the pressurized air system: ''Sistema de desconexion de emergencias por acido deuteroborico''. Basically, the system consists of four piezoelectric transducers with their corresponding preamplifiers coupled to the piping close to the valves. The following stages: amplifiers, threshold levels, channel identifications and visual alarm system are gathered in a box. The system was installed in the controlled zone of the Nuclear Power Stations Atucha I. It was calibrated and works on line. The values shown on the display are registered daily in order to separate the normal values from the leak ones. (author). 4 refs, 9 figs

  4. Nanotechnology based surface treatments for corrosion protection and deposit control of power plant equipment. Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-05-15

    Nanotechnology can provide possibilities for obtaining new valuable information regarding performance and corrosion protection in power plants. In general the desired performance of the contact surfaces is an easy-to-release effect. This is in order to prolong the time interval between cleaning periods or make the cleaning procedures easier and less expensive. Corrosion protection is also desired in order to extend the life time of various parts in the power plants and thus optimize the energy output and overall efficiency of the plant. Functional sol-gel coating based on nanotechnology is tested in a variety of conditions. Applications of functional sol-gel coatings were performed in the condenser and on seven air preheaters at Fynsvaerket, Odense, with corrosion protection as the main issue. Coatings with easy-to-clean effects were tested in the Flue Gas Desulphurization plant at Nordjyllandsvaerket, Aalborg, with the aim of reducing gipsum deposit. Thermo stabilized coatings were tested on tube bundles between in the passage from the 1st to 2end pass and on the wall between 1st and 2end pass at Amagervaerket, Copenhagen, and in the boiler at Haderslev CHP plant. The objective of this test were reducing deposits and increasing corrosion protection. The tested coatings were commercial available coatings and coatings developed in this project. Visual inspections have been performed of all applications except at Nordjyllandsvaerket. Corrosion assessment has been done at DTU - Mechanical Engineering. The results range from no difference between coated and uncoated areas to some improvements. At Amagervaerket the visual assessment showed in general a positive effect with a sol-gel hybrid system and a commercial system regarding removal of deposits. The visual assessment of the air preheaters at Fynsvaerket indicates reduced deposits on a sol-gel nanocomposite coated air preheater compared to an uncoated air preheater. (Author)

  5. Evaluation of Storage for Transportation Equipment, Unfueled Convertors, and Fueled Convertors at the INL for the Radioisotope Power Systems Program

    Energy Technology Data Exchange (ETDEWEB)

    S. G. Johnson; K. L. Lively

    2010-05-01

    This report contains an evaluation of the storage conditions required for several key components and/or systems of the Radioisotope Power Systems (RPS) Program at the Idaho National Laboratory (INL). These components/systems (transportation equipment, i.e., type ‘B’ shipping casks and the radioisotope thermo-electric generator transportation systems (RTGTS), the unfueled convertors, i.e., multi-hundred watt (MHW) and general purpose heat source (GPHS) RTGs, and fueled convertors of several types) are currently stored in several facilities at the Materials and Fuels Complex (MFC) site. For various reasons related to competing missions, inherent growth of the RPS mission at the INL and enhanced efficiency, it is necessary to evaluate their current storage situation and recommend the approach that should be pursued going forward for storage of these vital RPS components and systems. The reasons that drive this evaluation include, but are not limited to the following: 1) conflict with other missions at the INL of higher priority, 2) increasing demands from the INL RPS Program that exceed the physical capacity of the current storage areas and 3) the ability to enhance our current capability to care for our equipment, decrease maintenance costs and increase the readiness posture of the systems.

  6. A Novel Short-Term Maintenance Strategy for Power Transmission and Transformation Equipment Based on Risk-Cost-Analysis

    Directory of Open Access Journals (Sweden)

    Hang Yang

    2017-11-01

    Full Text Available Current studies on preventive condition-based maintenance of power transmission and transformation equipment mainly focus on mid-term or long-term maintenance, and cannot meet the requirements of short-term especially temporary maintenance. In order to solve the defects of the present preventive maintenance strategies, according to the engineering application and based on risk-cost analysis, a short-term maintenance strategy is proposed in this manuscript. For the equipment working in bad health condition, its active maintenance costs and operation risk costs are evaluated, respectively. Then the latest maintenance time is calculated in accordance with the principle that its operation risk costs are no higher than active maintenance costs. Utilizing the latest maintenance time, the best maintenance time is calculated by setting the maximum relative earnings of postponing maintenance as the target, which provides the operation staffs with comprehensive maintenance-decision support. In the end, different cases on the IEEE 24-bus system are simulated. The effectiveness and advantages of the proposed strategy are demonstrated by the simulation results.

  7. Study on intelligence fault diagnosis method for nuclear power plant equipment based on rough set and fuzzy neural network

    International Nuclear Information System (INIS)

    Liu Yongkuo; Xia Hong; Xie Chunli; Chen Zhihui; Chen Hongxia

    2007-01-01

    Rough set theory and fuzzy neural network are combined, to take full advantages of the two of them. Based on the reduction technology to knowledge of Rough set method, and by drawing the simple rule from a large number of initial data, the fuzzy neural network was set up, which was with better topological structure, improved study speed, accurate judgment, strong fault-tolerant ability, and more practical. In order to test the validity of the method, the inverted U-tubes break accident of Steam Generator and etc are used as examples, and many simulation experiments are performed. The test result shows that it is feasible to incorporate the fault intelligence diagnosis method based on rough set and fuzzy neural network in the nuclear power plant equipment, and the method is simple and convenience, with small calculation amount and reliable result. (authors)

  8. Statistical analysis of the behaviour of the mechanical equipment of EDFs power plants - evaluation of the availability and safety of thermal and nuclear units

    International Nuclear Information System (INIS)

    Procaccia, H.; Brillon, A.; Cravero, M.; Lucenet, G.

    1975-01-01

    The investigation and research directorate of EDF has undertaken a statistical analysis of the behaviour of large mechanical equipment at conventional power stations during the ten years following the operating reports of these stations. It has thus been possible to determine the intrinsic reliability, the failure rate, the mean repair time, and the mean good operating time of feed water reheating points, power turbines, pumps and boilers of the various EDF plants (125 and 250 MW) leading to a consideration of the feasibility of an extrapolation to present and future plants. Based on these elementary investigation two methods of calculation have been developed. One is used to assess the overall availability of a thermal or nuclear power station based on the knowledge of the failure rates of the equipment, each piece of equipment being associated with an idea of its technical importance in the functioning of the equipment. A numerical application is given for 125 and 250 MW conventional plants. The purpose of the other method is to estimate the operational safety of the safety equipment of nuclear power stations, based on the development of tree diagrams for faults in basic equipment. A numerical example is given for the cooling systems for Phenix and for one of the Super Phenix versions. (author)

  9. Development of preventive maintenance technology and advanced service equipment for operating nuclear power plants

    International Nuclear Information System (INIS)

    Abe, Kazuhiro; Sumikawa, Masaharu; Hirakawa, Hiromasa; Arakawa, Tadao; Hasegawa, Kunio; Kato, Kanji.

    1990-01-01

    Hitachi Ltd. as a manufacturer of nuclear power plants has carried out the consistent general preventive maintenance activities from the planning of the plants and the design of maintainability in the construction phase to the planning and working of preventive maintenance in the operation and maintenance phase, and exerted efforts to heighten the capacity ratio and reliability of the plants. For the purpose, the steady activities of reliability improvement have been carried out throughout the whole company, and the rationalization of the planning and management of the preventive maintenance with a computer and the development of the robots to which Al is applied have been promoted. As the technology of upgrading the facilities, boron racks, the control rods having long life and so on were developed, and their practical use is advanced. Moreover for the future, the development of the diagnostic technology on material deterioration using superconductive quantum interference devices (SQUID) is in progress. The preventive maintenance activities in Hitachi Ltd., the technical development for the purpose and the upgrading of the plant facilities are reported. (K.I.)

  10. Dynamic analysis of electric equipment for nuclear power stations under seismic loads

    International Nuclear Information System (INIS)

    Buck, K.E.; Bodisco, U. von; Winkler, K.

    1977-01-01

    The response spectrum method, generally accepted as the most practical method for linear seismic analysis of power station components, is here applied in conjunction with the finite element method to electric components. The fully dynamic analysis based on the superposition of the natural modes as carried out for an electronics cabinet and for transmitter supports is outlined and selected results are presented. Several different methods are in use for the superposition of the contributions of the different modes. Here addition of absolute values, the square-root of the sum of squares, and a mixed method taking account of closely spaced modes is applied. For different structures, the degree of conservativity is thus demonstrated, the largest difference in the stresses computed by the different methods being approximately 30%. For structures whose natural frequencies are in the spectrum range with zero period response, a simplified response analysis using static loads is often carried out. This is demonstrated for the electronics cabinet and transmitter mountings, and the results are compared with the fully dynamic analyses. It is seen that this 'pseudo-dynamic' analysis yields useful approximations for the distributions of stresses. Practical details of the structural models as well as results are presented for several switchgear and electronics cabinets

  11. Fast diagnosis and treatment of cracklike defect injuriousness in PWR power plant equipment

    International Nuclear Information System (INIS)

    Boneh, B.; Gilles, P.; Benchimol, M.

    1983-01-01

    The potential risk of cracking phenomena (initial defects or propagating cracks) in auxiliary and secondary power plant systems makes it essential to evaluate the injuriousness of such defects. This paper presents a Defect Injuriousness Diagnosis and Treatment Package (DIDTP) which can be applied to auxiliary and secondary system analysis during manufacturing and installation work as well as during actual system operation. Following a presentation of the individual elements comprising a DIDTP, a description is given of the analytical and computational methods, which are based on brittle and ductile fracture mechanics concepts fundamental to any DIDTP. A brief description is then given of the TITAN and ANODE computer codes developed by FRAMATOME which are used for automatic compilation of DIDTP's. Finally, a practical example is given to demonstrate the different stages involved in the compilation of a DIDTP, and the way in which the DIDTP can be used to provide results which make it possible to determine short or longterm actions: rework of faulty component, operating modifications, monitoring of critical zones, additional computations, etc. (orig./GL)

  12. Instantaneous response spectrum in seismic testing of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Morrone, A.

    1977-01-01

    This paper presents the concept of instantaneous response spectrum (IRS) as the response of single degree of freedom oscillators at a particular time. It demonstrates that a shake table random motion whose standard TRS envelops the RRS does not necessarily satisfy the enveloping requirement instantaneously. That is, any one (or more) instantaneous required response spectrum (IRRS) is not enveloped by any instantaneous test response spectrum (ITRS). Response spectra from different time histories, including single frequency sine beat motion used in resonance testing, are compared for enveloping with maximum response and with the actual response at particular times. These comparisons are given for the enveloping of RRS and IRRS derived with a time history response calculated at a particular building elevation of a nuclear power plant. For the test motion, several of the most severe ITRS derived with a modified EL Centro motion and with a sine beat motion with ten cycles per beat were used. It is shown that although the TRS with the modified EL Centro motion enveloped the given RRS, the selected modified EL Centro ITRS did not envelop the corresponding IRRS. With the sine beat motion, even though the TRS did not fully envelop the given RRS, the resulting sine beat ITRS did not require a larger factor for full IRRS enveloping than those of the modified EL Centro motion

  13. A Prototype PZT Matrix Transducer With Low-Power Integrated Receive ASIC for 3-D Transesophageal Echocardiography.

    Science.gov (United States)

    Chen, Chao; Raghunathan, Shreyas B; Yu, Zili; Shabanimotlagh, Maysam; Chen, Zhao; Chang, Zu-yao; Blaak, Sandra; Prins, Christian; Ponte, Jacco; Noothout, Emile; Vos, Hendrik J; Bosch, Johan G; Verweij, Martin D; de Jong, Nico; Pertijs, Michiel A P

    2016-01-01

    This paper presents the design, fabrication, and experimental evaluation of a prototype lead zirconium titanate (PZT) matrix transducer with an integrated receive ASIC, as a proof of concept for a miniature three-dimensional (3-D) transesophageal echocardiography (TEE) probe. It consists of an array of 9 ×12 piezoelectric elements mounted on the ASIC via an integration scheme that involves direct electrical connections between a bond-pad array on the ASIC and the transducer elements. The ASIC addresses the critical challenge of reducing cable count, and includes front-end amplifiers with adjustable gains and micro-beamformer circuits that locally process and combine echo signals received by the elements of each 3 ×3 subarray. Thus, an order-of-magnitude reduction in the number of receive channels is achieved. Dedicated circuit techniques are employed to meet the strict space and power constraints of TEE probes. The ASIC has been fabricated in a standard 0.18-μm CMOS process and consumes only 0.44 mW/channel. The prototype has been acoustically characterized in a water tank. The ASIC allows the array to be presteered across ±37° while achieving an overall dynamic range of 77 dB. Both the measured characteristics of the individual transducer elements and the performance of the ASIC are in good agreement with expectations, demonstrating the effectiveness of the proposed techniques.

  14. Ultra-low-power and ultra-low-cost short-range wireless receivers in nanoscale CMOS

    CERN Document Server

    Lin, Zhicheng; Martins, Rui Paulo

    2016-01-01

    This book provides readers with a description of state-of-the-art techniques to be used for ultra-low-power (ULP) and ultra-low-cost (ULC), short-range wireless receivers. Readers will learn what is required to deploy these receivers in short-range wireless sensor networks, which are proliferating widely to serve the internet of things (IoT) for “smart cities.” The authors address key challenges involved with the technology and the typical tradeoffs between ULP and ULC. Three design examples with advanced circuit techniques are described in order to address these trade-offs, which specially focus on cost minimization. These three techniques enable respectively, cascading of radio frequency (RF) and baseband (BB) circuits under an ultra-low-voltage (ULV) supply, cascoding of RF and BB circuits in current domain for current reuse, and a novel function-reuse receiver architecture, suitable for ULV and multi-band ULP applications such as the sub-GHz ZigBee. ·         Summarizes the state-of-the-art i...

  15. An artificial vision-based control system for automatic heliostat positioning offset correction in a central receiver solar power plant

    Energy Technology Data Exchange (ETDEWEB)

    Berenguel, M. [Universidad de Almeria, Dept. de Lenguajes y Computacion, La Canada Almeria (Spain); Rubio, F.R.; Lara, P.J.; Arahal, M.R.; Camacho, E.F.; Lopez, M. [Universidad de Sevilla, Dept. de Ingenieria de Sistemas y Automatica, Sevilla (Spain); Valverde, A. [Plataforma Solar de Almeria (PSA-CIEMAT), Tabernas (Almeria) (Spain)

    2004-07-01

    This paper presents the development of a simplified and automatic heliostat positioning offset correction control system using artificial vision techniques and common CCD devices. The heliostats of a solar power plant reflect solar radiation onto a receiver (in this case, a volumetric receiver) placed at the top of a tower in order to provide a desired energy flux distribution correlated with the coolant flow (in this case air mass flow) through the receiver, usually in an open loop control configuration. There exist error sources that increase the complexity of the control system, some of which are systematic ones, mainly due to tolerances, wrong mirror facets alignment (optical errors), errors due to the approximations made when calculating the solar position, etc., that produce errors (offsets) in the heliostat orientation (aiming point). The approximation adopted in this paper is based on the use of a B/W CCD camera to correct these deviations in an automatic way imitating the same procedure followed by the operators. The obtained images are used to estimate the distance between the sunbeam centroid projected by the heliostats and a target placed on the tower, this distance thus is used for low accuracy offset correction purposes. Basic threshold-based image processing techniques are used for automatic correction. (Author)

  16. Comparison of EMI/RFI requirements to qualify the equipment for nuclear power plant. (RG 1.180, EPRI TR 102323, IEC 62003 and GB/T 11684)

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Tae Heon [Korea Testing Laboratory, Ansan (Korea, Republic of); Kim, Jong Seog [Research Institute of Korea Electric Power Corporation, Daejeon (Korea, Republic of); Seo, Jeong Ho; Cho, Kyoung Youn [Korea Electric Association, Seoul (Korea, Republic of)

    2011-05-15

    One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). In some reports for nuclear power plant (NPP), electromagnetic interference (EMI), radio frequency interference (RFI), and power surges have been identified as environmental conditions that can affect the performance of safety-related electrical equipment. There are mainly two reference guides for applying to qualify EMI/RFI requirements of the equipment used in a NPP: US NRC RG 1.180 and EPRI TR 102323. Recently, IEC published the standard for the equipment in the NPP, IEC 62003. This paper has compared the requirements of these, including comparing of the requirement of the Chinese national standard, GB/T 11684

  17. Comparison of EMI/RFI requirements to qualify the equipment for nuclear power plant. (RG 1.180, EPRI TR 102323, IEC 62003 and GB/T 11684)

    International Nuclear Information System (INIS)

    Jang, Tae Heon; Kim, Jong Seog; Seo, Jeong Ho; Cho, Kyoung Youn

    2011-01-01

    One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). In some reports for nuclear power plant (NPP), electromagnetic interference (EMI), radio frequency interference (RFI), and power surges have been identified as environmental conditions that can affect the performance of safety-related electrical equipment. There are mainly two reference guides for applying to qualify EMI/RFI requirements of the equipment used in a NPP: US NRC RG 1.180 and EPRI TR 102323. Recently, IEC published the standard for the equipment in the NPP, IEC 62003. This paper has compared the requirements of these, including comparing of the requirement of the Chinese national standard, GB/T 11684

  18. Design of ultralow power receiver front-ends for 2.4 GHz wireless sensor network applications

    International Nuclear Information System (INIS)

    Zhang Meng; Li Zhiqun; Wang Zengqi; Wu Chenjian; Chen Liang

    2014-01-01

    This paper presents the design of an ultralow power receiver front-end designed for a wireless sensor network (WSN) in a 0.18 μm CMOS process. The author designs two front-ends working in the saturation region and the subthreshold region respectively. The front-ends contain a two-stage cross-coupling cascaded common-gate (CG) LNA and a quadrature Gilbert IQ mixer. The measured conversion gain is variable with high gain at 24 dB and low gain at 7 dB for the saturation one, and high gain at 22 dB and low gain at 5 dB for the subthreshold one. The noise figure (NF) at high gain mode is 5.1 dB and 6.3 dB for each. The input 1 dB compression point (IP1dB) at low gain mode is about −6 dBm and −3 dBm for each. The front-ends consume about 2.1 mA current from 1.8 V power supply for the saturation one and 1.3 mA current for the subthreshold one. The measured results show that, comparing with the power consumption saving, it is worth making sacrifices on the performance for using the subthreshold technology. (semiconductor integrated circuits)

  19. Communication Received from the Permanent Mission of Mexico to the International Atomic Energy Agency Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology and the Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2012-01-01

    The Director General has received a note verbale dated 15 June 2012 from the Permanent Mission of Mexico to the International Atomic Energy Agency providing information on the decision of the Government of Mexico to act in accordance with the 'Guidelines for the Export of Nuclear Material, Equipment and Technology', issued as document INFCIRC/254/Rev.10/Part 1, including its Annexes, and with the 'Guidelines for Transfers of Nuclear-Related Dual-Use Equipment, Material, Software and Related Technology', issued as document INFCIRC/254/Rev.8/Part 2

  20. Communication Received from the PermanentMission of Mexico to the International Atomic Energy Agency Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology and the Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2012-01-01

    The Director General has received a note verbale dated 15 June 2012 from the Permanent Mission of Mexico to the International Atomic Energy Agency providing information on the decision of the Government of Mexico to act in accordance with the 'Guidelines for the Export of Nuclear Material, Equipment and Technology', issued as document INFCIRC/254/Rev.10/Part 1, including its Annexes, and with the 'Guidelines for Transfers of Nuclear-Related Dual-Use Equipment, Material, Software and Related Technology', issued as document INFCIRC/254/Rev.8/Part 2

  1. Communication Received from the Permanent Mission of the Republic of Serbia to the International Atomic Energy Agency Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology and the Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2012-01-01

    The Director General has received a note verbale dated 28 September 2012 from the Permanent Mission of Serbia to the International Atomic Energy Agency providing information on the decision of the Government of Serbia to adhere to the 'Guidelines for the Export of Nuclear Material, Equipment and Technology', issued as document INFCIRC/254/Rev.10/Part 1, including its Annexes, and with the 'Guidelines for Transfers of Nuclear-Related Dual-Use Equipment, Material, Software and Related Technology', issued as document INFCIRC/254/Rev.8/Part 2 [fr

  2. Communication Received from the PermanentMission of Mexico to the International Atomic Energy Agency Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology and the Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-06-19

    The Director General has received a note verbale dated 15 June 2012 from the Permanent Mission of Mexico to the International Atomic Energy Agency providing information on the decision of the Government of Mexico to act in accordance with the 'Guidelines for the Export of Nuclear Material, Equipment and Technology', issued as document INFCIRC/254/Rev.10/Part 1, including its Annexes, and with the 'Guidelines for Transfers of Nuclear-Related Dual-Use Equipment, Material, Software and Related Technology', issued as document INFCIRC/254/Rev.8/Part 2.

  3. Communication Received from the Permanent Mission of Mexico to the International Atomic Energy Agency Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology and the Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-06-19

    The Director General has received a note verbale dated 15 June 2012 from the Permanent Mission of Mexico to the International Atomic Energy Agency providing information on the decision of the Government of Mexico to act in accordance with the 'Guidelines for the Export of Nuclear Material, Equipment and Technology', issued as document INFCIRC/254/Rev.10/Part 1, including its Annexes, and with the 'Guidelines for Transfers of Nuclear-Related Dual-Use Equipment, Material, Software and Related Technology', issued as document INFCIRC/254/Rev.8/Part 2.

  4. Communication Received from the Permanent Mission of the Republic of Serbia to the International Atomic Energy Agency Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology and the Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2012-01-01

    The Director General has received a note verbale dated 28 September 2012 from the Permanent Mission of Serbia to the International Atomic Energy Agency providing information on the decision of the Government of Serbia to adhere to the 'Guidelines for the Export of Nuclear Material, Equipment and Technology', issued as document INFCIRC/254/Rev.10/Part 1, including its Annexes, and with the 'Guidelines for Transfers of Nuclear-Related Dual-Use Equipment, Material, Software and Related Technology', issued as document INFCIRC/254/Rev.8/Part 2 [es

  5. Communication Received from the Permanent Mission of the Republic of Serbia to the International Atomic Energy Agency Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology and the Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2012-01-01

    The Director General has received a note verbale dated 28 September 2012 from the Permanent Mission of Serbia to the International Atomic Energy Agency providing information on the decision of the Government of Serbia to adhere to the 'Guidelines for the Export of Nuclear Material, Equipment and Technology', issued as document INFCIRC/254/Rev.10/Part 1, including its Annexes, and with the 'Guidelines for Transfers of Nuclear-Related Dual-Use Equipment, Material, Software and Related Technology', issued as document INFCIRC/254/Rev.8/Part 2

  6. Experience in the use of teleoperated robotic equipment in the Spanish Nuclear Power Plants (S.R.T. Project)

    International Nuclear Information System (INIS)

    Bielza, M.; Gomez, J.; Izquierdo, J.A.; Bercedo, A.; Espallardo, J.A.; Martinez, A.; Carmena, P.; Pascual, J.L.

    1998-01-01

    The main objective of the Teleoperated Robotic Systems project (SRT) is the development of teleoperated robotic systems for use in the inspection, surveillance and maintenance operations in nuclear and radioactive installations. These systems make possible the reduction of the individual and collective doses of the workers that undertake these operations, as well as an increase of plant availability as it is possible to carry out specific tasks of inspection and surveillance in high radiation dose areas without to reduce the power of the installation. This project started in 1995 deciding to priorize the inspection equipment in a first phase. As a result of this work currently several semi-industrial products are available: ROBCAR, ROBICEN y ANAES. These have been installed for testing and commercial operation in Spanish nuclear installations. In this paper the experience of using these prototypes in the S.M. de Garona and Cofrentes nuclear power plants is described, as well as the improvements in the design of these systems derived from these experiences that have been incorporated to the industrial prototypes that are currently in the last phase of development. (Author)

  7. Power Doppler ultrasonography and synovitis: correlating ultrasound imaging with histopathological findings and evaluating the performance of ultrasound equipments.

    Science.gov (United States)

    Koski, J M; Saarakkala, S; Helle, M; Hakulinen, U; Heikkinen, J O; Hermunen, H

    2006-12-01

    To examine the validity of power Doppler ultrasound imaging to identify synovitis, using histopathology as gold standard, and to assess the performance of ultrasound equipments. 44 synovial sites in small and large joints, bursae and tendon sheaths were depicted with ultrasound. A synovial biopsy was performed on the site depicted and a synovial sample was taken for histopathological evaluation. The performance of three ultrasound devices was tested using flow phantoms. A positive Doppler signal was detected in 29 of 35 (83%) of the patients with active histological inflammation. In eight additional samples, histological examination showed other pathological synovial findings and a Doppler signal was detected in five of them. No significant correlation was found between the amount of Doppler signal and histological synovitis score (r = 0.239, p = NS). The amount of subsynovial infiltration of polymorphonuclear leucocytes and surface fibrin correlated significantly with the amount of power Doppler signal: r = 0.397 (pultrasound devices differed in showing the smallest detectable flow. A negative Doppler signal does not exclude the possibility of synovitis. A positive Doppler signal in the synovium is an indicator of an active synovial inflammation in patients. A Doppler signal does not correlate with the extent of the inflammation and it can also be seen in other synovial reactions. It is important that the quality measurements of ultrasound devices are reported, because the results should be evaluated against the quality of the device used.

  8. Fundamental characteristics of new electric power storage equipment celled `ECS`; Atarashii denryoku chozo sochi `ECS` no kisoteki tokusei

    Energy Technology Data Exchange (ETDEWEB)

    Okamura, T.; Yamagishi, M.

    1997-01-30

    This paper introduces new electric power storage equipment called an energy capacitor system. A special electrically double-layered capacitor with its energy density raised in sacrifice of internal resistance has the current so adjusted that loss will not increase by using a switching converter (consisting of a charger and a current pump). The capacitor is charged and discharged at high efficiency. Upper limits of the charge voltage for each capacitor are connected with parallel monitor circuits so that maximum charge voltage of each capacitor will be aligned at one level, wherein charge and discharge are performed with that voltage used as the starting point. A drawback in a capacitor is lower energy density than in a secondary battery. Therefore, high voltage withstanding organic electrolyte was used, and electrode activated carbon was given discussions starting from its raw material structures. The efforts resulted in obtaining as high energy density as 43 Wh/kg (about 20 times as much as in conventional materials, and comparable to lead-acid batteries). In order to minimize heat generation due to the increased internal resistance, a switching converter was used to suppress charge/discharge currents to the minimum required levels. Although the capacitor still has insufficient voltage withstanding power and short life, the energy density is increasing beyond the initial estimation. The next problem to be solved is reduction in production cost for its industrialization. 4 refs., 4 figs., 2 tabs.

  9. Upgrading Planning and Executive Strategy for Reactor Protection System and Relative Equipment in Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Jiang Zuyue

    2010-01-01

    Qinshan Nuclear Power Plant (QNPP) is the first nuclear power plant in China which completed the reactor protection system (RPS) upgrading with new digital safety instrumentation and control (I and C) platform instead of original analog system. At the same time,the nuclear instrumentation system (NIS) was upgraded with the same digital I and C platform. For adapting QNPP's actual engineering situation,the upgrading planning was taken by comprehensively investigating current development and application of digital safety I and C platform in the worldwide scope and by reviewing plant's original systems operation history. The project executive strategy-QNPP's leading role with necessary overseas cooperation and internal technical supports as great as possible, was determined. Some significant factors might influence and restrict the RPS and relative equipment upgrading executive actions in an operating NPP were analyzed.Finally, the engineering feasibility was briefly assessed to recognize the anticipated issues and difficulties and to prepare the relative solutions in advance for the purpose of ensuring the RPS upgrading objectives completely realized. (authors)

  10. Procedure for qualify class 1E equipment for nuclear power generating stations; Kvalifikacija elektroopreme za stjecanje klase 1E u nuklearnim elektranama

    Energy Technology Data Exchange (ETDEWEB)

    Smiljanic, D [' Rade Koncar' Institut, Zagreb (Yugoslavia)

    1983-07-01

    This paper describes the basic requirements for qualifying Class 1E equipment and systems that are to be used in nuclear power generating stations. The requirements presented include the principles, procedures and methods of qualification. The qualification requirements will confirm the adequacy of the equipment design under normal, abnormal, design basis event, post design basis event and containment test conditions for the performance of Class 1 E functions. The presented methods of qualification are in accordance with IEEE Standards and other standards (IEC, JUS, DIN, etc,), and have the primary role to provide guidance for demonstrating the qualification of Class 1E equipment produced by 'Rade Koncar'.(author)

  11. Study of a thermoelectric system equipped with a maximum power point tracker for stand-alone electric generation.

    Science.gov (United States)

    Favarel, C.; Champier, D.; Bédécarrats, J. P.; Kousksou, T.; Strub, F.

    2012-06-01

    According to the International Energy Agency, 1.4 billion people are without electricity in the poorest countries and 2.5 billion people rely on biomass to meet their energy needs for cooking in developing countries. The use of cooking stoves equipped with small thermoelectric generator to provide electricity for basic needs (LED, cell phone and radio charging device) is probably a solution for houses far from the power grid. The cost of connecting every house with a landline is a lot higher than dropping thermoelectric generator in each house. Thermoelectric generators have very low efficiency but for isolated houses, they might become really competitive. Our laboratory works in collaboration with plane`te-bois (a non governmental organization) which has developed energy-efficient multifunction (cooking and hot water) stoves based on traditional stoves designs. A prototype of a thermoelectric generator (Bismuth Telluride) has been designed to convert a small part of the energy heating the sanitary water into electricity. This generator can produce up to 10 watts on an adapted load. Storing this energy in a battery is necessary as the cooking stove only works a few hours each day. As the working point of the stove varies a lot during the use it is also necessary to regulate the electrical power. An electric DC DC converter has been developed with a maximum power point tracker (MPPT) in order to have a good efficiency of the electronic part of the thermoelectric generator. The theoretical efficiency of the MMPT converter is discussed. First results obtained with a hot gas generator simulating the exhaust of the combustion chamber of a cooking stove are presented in the paper.

  12. Research on big data risk assessment of major transformer defects and faults fusing power grid, equipment and environment based on SVM

    Science.gov (United States)

    Guo, Lijuan; Yan, Haijun; Gao, Wensheng; Chen, Yun; Hao, Yongqi

    2018-01-01

    With the development of power big data, considering the wider power system data, the appropriate large data analysis method can be used to mine the potential law and value of power big data. On the basis of considering all kinds of monitoring data and defects and fault records of main transformer, the paper integrates the power grid, equipment as well as environment data and uses SVM as the main algorithm to evaluate the risk of the main transformer. It gets and compares the evaluation results under different modes, and proves that the risk assessment algorithms and schemes have certain effectiveness. This paper provides a new idea for data fusion of smart grid, and provides a reference for further big data evaluation of power grid equipment.

  13. Thermal Integration of CO{sub 2} Compression Processes with Coal-Fired Power Plants Equipped with Carbon Capture

    Energy Technology Data Exchange (ETDEWEB)

    Edward Levy

    2012-06-29

    Coal-fired power plants, equipped either with oxycombustion or post-combustion CO{sub 2} capture, will require a CO{sub 2} compression system to increase the pressure of the CO{sub 2} to the level needed for sequestration. Most analyses show that CO{sub 2} compression will have a significant effect on parasitic load, will be a major capital cost, and will contribute significantly to reduced unit efficiency. This project used first principle engineering analyses and computer simulations to determine the effects of utilizing compressor waste heat to improve power plant efficiency and increase net power output of coal-fired power plants with carbon capture. This was done for units with post combustion solvent-based CO{sub 2} capture systems and for oxyfired power plants, firing bituminous, PRB and lignite coals. The thermal integration opportunities analyzed for oxycombustion capture are use of compressor waste heat to reheat recirculated flue gas, preheat boiler feedwater and predry high-moisture coals prior to pulverizing the coal. Among the thermal integration opportunities analyzed for post combustion capture systems are use of compressor waste heat and heat recovered from the stripper condenser to regenerate post-combustion CO{sub 2} capture solvent, preheat boiler feedwater and predry high-moisture coals. The overall conclusion from the oxyfuel simulations is that thermal integration of compressor heat has the potential to improve net unit heat rate by up to 8.4 percent, but the actual magnitude of the improvement will depend on the type of heat sink used and to a lesser extent, compressor design and coal rank. The simulations of a unit with a MEA post combustion capture system showed that thermal integration of either compressor heat or stripper condenser heat to preheat boiler feedwater would result in heat rate improvements from 1.20 percent to 4.19 percent. The MEA capture simulations further showed that partial drying of low rank coals, done in combination

  14. Portfolio Purchasing Decision for Mobile Power Equipment of B2C E-Commerce Export Retailer Based on CVaR

    Science.gov (United States)

    Yanchun, Wan; Qiucen, Chen

    2017-11-01

    Purchasing is an important part of export e-commerce of B2C, which plays an important role on risk and cost control in supply management. From the perspective of risk control, the paper construct a CVaR model for portfolio purchase. We select a heavy sales mobile power equipment from a typical B2C e-commerce export retailer as study sample. This study optimizes the purchasing strategy of this type of mobile power equipment. The research has some reference for similar enterprises in purchasing portfolio decision.

  15. Construction of a model of the process of accumulation of radionuclides of corrosion products on the equipment in nuclear power plants with boiling-water reactors

    International Nuclear Information System (INIS)

    Tevlin, S.A.

    1985-01-01

    This paper addresses the problem of corrosion of the structural materials of the reactor loop. This problem can be solved by constructing physical models of the process of accumulation of radionuclides on the equipment at nuclear power plants and by constructing the analytical apparatus for describing them. These models are presented here, and allow the analyzing of the effect of separate states and thermophysical factors, determination of the basic factors, and the ability to foresee in timely fashion the water state and structural measures required to lower the rate of growth and to decrease the amount of radionuclides deposited on the equipment in the nuclear power plant

  16. Communication Received from the Permanent Mission of the Netherlands regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2011-12-01

    The Agency has received a Note Verbale from the Permanent Mission of the Kingdom of the Netherlands, dated 12 July 2011, in which it requests that the Agency circulate to all Member States a letter of 12 July 2011 from the Chairman of the Nuclear Suppliers Group, Ambassador Piet de Klerk, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [es

  17. Communication Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material, Software and Related Technology

    International Nuclear Information System (INIS)

    2010-01-01

    The Agency has received a Note Verbale from the Permanent Mission of Hungary, dated 14 June 2010, in which it requests that the Agency circulate to all Member States a letter of 7 May 2010 from the Chairman of the Nuclear Suppliers Group, Ambassador Ms. Gyorgyi Martin Zanathy, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America,1 providing further information on those Governments’ Guidelines for Nuclear Transfers [es

  18. Communication Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material, Software and Related Technology

    International Nuclear Information System (INIS)

    2010-01-01

    The Agency has received a Note Verbale from the Permanent Mission of Hungary, dated 14 June 2010, in which it requests that the Agency circulate to all Member States a letter of 7 May 2010 from the Chairman of the Nuclear Suppliers Group, Ambassador Ms. Gyorgyi Martin Zanathy, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America,1 providing further information on those Governments’ Guidelines for Nuclear Transfers [fr

  19. Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2008-01-01

    The Agency has received a Note Verbale from the Permanent Mission of Brazil, dated 22 March 2007, in which it requests that the Agency circulate to all Member States a letter of 12 December 2006 from the Chairman of the Nuclear Suppliers Group, Ambassador Jose Artur Denot Medeiros, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [es

  20. Communication Received from the Permanent Mission of the Netherlands regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology

    International Nuclear Information System (INIS)

    2011-01-01

    The Agency has received a Note Verbale from the Permanent Mission of the Kingdom of the Netherlands, dated 12 July 2011, in which it requests that the Agency circulate to all Member States a letter of 12 July 2011 from the Chairman of the Nuclear Suppliers Group, Ambassador Piet de Klerk, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers