WorldWideScience

Sample records for nuclear plant applications

  1. Fiber optic applications in nuclear power plants

    International Nuclear Information System (INIS)

    Collette, P.; Kwapien, D.

    1984-01-01

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

  2. Wireless Technology Application to Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Jeong Kweon; Jeong, See Chae; Jeong, Ki Hoon; Oh, Do Young; Kim, Jae Hack

    2009-01-01

    Wireless technologies are getting widely used in various industrial processes for equipment condition monitoring, process measurement and other applications. In case of Nuclear Power Plant (NPP), it is required to review applicability of the wireless technologies for maintaining plant reliability, preventing equipment failure, and reducing operation and maintenance costs. Remote sensors, mobile technology and two-way radio communication may satisfy these needs. The application of the state of the art wireless technologies in NPPs has been restricted because of the vulnerability for the Electromagnetic Interference and Radio Frequency Interference (EMI/RFI) and cyber security. It is expected that the wireless technologies can be applied to the nuclear industry after resolving these issues which most of the developers and vendors are aware of. This paper presents an overview and information on general wireless deployment in nuclear facilities for future application. It also introduces typical wireless plant monitoring system application in the existing NPPs

  3. Nuclear plant analyzer development and analysis applications

    International Nuclear Information System (INIS)

    Laats, E.T.

    1984-10-01

    The Nuclear Plant Analyzer (NPA) is being developed as the US Nuclear Regulatory Commission's (NRC's) state of the art safety analysis and engineering tool to address key nuclear plant safety issues. This paper describes four applications of the NPA in assisting reactor safety analyses. Two analyses evaluated reactor operating procedures, during off-normal operation, for a pressurized water reactor (PWR) and a boiling water reactor (BWR), respectively. The third analysis was performed in support of a reactor safety experiment conducted in the Semiscale facility. The final application demonstrated the usefulness of atmospheric dispersion computer codes for site emergency planning purposes. An overview of the NPA and how it supported these analyses are the topics of this paper

  4. Nuclear plant analyzer development and analysis applications

    International Nuclear Information System (INIS)

    Laats, E.T.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is being developed as the U.S. Nuclear Regulatory Commission's (NRC's) state of the art safety analysis and engineering tool to address key nuclear plant safety issues. The NPA integrates the NRC's computerized reactor behavior simulation codes such as RELAP5 and TRAC-BWR, both of which are well-developed computer graphics programs, and large repositories of reactor design and experimental data. Utilizing the complex reactor behavior codes as well as the experiment data repositories enables simulation applications of the NPA that are generally not possible with more simplistic, less mechanistic reactor behavior codes. These latter codes are used in training simulators or with other NPA-type software packages and are limited to displaying calculated data only. This paper describes four applications of the NPA in assisting reactor safety analyses. Two analyses evaluated reactor operating procedures, during off-normal operation, for a pressurized water reactor (PWR) and a boiling water reactor (BWR), respectively. The third analysis was performed in support of a reactor safety experiment conducted in the Semiscale facility. The final application demonstrated the usefulness of atmospheric dispersion computer codes for site emergency planning purposes. An overview of the NPA and how it supported these analyses are the topics of this paper

  5. Application of fieldbus techniques in nuclear power plants

    International Nuclear Information System (INIS)

    Wang Xu; Chen Hang; Yu Shuxin; Zhang Xinli

    2012-01-01

    The successful application experience of fieldbus techniques in thermal power plants and nuclear power plants are outlined first. And then, the application of fieldbus techniques in domestic 3rd-generation nuclear power plant (NPP) project is discussed. After that, the solution to the potential problems of fieldbus techniques application in NPP is provided. (authors)

  6. Applications of lasers in nuclear power plants

    International Nuclear Information System (INIS)

    Raj, Rupam; Sanyal, D.N.; Sil, Jaydeb

    2013-01-01

    Applications of lasers in nuclear power plants: Bellow lip cutting and high pressure feeder coupling stud (HPFC) cutting during en-masse coolant channel replacement (EMCCR) campaign at Narora Atomic Power Station Reactor 1 in May 2006; cutting of pressure tubes from Madras Atomic Power Station 1 (MAPS-1) for easy storage in April 2005; In-situ cutting of selected coolant channel S-7 at Kakrapar Atomic Power Station (KAPS-2) (cutting of 12 mm thick end fitting and 4 mm thick liner tube of stainless steel from inside) in January 2005; Development of a miniature cutting mechanism for steam generator tubes (14 mm i.d.) from inside, In-situ bellow repair for secondary shutdown system; LASER welding may be deployed for End shield of MAPS-1 leak repair

  7. A study on expert system applications for nuclear power plant

    International Nuclear Information System (INIS)

    Huh, Young Hwan; Kim, Yeong Jin; Park, Nam Seog; Dong, In Sook; Choi, In Seon

    1987-12-01

    The application of artificial intelligence techniques to nuclear power plants such as expert systems is rapidly emerging. expert systems can contribute significantly to the availability and the improved operation and safety of nuclear power plants. The objective of the project is to develop an expert system in a selected application area in the nuclear power plants. This project will last for 3 years. The first year's tasks are: - Information collection and literature survey on expert systems. - Analysis of several applicable areas for applying AI technologies to the nuclear power plants. - Conceptual design of a few selected domains. - Selection of hardware and software tools for the development of the expert system

  8. Laser applications in nuclear power plants

    Indian Academy of Sciences (India)

    2014-01-09

    Jan 9, 2014 ... we have used laser techniques to cut stainless steel sheets up to 14 mm thickness and stainless steel weld up to ... radioactive environment, reasons being easiness in tool handling, flexibility, non-contact nature ... in nuclear power plants of NPCIL, India, by invoking different innovative techniques. Figure 1.

  9. Neutral networks and their application in nuclear power plants

    International Nuclear Information System (INIS)

    Zhao Fuyu; Li Tiejun; Liao Zhongyue

    1994-01-01

    The neutral theory has been applied to various fields and many achievements have been obtained in many aspects, and the theory has also applied to nuclear engineering. In this paper, a few patterns of neutral networks and application in nuclear power plant is surveyed so as to bring the researching direction to nuclear work's attention at home

  10. Application of analysis technology in nuclear plant

    International Nuclear Information System (INIS)

    Takaoka, Keiko; Miura, Hiromi; Umeda, Kenji

    1996-01-01

    Recently, thanks to the rapid improvement of EWS performance, the authors have been able to carry out design evaluation comparatively, easily, utilizing computational fluid dynamics (CFD) technology. The Nuclear Plant Engineering Department has carried out some analyses in the past several years with the main purpose of evaluating the design of nuclear reactor internals. These studies included ''Thermal Hydraulic Analysis for Top Plenum'' and ''Flow Analysis for Lower Plenum''. It is considered to be a special matter in thermal hydraulic analysis of the top plenum that temperature distribution has been estimated with a relatively small number of meshes by means of an imaginary spray nozzle, and in the flow analysis for the lower plenum that flow distribution has been found to change largely, depending on the reactor internals. One of the ways to confirm the safety of nuclear plants, detailed structural analysis, is required for all possible combinations of transient and load conditions during operation. In particular, it is very important to clarify the thermal stress behavior under operating conditions and to evaluate fatigue analysis in accordance with the Code Requirements. However, it is very complicated and it takes a lot of time. A new system was developed which can operate continuously all of the definitions of the analytical model, the analyzation of pressurized thermal and external stress, and editing reports. In this paper, the authors introduce this system and apply it to a pressurized water reactor

  11. The application of plant information system on third Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Liu Wangtian

    2005-01-01

    Plant overall control has been applied in Qinshan Nuclear Power Plant, which enhances the security of plant operation, but it is not enough to improve the technical administration level. In order to integrate the overall information and to improve the technical administration level more. Third Qinshan Nuclear Power Plant applies the plant information system. This thesis introduces the application of plant information system in Third Qinshan Nuclear Power Plant and the effect to the plant after the system is carried into execution, in addition, it does more analysis and exceptions for application of plant information system in the future. (authors)

  12. Application of digital control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Keiper, J.T.

    1993-01-01

    This paper describes a sampling of recent digital applications, both safety related and non-safety related, in four nuclear power plants and discusses a few of the unique application experiences. Each application accrues unique benefits, but also poses unique problems. A few of the benefits and problems are discussed

  13. Internet applications in nuclear power plant operation management

    International Nuclear Information System (INIS)

    Munoz, M.

    2000-01-01

    The use of the Internet is quickly becoming widespread in practically all areas of business and industry. The nuclear industry should not remain indifferent to this new trend. This paper analyses some of the Internet applications that can be easily adapted to nuclear power plant operation management, including. (Author)

  14. Topics for application of expert systems for nuclear power plants

    International Nuclear Information System (INIS)

    Trovato, S.A.; Aydin, F.

    1992-01-01

    Expert systems are an innovative form of computer software which offer to enhance productivity and improve operations of nuclear power plants. A survey and assessment of opportunities for application of this technology at Consolidated Edison Company of New York, Inc.'s (Con Edison) Indian Point 2 nuclear power plant was conducted. Eleven topics for expert systems are discussed in this paper. 1 ref., 2 figs., 2 tabs

  15. Hierarchical structure for risk criteria applicable to nuclear power plants

    International Nuclear Information System (INIS)

    Hall, R.E.; Mitra, S.P.

    1985-01-01

    This paper discusses the development of a hierarchical structure for risk criteria applicable to nuclear power plants. The structure provides a unified framework to systematically analyze the implications of different types of criteria, each focusing on a particular aspect of nuclear power plant risks. The framework allows investigation of the specific coverage of a particular criterion and comparison of different criteria with regard to areas to which they apply. 5 refs., 2 figs

  16. Digital nuclear instrumentation application to nuclear power plant

    International Nuclear Information System (INIS)

    Burel, J.-P.; Fanet, H.

    1993-01-01

    The use of digital techniques for the control of nuclear reactors offers an interesting prospect in the improvement of the operation and safety of reactors. Thanks to close collaboration between Merlin Gerin and the French Atomic Energy Commission, a new piece of technology for nuclear instrumentation systems has been developed in order to meet the needs of different types of reactors. The principles of measurement are presented and the technology used is described. Other interesting points of this technology in addition to installation, operation and safety are examined. The digital neutron measurements are already operating in research reactors in France and will be installed in a different configuration in the new 1400 MW nuclear power plant. Integration into different designs is easily attainable by adapting the information transmission mode according to the technology present in the protection system and the treatment and visualization systems. (author)

  17. Laser applications in nuclear power plants

    Indian Academy of Sciences (India)

    2014-01-09

    Jan 9, 2014 ... Keywords. Nd:YAG laser; fibre-optic beam delivery; laser cutting; laser welding; nuclear reactor. ... Author Affiliations. D N Sanyal1. Remote Tooling Section, Technology Development Group, Nuclear Power Corporation of India Ltd., Mumbai 400 094, India ...

  18. Potential applications of neural networks to nuclear power plants

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1991-01-01

    Application of neural networks to the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: diagnosing specific abnormal conditions, detection of the change of mode of operation, signal validation, monitoring of check valves, plant-wide monitoring using autoassociative neural networks, modeling of the plant thermodynamics, emulation of core reload calculations, monitoring of plant parameters, and analysis of plant vibrations. Each of these projects and its status are described briefly in this article. The objective of each of these projects is to enhance the safety and performance of nuclear plants through the use of neural networks

  19. Russian nuclear power plants for marine applications

    Energy Technology Data Exchange (ETDEWEB)

    Reistad, O. [Norwegian Radiation Protection Authority (Norway); Oelgaard, P.L. [Risoe National Lab. (Denmark)

    2006-04-15

    In order to establish a systematic approach for future proliferation and environmental analyses of Russia's marine nuclear reactor systems, this paper summarizes and analyzes the available open-source information on the design properties of reactor systems and nuclear fuels. The most distinctive features of Russian marine reactor development are pointed out, and similarities and differences between Russian military and civilian reactor systems and fuel are discussed. Relevant updated information on all Russian vessels using nuclear propulsion is presented in Annex I. The basic analytic division in this paper follows vessel generations first to third generation; and reactor types PWR and LMC technology. Most of the available information is related to nuclear icebreakers. This information is systematically analyzed in order to identify stages in the development of Russia's civilian naval nuclear reactors. Three different reactor models are discussed: OK-150, OK-900 and KLT-40, together with several versions of these. Concerning military reactors, it is not possible to identify characteristics for the individual reactor models, so the basic division follows vessel generations first to third generation. From the information available, however, it is possible to identify the main lines along which the design of submarines of especially the first and the second generation has been made. The conclusions contain a discussion of possible implications of the results, in addition to suggestions for further work. (au)

  20. Russian nuclear power plants for marine applications

    International Nuclear Information System (INIS)

    Reistad, O.; Oelgaard, P.L.

    2006-04-01

    In order to establish a systematic approach for future proliferation and environmental analyses of Russia's marine nuclear reactor systems, this paper summarizes and analyzes the available open-source information on the design properties of reactor systems and nuclear fuels. The most distinctive features of Russian marine reactor development are pointed out, and similarities and differences between Russian military and civilian reactor systems and fuel are discussed. Relevant updated information on all Russian vessels using nuclear propulsion is presented in Annex I. The basic analytic division in this paper follows vessel generations first to third generation; and reactor types PWR and LMC technology. Most of the available information is related to nuclear icebreakers. This information is systematically analyzed in order to identify stages in the development of Russia's civilian naval nuclear reactors. Three different reactor models are discussed: OK-150, OK-900 and KLT-40, together with several versions of these. Concerning military reactors, it is not possible to identify characteristics for the individual reactor models, so the basic division follows vessel generations first to third generation. From the information available, however, it is possible to identify the main lines along which the design of submarines of especially the first and the second generation has been made. The conclusions contain a discussion of possible implications of the results, in addition to suggestions for further work. (au)

  1. Application of AI technology to nuclear plant operations

    International Nuclear Information System (INIS)

    Sackett, J.I.

    1988-01-01

    In this paper, applications of Artificial Intelligence (AI) Technology to nuclear-power plant operation are reviewed. AI Technology is advancing rapidly and in the next five years is expected to enjoy widespread application to operation, maintenance, management and safety. Near term emphasis on a sensor validation, scheduling, alarm handling, and expert systems for procedural assistance. Ultimate applications are envisioned to culminate in autonomous control such as would be necessary for a power system in space, where automatic control actions are taken based upon reasoned conclusions regarding plant conditions, capability and control objectives

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

    International Nuclear Information System (INIS)

    Reifman, J.

    1997-01-01

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

  3. Green County Nuclear Power Plant. License application

    International Nuclear Information System (INIS)

    1975-07-01

    The Green County reactor, a PWR to be supplied by Babcock and Wilcox, will be a baseload generating facility planned to provide for mass transit and other public agency electrical needs. The plant is scheduled for completion by 1983 and will have a generating capacity of about 1200 MW(e). (FS)

  4. 78 FR 37324 - Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications

    Science.gov (United States)

    2013-06-20

    ... Environmental Reports for Nuclear Power Plant License Renewal Applications AGENCY: Nuclear Regulatory Commission... for Nuclear Power Plant License Renewal Applications.'' This regulatory guide provides guidance to... renewal of a nuclear power plant operating license. Applicants should use this regulatory guide when...

  5. Application of 3-dimensional CAD modeling system in nuclear plants

    International Nuclear Information System (INIS)

    Suwa, Minoru; Saito, Shunji; Nobuhiro, Minoru

    1990-01-01

    Until now, the preliminary work for mutual components in nuclear plant were readied by using plastic models. Recently with the development of computer graphic techniques, we can display the components on the graphics terminal, better than with use of plastic model and actual plants. The computer model can be handled, both telescopically and microscopically. A computer technique called 3-dimensional CAD modeling system was used as the preliminary work and design system. Through application of this system, database for nuclear plants was completed in arrangement step. The data can be used for piping design, stress analysis, shop production, testing and site construction, in all steps. In addition, the data can be used for various planning works, even after starting operation of plant. This paper describes the outline of the 3-dimensional CAD modeling system. (author)

  6. Application of condition based maintenance to nuclear power plants

    International Nuclear Information System (INIS)

    Sonoda, Yukio; Nakano, Tomohito; Shimizu, Shunichi; Iida, Jun; Atomura, Masakazu; Abe, Masahiro

    2002-01-01

    Device Karte management system which supports application of condition based maintenance to nuclear power plants has been developed. The purpose of this system is to support maintenance personnel in device inspection scheduling based on operating condition monitoring and maintenance histories. There are four functions: field database, degradation estimation, inspection time decision and maintenance planning. The authors have been applying this system to dozens of devices of Onagawa Nuclear Power Station Unit No. 1 for one year. This paper represents the system concept and its application experiences. (author)

  7. Application perspectives of simulation techniques CFD in nuclear power plants

    International Nuclear Information System (INIS)

    Galindo G, I. F.

    2013-10-01

    The scenarios simulation in nuclear power plants is usually carried out with system codes that are based on concentrated parameters networks. However situations exist in some components where the flow is predominantly 3-D, as they are the natural circulation, mixed and stratification phenomena. The simulation techniques of computational fluid dynamics (CFD) have the potential to simulate these flows numerically. The use of CFD simulations embraces many branches of the engineering and continues growing, however, in relation to its application with respect to the problems related with the safety in nuclear power plants, has a smaller development, although is accelerating quickly and is expected that in the future they play a more emphasized paper in the analyses. A main obstacle to be able to achieve a general acceptance of the CFD is that the simulations should have very complete validation studies, sometimes not available. In this article a general panorama of the state of the methods application CFD in nuclear power plants is presented and the problem associated to its routine application and acceptance, including the view point of the regulatory authorities. Application examples are revised in those that the CFD offers real benefits and are also presented two illustrative study cases of the application of CFD techniques. The case of a water recipient with a heat source in its interior, similar to spent fuel pool of a nuclear power plant is presented firstly; and later the case of the Boron dilution of a water volume that enters to a nuclear reactor is presented. We can conclude that the CFD technology represents a very important opportunity to improve the phenomena understanding with a strong component 3-D and to contribute in the uncertainty reduction. (Author)

  8. Applications of wavelet transforms for nuclear power plant signal analysis

    International Nuclear Information System (INIS)

    Seker, S.; Turkcan, E.; Upadhyaya, B.R.; Erbay, A.S.

    1998-01-01

    The safety of Nuclear Power Plants (NPPs) may be enhanced by the timely processing of information derived from multiple process signals from NPPs. The most widely used technique in signal analysis applications is the Fourier transform in the frequency domain to generate power spectral densities (PSD). However, the Fourier transform is global in nature and will obscure any non-stationary signal feature. Lately, a powerful technique called the Wavelet Transform, has been developed. This transform uses certain basis functions for representing the data in an effective manner, with capability for sub-band analysis and providing time-frequency localization as needed. This paper presents a brief overview of wavelets applied to the nuclear industry for signal processing and plant monitoring. The basic theory of Wavelets is also summarized. In order to illustrate the application of wavelet transforms data were acquired from the operating nuclear power plant Borssele in the Netherlands. The experimental data consist of various signals in the power plant and are selected from a stationary power operation. Their frequency characteristics and the mutual relations were investigated using MATLAB signal processing and wavelet toolbox for computing their PSDs and coherence functions by multi-resolution analysis. The results indicate that the sub-band PSD matches with the original signal PSD and enhances the estimation of coherence functions. The Wavelet analysis demonstrates the feasibility of application to stationary signals to provide better estimates in the frequency band of interest as compared to the classical FFT approach. (author)

  9. Innovative applications of technology for nuclear power plant productivity improvements

    International Nuclear Information System (INIS)

    Naser, J. A.

    2012-01-01

    The nuclear power industry in several countries is concerned about the ability to maintain high plant performance levels due to aging and obsolescence, knowledge drain, fewer plant staff, and new requirements and commitments. Current plant operations are labor-intensive due to the vast number of operational and support activities required by commonly used technology in most plants. These concerns increase as plants extend their operating life. In addition, there is the goal to further improve performance while reducing human errors and increasingly focus on reducing operations and maintenance costs. New plants are expected to perform more productively than current plants. In order to achieve and increase high productivity, it is necessary to look at innovative applications of modern technologies and new concepts of operation. The Electric Power Research Inst. is exploring and demonstrating modern technologies that enable cost-effectively maintaining current performance levels and shifts to even higher performance levels, as well as provide tools for high performance in new plants. Several modern technologies being explored can provide multiple benefits for a wide range of applications. Examples of these technologies include simulation, visualization, automation, human cognitive engineering, and information and communications technologies. Some applications using modern technologies are described. (authors)

  10. Application of ceramic and glass materials in nuclear power plants

    International Nuclear Information System (INIS)

    Hamnabard, Z.

    2008-01-01

    Ceramic and glass are high temperature materials that can be used in many fields of application in nuclear industries. First, it is known that nuclear fuel UO 2 is a ceramic material. Also, ability to absorb neutrons without forming long lived radio-nuclides make the non-oxide ceramics attractive as an absorbent for neutron radiation arising in nuclear power plants. Glass-ceramic materials are a new type of ceramic that produced by the controlled nucleation and crystallization of glass, and have several advantages such as very low or null porosity, uniformity of microstructure, high chemical resistance etc. over conventional powder processed ceramics. These ceramic materials are synthesized in different systems based on their properties and applications. In nuclear industries, those are resistant to leaching and radiation damage for thousands of years, Such as glass-ceramics designed for radioactive waste immobilization and machinable glass-ceramics are used. This article introduces requirements of different glass and ceramic materials used in nuclear power plants and have been focused on developments in properties and application of them

  11. Low-temperature nuclear heat applications: Nuclear power plants for district heating

    International Nuclear Information System (INIS)

    1987-08-01

    The IAEA reflected the needs of its Member States for the exchange of information in the field of nuclear heat application already in the late 1970s. In the early 1980s, some Member States showed their interest in the use of heat from electricity producing nuclear power plants and in the development of nuclear heating plants. Accordingly, a technical committee meeting with a workshop was organized in 1983 to review the status of nuclear heat application which confirmed both the progress made in this field and the renewed interest of Member States in an active exchange of information about this subject. In 1985 an Advisory Group summarized the Potential of Low-Temperature Nuclear Heat Application; the relevant Technical Document reviewing the situation in the IAEA's Member States was issued in 1986 (IAEA-TECDOC-397). Programme plans were made for 1986-88 and the IAEA was asked to promote the exchange of information, with specific emphasis on the design criteria, operating experience, safety requirements and specifications for heat-only reactors, co-generation plants and power plants adapted for heat application. Because of a growing interest of the IAEA's Member States about nuclear heat employment in the district heating domaine, an Advisory Group meeting was organized by the IAEA on ''Low-Temperature Nuclear Heat Application: Nuclear Power Plants for District Heating'' in Prague, Czechoslovakia in June 1986. The information gained up to 1986 and discussed during this meeting is embodied in the present Technical Document. 22 figs, 11 tabs

  12. Research on the application of optoelectronics to nuclear power plants

    International Nuclear Information System (INIS)

    Shirosaki, Hidekazu; Mitsuda, Hiromichi; Kurata, Toshikazu; Soramoto, Seiki; Maekawa, Tatsuyuki.

    1995-01-01

    Optoelectronics, which is based on technologies such as laser diodes and optical fibers, is approaching the realm of practical application in the fields of optical fiber communications and compact disks etc,. In addition, laser enrichment, a type of uranium enrichment technique used in the nuclear field, can also be regarded as a product of optoelectronics. Application of optoelectronics in a wide range of fields is likely to continue in the future, and research is being conducted on coherent optical communication, optical integrated circuits, optical computers and other subjects in hopes of attaining practical application of these technologies in the future. On the other hand, digital control equipment and other related devices have been installed and data transfer using optical fibers has been implemented on a partial basis at nuclear power plants, and optoelectronics is anticipated to be applied on an even broader scale in the future, thereby creating the potential for improving plant reliability. In this research, we conducted an investigative study of technologies relating to optoelectronics, and proposed a remote monitoring system for manually operated valves that employs optical switches. Moreover, we conducted theoretical verification tests on the proposed system and carried out a feasibility study relating to application to nuclear power plants. As a result, the proposed system was found to be effective, and confirmed to have the potential of realization as a valve switching monitoring system. (author)

  13. Practical application of computer graphics in nuclear power plant engineering

    International Nuclear Information System (INIS)

    Machiba, Hiroshi; Kawamura, Hirobumi; Sasaki, Norio

    1992-01-01

    A nuclear power plant is composed of a vast amount of equipment, piping, and so on, and six or seven years are required to complete the design and engineering from the initial planning stage to the time of commercial operation. Furthermore, operating plants must be continually maintained and improved for a long period. Computer graphics were first applied to the composite arrangement design of nuclear power plants in the form of 3-dimensional CAD. Subsequently, as the introduction of CAE has progressed, a huge assortment of information has been accumulated in database, and measures have been sought that would permit the convenient utilization of this information. Using computer graphics technologies, improvement of the interface between the user and such databases has recently been accomplished. In response to the growth in environmental consciousness, photo-realistic simulations for artistic design of the interior and overviews showing harmony with the surroundings have been achieved through the application of computer graphics. (author)

  14. 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

  15. Barnwell Nuclear Fuels Plant applicability study. Volume III. Appendices

    International Nuclear Information System (INIS)

    1978-03-01

    Volume III suppliees supporting information to assist Congress in making a decision on the optimum utilization of the Barnwell Nuclear Fuels Plant. Included are applicable fuel cycle policies; properties of reference fuels; description and evaluation of alternative operational (flue cycle) modes; description and evaluation of safeguards systems and techniques; description and evaluation of spiking technology; waste and waste solidification evaluation; and Department of Energy programs relating to nonproliferation

  16. Advanced applications of water cooled nuclear power plants

    International Nuclear Information System (INIS)

    2008-07-01

    By August 2007, there were 438 nuclear power plants (NPPs) in operation worldwide, with a total capacity of 371.7 GW(e). Further, 31 units, totaling 24.1 GW(e), were under construction. During 2006 nuclear power produced 2659.7 billion kWh of electricity, which was 15.2% of the world's total. The vast majority of these plants use water-cooled reactors. Based on information provided by its Member States, the IAEA projects that nuclear power will grow significantly, producing between 2760 and 2810 billion kWh annually by 2010, between 3120 and 3840 billion kWh annually by 2020, and between 3325 and 5040 billion kWh annually by 2030. There are several reasons for these rising expectations for nuclear power: - Nuclear power's lengthening experience and good performance: The industry now has more than 12 000 reactor years of experience, and the global average nuclear plant availability during 2006 reached 83%; - Growing energy needs: All forecasts project increases in world energy demand, especially as population and economic productivity grow. The strategies are country dependent, but usually involve a mix of energy sources; - Interest in advanced applications of nuclear energy, such as seawater desalination, steam for heavy oil recovery and heat and electricity for hydrogen production; - Environmental concerns and constraints: The Kyoto Protocol has been in force since February 2005, and for many countries (most OECD countries, the Russian Federation, the Baltics and some countries of the Former Soviet Union and Eastern Europe) greenhouse gas emission limits are imposed; - Security of energy supply is a national priority in essentially every country; and - Nuclear power is economically competitive and provides stability of electricity price. In the near term most new nuclear plants will be evolutionary water cooled reactors (Light Water Reactors (LWRs) and Heavy Water Reactors (HWRs), often pursuing economies of scale. In the longer term, innovative designs that

  17. Application of Modern Technologies for Nuclear Power Plant Productivity Improvements

    International Nuclear Information System (INIS)

    Joseph, A. Naser

    2011-01-01

    The nuclear power industry in several countries is concerned about the ability to maintain current high plant performance levels due to aging and obsolescence, knowledge drain, fewer plant staff, new requirements and commitments, unnecessary workloads and stress levels, and human errors. Current plant operations are labor-intensive due to the vast number of operational and support activities required by the commonly used technology in most plants. These concerns increase as plants extend their operating life. In addition, there is the desire by many plants to further improve performance while reducing human errors and increasingly focus on reducing operations and maintenance costs. New productivity improvement capabilities with measurable economic benefits are needed so that a successful business case can be made for their use. Improved and new instrumentation and control, human-system interface, information and communications technologies used properly can address concerns about cost-effectively maintaining current performance levels and enable shifts to even higher performance levels. This can be accomplished through the use of new technology implementations to improve productivity, reduce costs of systemic inefficiencies and avoid unexpected costs. Many of the same type of productivity improvements for operating plants will be applicable for new plants. As new plants are being built, it is important to include these productivity improvements or at least provide the ability to implement them easily later

  18. Neural networks and their potential application to nuclear power plants

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1991-01-01

    A network of artificial neurons, usually called an artificial neural network is a data processing system consisting of a number of highly interconnected processing elements in an architecture inspired by the structure of the cerebral cortex portion of the brain. Hence, neural networks are often capable of doing things which humans or animals do well but which conventional computers often do poorly. Neural networks exhibit characteristics and capabilities not provided by any other technology. Neural networks may be designed so as to classify an input pattern as one of several predefined types or to create, as needed, categories or classes of system states which can be interpreted by a human operator. Neural networks have the ability to recognize patterns, even when the information comprising these patterns is noisy, sparse, or incomplete. Thus, systems of artificial neural networks show great promise for use in environments in which robust, fault-tolerant pattern recognition is necessary in a real-time mode, and in which the incoming data may be distorted or noisy. The application of neural networks, a rapidly evolving technology used extensively in defense applications, alone or in conjunction with other advanced technologies, to some of the problems of operating nuclear power plants has the potential to enhance the safety, reliability and operability of nuclear power plants. The potential applications of neural networking include, but are not limited to diagnosing specific abnormal conditions, identification of nonlinear dynamics and transients, detection of the change of mode of operation, control of temperature and pressure during start-up, signal validation, plant-wide monitoring using autoassociative neural networks, monitoring of check valves, modeling of the plant thermodynamics, emulation of core reload calculations, analysis of temporal sequences in NRC's ''licensee event reports,'' and monitoring of plant parameters

  19. Fiber optic sensors for nuclear power plant applications

    Energy Technology Data Exchange (ETDEWEB)

    Kasinathan, Murugesan; Sosamma, Samuel; BabuRao, Chelamchala; Murali, Nagarajan; Jayakumar, Tammana [Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu-603102 (India)

    2012-05-17

    Studies have been carried out for application of Raman Distributed Temperature Sensor (RDTS) in Nuclear Power Plants (NPP). The high temperature monitoring in sodium circuits of Fast Breeder Reactor (FBR) is important. It is demonstrated that RDTS can be usefully employed in monitoring sodium circuits and in tracking the percolating sodium in the surrounding insulation in case of any leak. Aluminum Conductor Steel Reinforced (ACSR) cable is commonly used as overhead power transmission cable in power grid. The suitability of RDTS for detecting defects in ACSR overhead power cable, is also demonstrated.

  20. The application of manipulator robot for nuclear power plant maintenance

    International Nuclear Information System (INIS)

    Fujita, Jun; Onishi, Ken

    2009-01-01

    In the maintenance works at nuclear power plant, robots are used because of high radiation, narrow space and underwater work. In light of manufacture period, cost and reliability, various maintenance works are requested to be done by one robot. As one of the solutions, we developed manipulator robots for the access of specialized tools. This study shows manipulator robots developed by MHI, application example to maintenance works and effectiveness of manipulator robots. When robotization of maintenance works are considered, manipulator technology is very effective solution means. The manipulator technologies in this study are able to apply to robotization needed under radiation environment. (author)

  1. The application of manipulator robot for nuclear plant maintenance

    International Nuclear Information System (INIS)

    Kohata, Yukifumi; Fujita, Jun; Onishi, Ken; Tsuhari, Hiroyuki; Hosoe, Fumihiro

    2010-01-01

    In the maintenance works at nuclear power plant, robots are used because of high radiation, narrow space and underwater work. Various robots are needed because there is various maintenance works. This is inefficiency. As the solutions, we developed manipulator robots for the access of specialized tools. This study shows manipulator robots developed by MHI, application example to maintenance works and effectiveness of manipulator robots. When robotization of maintenance works are considered, manipulator technology is very effective solution means. We achieved efficiency improvement and the reliability improvement by developing a high generality manipulator. (author)

  2. Application of meteorology to safety at nuclear plants

    International Nuclear Information System (INIS)

    1968-01-01

    This report was prepared on behalf of the International Atomic Energy Agency by an international panel of experts who met at the Agency's headquarters from 10 to 14 April 1967. The application of meteorology to safety at nuclear plants is discussed in connection with site selection, design and construction, operation, and emergency planning and action. The final chapter considers the training to be given to operators and health and safety personnel on meteorology problems. The appendix gives a simple method for computing air concentration values at ground level. An extensive bibliography is also included.

  3. Six sigma management and its application in nuclear power plant

    International Nuclear Information System (INIS)

    Liu Weihua; Tong Lili

    2007-01-01

    Six sigma management mode is presented. The feasibility, necessity and the steps to extend six sigma in nuclear power plant are addressed. Nuclear power plant can eliminate or decrease human errors through importing six management concept, the 'zero disfigurement' quality and operation can achieved, decreasing accident risk and realizing safety operation. (authors)

  4. Application of ABWR construction database to nuclear power plant project

    International Nuclear Information System (INIS)

    Takashima, Atsushi; Katsube, Yasuhiko

    1999-01-01

    Tokyo Electric Power Company (TEPCO) completed the construction of Kashiwazaki-Kariwa Nuclear Power Station Unit No. 6 and No. 7 (K-6/7) as the first advanced boiling water reactors (ABWR) in the world successfully. K-6 and K-7 started their commercial operations in November, 1996 and in July, 1997 respectively. We consider ABWR as a standard BWR in the world as well as in Japan because ABWR is highly reputed. However, because the interval of our nuclear power plant construction is going to be longer, our engineering level on plant construction will be declining. Hence it is necessary for us to maintain our engineering level. In addition to this circumstance, we are planning to wide application of separated purchase orders for further cost reduction. Also there is an expectation for our contribution to ABWR plant constructions overseas. As facing these circumstances, we have developed a construction database based on our experience for ABWR construction. As the first step of developing the database for these use, we analyzed our own activities in the previous ABWR construction. Through this analysis, we could define activity units of which the project consists. As the second step, we clarified the data which are treated in each activity unit and the interface among them. By taking these steps, we could develop our database efficiently. (author)

  5. Research on artificial neural network applications for nuclear power plants

    International Nuclear Information System (INIS)

    Chang, Soon-Heung; Cheon, Se-Woo

    1992-01-01

    Artificial neural networks (ANNs) are an emerging computational technology which can significantly enhance a number of applications. These consist of many interconnected processing elements that exhibit human-like performance, i.e., learning, pattern recognition and associative memory skills. Several application studies on ANNs devoted to nuclear power plants have been carried out at the Korea Advanced Institute of Science and Technology since 1989. These studies include the feasibility of using ANNs for the following tasks: (1) thermal power prediction, (2) transient identification, (3) multiple alarm processing and diagnosis, (4) core thermal margin prediction, and (5) prediction of core parameters for fuel reloading. This paper introduces the back-propagation network (BPN) model which is the most commonly used algorithm, and summarizes each of the studies briefly. (author)

  6. Neural networks and their potential application in nuclear power plants

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1991-01-01

    A neural network is a data processing system consisting of a number of simple, highly interconnected processing elements in an architecture inspired by the structure of the cerebral cortex portion of the brain. Hence, neural networks are often capable of doing things which humans or animals do well but which conventional computers often do poorly. Neural networks have emerged in the past few years as an area of unusual opportunity for research, development and application to a variety of real world problems. Indeed, neural networks exhibit characteristics and capabilities not provided by any other technology. Examples include reading Japanese Kanji characters and human handwriting, reading a typewritten manuscript aloud, compensating for alignment errors in robots, interpreting very noise signals (e.g., electroencephalograms), modeling complex systems that cannot be modeled mathematically, and predicting whether proposed loans will be good or fail. This paper presents a brief tutorial on neural networks and describes research on the potential applications to nuclear power plants

  7. Applications of modern control systems in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Wilhelm, H [Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.). Abt. GK/TE

    1980-10-01

    A new generation of automation and control systems are currently becoming commercially available in the power plant market which, because of their incorporation of microprocessors and bus data transmission systems, represent a major step forward in innovation. The application of these systems meets today's requirements and solutions, for the number of measurements to be performed has increased five or sixfold in the past few years, and the number of drive systems to be controlled has doubled or even tripled. Requirements to be met by process management systems have become vastly more complicated: peak load operation, short startup times, improved communication, and rising safety and reliability requirements, especially in nuclear power plants. Control concepts have been developed for the area relevant to reactor safety and for the whole of the plant, which make full use of the possibilities offered by plant systems. More stringent demands must be met especially in the areas of handling, communication, testing capability, improved function, and flexibility and modular design in the safety sector.

  8. Applications of modern control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Wilhelm, H.

    1980-01-01

    A new generation of automation and control systems are currently becoming commercially available in the power plant market which, because of their incorporation of microprocessors and bus data transmission systems, represent a major step forward in innovation. The application of these systems meets today's requirements and solutions, for the number of measurements to be performed has increased five or sixfold in the past few years, and the number of drive systems to be controlled has doubled or even tripled. Requirements to be met by process management systems have become vastly more complicated: peak load operation, short startup times, improved communication, and rising safety and reliability requirements, especially in nuclear power plants. Control concepts have been developed for the area relevant to reactor safety and for the whole of the plant, which make full use of the possibilities offered by plant systems. More stringent demands must be met especially in the areas of handling, communication, testing capability, improved function, and flexibility and modular design in the safety sector. (orig.) [de

  9. A study on the development and application of expert system for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    It is a final report of the research that is a study on the development and application of expert system for nuclear power plants and development of the schemes computing environments and user interfaces for the expert system, which is a systematic and efficient development of expert system for nuclear power plants in the future. This report is consisted of -Development trends of expert system for nuclear power plants. -Classification of expert system applications for nuclear power plants. -Systematic and efficient developments schemes of expert system for nuclear power plants, and -Suitable computing environments and user interfaces for the expert systems. (author). 113 refs., 85 figs.

  10. A study on the development and application of expert system for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-12-31

    It is a final report of the research that is a study on the development and application of expert system for nuclear power plants and development of the schemes computing environments and user interfaces for the expert system, which is a systematic and efficient development of expert system for nuclear power plants in the future. This report is consisted of -Development trends of expert system for nuclear power plants. -Classification of expert system applications for nuclear power plants. -Systematic and efficient developments schemes of expert system for nuclear power plants, and -Suitable computing environments and user interfaces for the expert systems. (author). 113 refs., 85 figs.

  11. 76 FR 81994 - UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit...

    Science.gov (United States)

    2011-12-29

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit 3; Exemption 1.0 Background: UniStar Nuclear Energy (UNE) submitted to the U.S. Nuclear Regulatory Commission (NRC or the Commission ) a...

  12. Application of virtual reality to simulation in nuclear power plant

    International Nuclear Information System (INIS)

    Liu Pengfei; Yang Yanhua; Yang Yongmu; Duan Dongdong; Luo Jie

    2008-01-01

    Based on detailed analysis of the structure and key techniques of a virtual reality system, the applications of virtual reality to simulation in nuclear power plant (NPP) were developed. In order to meet the requirement of simulation in NPP, motion simulation of control rod drive system, walking system inside the containment and virtual main control room were presented. A simulator of NPP was connected to interchange dynamic data between virtual main control room and the simulator. The simulating results show that the technique of virtual reality can be applied well to the simulation inside containment, which is filled with activity material, and the simulation of virtual main control room, where human factors must be considered. It also can be used well to design virtual education and training system of NPP. (authors)

  13. Application of microearthquake surveys in nuclear power plant siting

    International Nuclear Information System (INIS)

    1985-06-01

    Earthquakes of magnitude less than 3 are generally referred to as microearthquakes. After an overview of the use of microearthquake survey in decisions related to the siting of nuclear power plants, the main aspects of a microearthquake survey network are discussed. The use of microearthquake surveys in investigating problems related to near-field (floating) earthquakes is also discussed. The discussion is centered on the practical application of such a survey leading from objectives and limitations over to planning, instrumentation, operation, maintenance, processing of the data, and interpretation and reporting of the results. An appendix entitled Earthquake Magnitude gives useful background information for definitions of different types of magnitude and their calculation using the records from microearthquake surveys

  14. Application of fatigue monitoring system in PWR nuclear power plant

    International Nuclear Information System (INIS)

    Piao Lei

    2014-01-01

    Fatigue failure is one form of equipment failure of nuclear power plant, influencing equipment lifetime and lifetime extension. Fatigue monitoring system can track real thermal transient at fatigue sensitive components, establish a basis for fatigue analyses based on realistic operating loads, identify unexpected operational transients, optimize the plant behavior by improved operating modes, provide supporting data for lifetime management, enhance security of plant and reduce economical loss. Fatigue monitoring system has been applied in many plants and is required to be applied in Generation-III nuclear power plant. It is necessary to develop the fatigue monitoring system with independent intellectual property rights and improve the competitiveness of domestic Generation-III nuclear power technology. (author)

  15. The application of availability analysis to nuclear power plants

    International Nuclear Information System (INIS)

    Brooks, A.C.

    1984-01-01

    The use of probabilistic risk analysis (PRA) to assess the risks from nuclear power plants is now well established. Considerably less attention has been given so far to the use of availability analysis techniques. The economics of power generation are now such that with nuclear power currently supplying a substantial fraction of power in many countries, increasing attention is being paid to improving plant availability. This paper presents a technique for systematically identifying the areas in which measures to improve plant availability will be most effective. (author)

  16. Application of robotic systems to nuclear power plant maintenance tasks

    International Nuclear Information System (INIS)

    Kok, K.D.; Bartilson, B.M.; Rosen, K.L.; Renner, G.F.; Law, T.M.

    1984-01-01

    Robotics technology has developed to where it can provide consistent performance of well-defined tasks. Although nuclear power plant maintenance tasks are characteristically unique, there are some common subtasks which have the consistency required for robots. Several maintenance activities were selected for further study. Concepts for robotic devices and rough scenarios for their use were developed and analyzed for their effect on maintenance costs. The results of the analysis, which was performed using a 10-year life and conservative estimates and procedures, indicate cost savings ranging from $100,000 to $1.5 M in net present value per robot. Projected purchase prices for the robots were less than $200,000. Although the robot concepts used commercially available technology, they are unlike any products either in use or widely required. Robot manufacturers are concentrating on mainstream applications in production, and are unlikely to develop such specialized products. The potential for cost savings indicates that developments should be funded by the nuclear industry

  17. Barnwell Nuclear Fuels Plant applicability study. Executive summary

    International Nuclear Information System (INIS)

    1978-04-01

    A study was conducted of the Barnwell Nuclear Fuels Plant in South Carolina to determine if that facility can be utilized in support of the nonproliferation objectives of the United States; and for activities contributing to the International Nuclear Fuel Cycle Evaluation to be carried out under contract at the Barnwell plant. One of the conclusions of this study is that there is nothing to support modification of the Presidential decision that the BNFP receive neither Federal encouragement nor funding for its completion on a reprocessing facility

  18. Modular robotic applications in nuclear power plant maintenance

    International Nuclear Information System (INIS)

    Glass, S.W.; Ranson, C.C.; Reinholtz, C.F.; Calkins, J.M.

    1996-01-01

    General-purpose factory automation robots have experienced limited use in nuclear maintenance and hazardous-environment work spaces due to demanding requirements on size, weight, mobility and adaptability. Robotic systems in nuclear power plants are frequently custom designed to meet specific space and performance requirements. Examples of these custom configurations include Framatome Technologies COBRA trademark Steam Generator Manipulator and URSULA trademark Reactor Vessel Inspection Manipulator. The use of custom robots in nuclear plants has been limited because of the lead time and expense associated with custom design. Developments in modular robotics and advanced robot control software coupled with more powerful low-cost computers, however, are helping to reduce the cost and schedule for deploying custom robots. A modular robotic system allows custom robot configurations to be implemented using standard (modular) joints and adaptable controllers. This paper discusses Framatome Technologies (FTI) current and planned developments in the area of modular robot system design

  19. Application of Pressure Equipment Standard at nuclear power plants; Aplicacion del Reglamento de Equipos a Presion a las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

    Regarding with the paper presented on 9{sup t}h June 2011 referred to the Industrial Security standard in Nuclear Plants, it was about the application of Pressure Equipment standard to mentioned Nuclear Plants, this article is an extract of the paper going to be exposed. (Author)

  20. 76 FR 81992 - PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant; Exemption

    Science.gov (United States)

    2011-12-29

    ... License Application for Bell Bend Nuclear Power Plant; Exemption 1.0 Background PPL Bell Bend, LLC... for Nuclear Power Plants.'' This reactor is to be identified as Bell Bend Nuclear Power Plant (BBNPP... based upon the U.S. EPR reference COL (RCOL) application for UniStar's Calvert Cliffs Nuclear Power...

  1. 76 FR 46330 - NUREG-1934, Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG); Second Draft...

    Science.gov (United States)

    2011-08-02

    ... NUCLEAR REGULATORY COMMISSION [NRC-2009-0568] NUREG-1934, Nuclear Power Plant Fire Modeling... 1023259), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft Report for...), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft for Comment,'' is...

  2. Analysis of Defective Pipings in Nuclear Power Plants and Applications of Guided Ultrasonic Wave Techniques

    International Nuclear Information System (INIS)

    Koo, Dae Seo; Cheong, Yong Moo; Jung, Hyun Kyu; Park, Chi Seung; Park, Jae Suck; Choi, H. R.; Jung, S. S.

    2006-07-01

    In order to apply the guided ultrasonic techniques to the pipes in nuclear power plants, the cases of defective pipes of nuclear power plants, were investigated. It was confirmed that geometric factors of pipes, such as location, shape, and allowable space were impertinent for the application of guided ultrasonic techniques to pipes of nuclear power plants. The quality of pipes, supports, signals analysis of weldment/defects, acquisition of accurate defects signals also make difficult to apply the guided ultrasonic techniques to pipes of nuclear power plants. Thus, a piping mock-up representing the pipes in the nuclear power plants were designed and fabricated. The artificial flaws will be fabricated on the piping mock-up. The signals of guided ultrasonic waves from the artificial flaws will be analyzed. The guided ultrasonic techniques will be applied to the inspection of pipes of nuclear power plants according to the basis of signals analysis of artificial flaws in the piping mock-up

  3. Development of advanced RFID application system for nuclear power plant

    International Nuclear Information System (INIS)

    Onda, Kimiharu; Wakabayashi, Eisuke; Arai, Ryota; Shigemi, Ryosuke; Muro, Keiro; Yuda, Shinya

    2008-01-01

    In late years there comes to be close request for traceability of the information such as production control, construction and maintenance record and work history of nuclear power plants. On the other hand, the Radio-frequency identification (RFID) technology that can specify a product and personnel by an electric wave has raised the functionality and versatility as the base technology that can support ubiquitous information society around the mass production industry. In such a background, this article described the developed system, which applied the RFID to nuclear power plants in the areas of production control of the piping manufacture, the construction management and condition monitoring for maintenance works in order to improve their quality and reliability. (T. Tanaka)

  4. Applications of the United States Nuclear Regulatory Commission nuclear plant analyzer

    International Nuclear Information System (INIS)

    Laats, E.T.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is being developed as the US NRC's state of the art safety analysis and engineering tool to address key nuclear plant safety issues. The NPA integrates the NRC's computerized reactor behavior codes such as RELAP5 and TRAC-BWR, both of which are well-developed computer graphics programs and large repositories of reactor design and experimental data. Utilizing these complex reactor behavior codes, as well as the experiment data repositories, enables simulation applications of the NPA that are generally not possible with more simplistic, less mechanistic reactor behavior codes used in training simulators or with simulators that are limited to displaying calculated data only. This paper describes four applications of the NPA simulation capabilities in assisting reactor safety analyses. Two analyses evaluated reactor operating procedures, during off-normal operation, for a pressurized water reactor (PWR) and a boiling water reactor (BWR), respectively. The third analysis was performed in support of a reactor safety experiment conducted in the Semiscale facility. The final application demonstrated the usefulness of atmospheric dispersion computer codes for site emergency planning purposes. An overview of the NPA simulation capabilities and how it supported these analyses are the topics of this paper

  5. Laser application maintenance technologies for nuclear power plant

    International Nuclear Information System (INIS)

    Shima, Seishi; Sato, Kenji; Kobayashi, Masahiro; Sano, Yuji; Kimura, Seiichiro

    2000-01-01

    Several plants that were the first to be constructed in Japan have been operating for more than 20 years now, and preventive maintenance is therefore a matter of great importance. This paper summarizes the status of applied laser maintenance technologies both preventive and repair. Especially for the laser peening and laser de-sensitization treatment technology, field applications were also described in detail. In future, expansion of field application area on the preventive maintenance, repair and inspection technologies will be developed. (author)

  6. Human factors guidelines for nuclear power plant applications

    International Nuclear Information System (INIS)

    Ketchel, J.

    1993-01-01

    In 1989, Waters et al. reported to the Human Factors Society on developing human factors criteria for a new reactor plant. They correctly indicated that much of the guidance documentation in human factors engineering has derived from MIL-STD-1472 and its antecedents. Guidelines for human-computer interface have sprung primarily from the Smith and Mosier compendium and its source documents. NUREG-0700, which is currently being updated, was developed by the US Nuclear Regulatory Commission (NRC) as a general evaluation guide for inspecting control rooms. In addition, the Electric Power Research Institute, Institute of Nuclear Power Operations, US Department of Energy, the NRC, and others have published a number of specialized documents on a range of subjects. The number of guidelines and standards has grown in the past few years to an impressive number, including those published by international organizations and professional societies. This paper provides an update on current efforts to provide appropriate guidance for the power industry and, perhaps more importantly, offers a perspective on how users should think about using the available materials and what else is needed. The Electric Power Research Institute (EPRI) continues to be one of the principal participants in providing guidance to the utilities. Human factors guidelines is indeed a timely topic, currently of great interest to EPRI's constituents and to designers of new and upgraded nuclear power plants (NPMs) in the Advanced Light Water Reactor and the Instrumentation and Control Upgrade Initiative programs

  7. Symposium on application of new materials to nuclear plants

    International Nuclear Information System (INIS)

    1988-01-01

    The papers on the application of new materials for upgrading LWRs, the application of new materials to FBRs, the application of new materials to high temperature gas-cooled reactors, the application of new materials to nuclear fusion reactors, engineering ceremics shape memorizing alloys and metal base composite materials are collected in this book. As for LWRs, the change of materials for LWR components and the present status of the research and development of the application of new materials in ANERI are described. As for the application of new materials to a demonstration FBR, high Cr-Mo steel, high ductility stainless steel, neutron resistant stainless steel and low cobalt case hardening material are explained, and the development of new materials for practical FBRs is discussed. As for high temperature gas-cooled reactors, the materials for control rod cladding tubes, heat exchangers and high temperature piping, fuel cladding, moderator and reflector, and heat insulator are described. As for nuclear fusion reactors, the structural materials, the materials facing plasma, and superconductive materials, electrode materials and others are discussed. (K.I.)

  8. Status report on the application of process noise technique in nuclear power plants

    International Nuclear Information System (INIS)

    Espefaelt, R.; Aakerhielm, F.

    1979-09-01

    The report gives a survey of applications of noise technique reported for nuclear power plants. The scope has been limited to areas of interest for BWR and PWR plants of the types found in Sweden and with an emphasis on cases where the practical applicability has been clearly demonstrated. (author)

  9. 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)

  10. A study on expert system applications for nuclear power plant

    International Nuclear Information System (INIS)

    Huh, Young Hwan; Kim, Kil Yoo; Kang, Soon Ju; Park, Nam Seok; Ryu, Chan Ho; Choi, In Seon; Chung, Young Moo; Chung, Tae Eon; Yim, Chang Jae; Lee, Yoon Sang.

    1990-01-01

    The objectives of this research are 1) to develop an expert system which can automatically evaluate eddy current (EC) signal during an eddy current test (ECT) of SG U tube inspection, 2) to build an effective data base management system for ECT data. By this expert system the reliability in EC signal evaluation can be improved, and the required man-power can be reduced. And this expert system can supply a stable ECT and contribute to a safe operation of the nuclear power plant. (author)

  11. The Basic Framework for Robot Applicability Enhancement of Nuclear Risk Management in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Young; Jeong, Kungmin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Inn Seock [bISSA Technology, Inc., Germantown (United States)

    2015-05-15

    Beyond-design-basis external events such as the one having occurred at the Fukushima Daiichi Nuclear Power Plant typically pose considerable challenges to the plant personnel because of the harsh environments caused by the events (e.g., extreme terrains, high radiation, radioactive rubbles, high heat, and explosive environment). Therefore, remote response techniques by use of robotic systems are needed to help the plant personnel cope with the extreme events. In this study the basic framework for enhancing robotic applicability to disaster management was developed using the analytic technique of Master Logic Diagram (MLD) and Goal-Tree Success-Tree (GTST). The users of robots have to devise a sound maintenance program, otherwise their unscheduled downtime may increase beyond limit, consequently defeating the purpose of robot applications. In addition, maintainability could be enhanced by designing for ease of diagnosis, and ease of access and repair. Ways to upgrade maintainability could be devised by evaluating maintainability in the design stage. The basic framework discussed herein shall be used by the KAERI's robotics team as a fundamental framework in enhancing the applicability of disaster robots in the hazardous environment caused by extreme events.

  12. Development and application of emergency operating procedures for nuclear power plants

    International Nuclear Information System (INIS)

    Lin Chengge

    1990-01-01

    The development and application of emergency operating procedures (EOPs) is an important measure to assure the operational safety for nuclear power plants. Event-oriented, symptom-, function- and state-oriented EOPs with their structures, interfaces, development procedures and practical application are described. The ideas and approach can be available for the preparation of EOPs for nuclear power plants which are going to be in service

  13. 77 FR 10784 - Calvert Cliffs Nuclear Power Plant, LLC; Notice of Withdrawal of Application for Amendment to...

    Science.gov (United States)

    2012-02-23

    ... Nuclear Power Plant, LLC; Notice of Withdrawal of Application for Amendment to Facility Operating License... Nuclear Power Plant, LLC, the licensee, to withdraw its application dated October 25, 2010, for a proposed amendment to Renewed Facility Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Plant...

  14. Nuclear power plant outages

    International Nuclear Information System (INIS)

    1998-01-01

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

  15. Building and application of the plant condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.

    2013-01-01

    To achieve the stable operation of nuclear power plants, we developed the plant condition monitoring system based on the heat and mass balance calculation. This system has adopted the heat balance model based on the actual plant data to find the symptoms of the disorder of the equipment by heat balance changes in the turbine system. (author)

  16. Development and application of the plant condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.

    2014-01-01

    To achieve the stable operation of nuclear power plants, we developed the plant condition monitoring system based on the heat and mass balance calculation. In this system, it is a significant feature to adopt the sophisticated heat balance model based on the actual plant data to find the symptoms of anomalies in the turbine system from heat balance changes. (author)

  17. Applications of probabilistic safety assessment (PSA) for nuclear power plants

    International Nuclear Information System (INIS)

    2001-02-01

    This report, which compiles information on a comprehensive set of PSA applications in the areas of NPP design, operation, and accident mitigation and management, is the culmination of an IAEA project on PSA Applications and Tools to Improve NPP Safety. In this regard, the Technical Committee Meeting (TCM) held in Madrid in February 1998 allowed participants to review and provide very valuable comments for this report. Several important facts related to PSA and its applications were highlighted during this TCM: living PSAs are the basis for the risk informed approach to decision making; development and use of safety/risk monitors as tools for configuration management is spreading fast; the different uses of PSA to support NPP testing and maintenance planning and optimization are amongst the most widespread PSA applications; plant specific PSAs are being used to support the safety upgrading programmes of plants built to earlier standards; not all countries have a regulatory framework for the use of the probabilistic approach in decision making. Some countries are still far from 'risk-informed' regulation, and this means that there is still considerable work ahead, both for regulators and utilities, to clarify approaches, to establish a framework and to reach a common understanding in relation to the use of PSA in decision making. This report is based on the premise that the use of PSA can provide useful information for the decision maker. This report is intended to provide an overview of current PSA applications. Section 2 addresses the PSA application process, outlines the general requirements for PSA tools and provides a discussion on PSA aspects such as PSA level, scope and level of detail, which have to be considered when planning/performing PSA applications. Section 3 discusses the technical aspects of individual applications and is divided into three parts. Section 3.1 is dedicated to the design related PSA applications. The second part of Section 3 considers

  18. Internet applications in nuclear power plant operation management; Aplicaciones de internet en la gestion de la explotacion de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Munoz, M. [Empresarios Agrupados, A. I. E. Madrid (Spain)

    2000-07-01

    The use of the Internet is quickly becoming widespread in practically all areas of business and industry. The nuclear industry should not remain indifferent to this new trend. This paper analyses some of the Internet applications that can be easily adapted to nuclear power plant operation management, including. (Author)

  19. Application and development analysis of nuclear power plant modular construction

    International Nuclear Information System (INIS)

    Fang Xiaopeng

    2015-01-01

    Modular Construction is currently one of the major development trends for the nuclear power plant construction technology worldwide. In the first-of-a-kind AP1000 Nuclear Power Project practiced in China, the large-scale structural modules and mechanical modules have been successfully fabricated, assembled and installed. However, in the construction practice of the project, some quality issues are identified with the assembly and installation process of large-scale structural modules in addition to the issue of incomplete supply of mechanical modules, which has failed to fully demonstrate the features and merits of modular construction. This paper collects and consolidates the issues of modular construction of AP1000 first of a kind reactor, providing root cause analysis in the aspects of process design, quality control, site construction logic, interface management in the process of module fabrication, assembly and installation; modular construction feasibility assessment index is proved based on the quantification and qualitative analysis of the impact element. Based on the modular construction feasibility, NPP modular construction improvement suggestions are provided in the aspect of modular assembly optimization definition, tolerance control during the fitting process and the construction logic adjustment. (author)

  20. Applications of pattern recognition theory in diagnostics of nuclear power plants

    International Nuclear Information System (INIS)

    Cech, J.

    1982-01-01

    The questions are discussed of the application of the theory of pattern recognition in the diagnostics of nuclear power plants. For the future use of recognition systems in the diagnostics of nuclear power plants it is obvious that like with other complex systems, optimal models will have to be used which will organize the optimal recognition algorithm. The conclusion is presented that for the needs of nuclear power plants special systems will be more suitable for pattern recognition than digital computers which are flexible and adaptible but have a lower decision rate, an insufficient working memory, complicated programs, etc. (Z.M.)

  1. Application on electrochemistry measurement of high temperature high pressure condition in PWR nuclear power plants

    International Nuclear Information System (INIS)

    Li Yuchun; Xiao Zhongliang; Jiang Ya; Yu Xiaowei; Pang Feifei; Deng Fenfang; Gao Fan; Zhou Nianguang

    2011-01-01

    High temperature high pressure electrochemistry testing system was comprehensively analyzed in this paper, according to actual status for supervision in primary and secondary circuits of PWR nuclear power plants. Three research methods were reviewed and discussed for in-situ monitor system. By combination with ECP realtime measurement it was executed for evaluation and water chemistry optimization in nuclear power plants. It is pointed out that in-situ electrochemistry measurement has great potential application for water chemistry evaluation in PWR nuclear power plants. (authors)

  2. Application of autonomous mobile patrol system for nuclear power plants

    International Nuclear Information System (INIS)

    Kanemoto, S.; Hattori, Y.; Ochiai, M.; Tai, I.; Ozaki, O.; Shimada, H.; Okano, H.

    1995-01-01

    The integrity of the components of an operating nuclear power plant (NPP) is usually monitored daily by an operator patrol. Currently, there is a great need to replace such human patrol activities by automated remote monitoring in order to reduce radiation exposure and severe workload. From this perspective, we started an R and D project with the objective of developing an autonomous mobile patrol system for NPPs. The project started in 1991 and is scheduled to be completed in 1996. The main targets of this project are as follows. (1) Development of an autonomous and independent mobile robot, (2) Development of a transportable compact remote sensing system for plant component inspection, (3) Development of a patrol guidance and sensing data evaluation system. The remote sensing system has the capability of detecting video image, sound, temperature and vibration distribution of component surfaces. A laser Doppler vibrometer is newly developed to measure a wide range of vibration distribution remotely. Also, in order to integrate and recognize various kinds of remote sensing data, a 3-dimensional (3D) computer aided design database and 3D graphics technology is extensively used. Operators can interpret the measured image data by mapping their textures onto the 3-dimensional model surface. In this paper, we describe the concept of the entire patrol system and its three main component technologies, that is, mobile robot, remote sensing and inspected data evaluations. (author)

  3. Cardinal principle and application practice of 3D digital model design for nuclear power plant

    International Nuclear Information System (INIS)

    Wang Ruobing; Wu Yan

    2005-01-01

    The practical application of 3D digital model design at nuclear power plants was introduced in detail in the paper. The whole process for system choice, program constitution, model design and project practice were also summarized. By demonstrating the cardinal principal and application practice of 3D digital model design as an important sub-project of CGNPC Digital Plant, the paper validates the rationality and validity of the major architecture system and program configuration of the digital plant, carries out beneficial attempt and study in the overall power plant life engineering management and site practice, and has achieved significant engineering and social benefits. The success of practices in the project accelerates the extended and extensive application of Digital Plant in the operation and maintenance simulation of Daya Bay and Ling'ao Nuclear Power Plants, and the engineering design management for Ling'ao II and III of CGNPC on a consolidated basis. (authors)

  4. Applications of neural networks to monitoring and decision making in the operation of nuclear power plants

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1990-01-01

    Application of neural networks to monitoring and decision making in the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: (1) diagnosing specific abnormal conditions or problems in nuclear power plants, (2) detection of the change of mode of operation of the plant, (3) validating signals coming from detectors, (4) review of ''noise'' data from TVA's Sequoyah Nuclear Power Plant, and (5) examination of the NRC's database of ''Letter Event Reports'' for correlation of sequences of events in the reported incidents. Each of these projects and its status are described briefly in this paper. This broad based program has as its objective the definition of the state-of-the-art in using neural networks to enhance the performance of commercial nuclear power plants

  5. Application of balanced score card in the development of performance indicator system in nuclear power plant

    International Nuclear Information System (INIS)

    Shen Shuguang; Huang Fang; Fang Zhaoxia

    2013-01-01

    Performance indicator, which is one of ten performance monitoring tools recommended by WANO performance improvement model, has become an effective tool for performance improvement of nuclear power plant. At present, performance indicator system has been built in nuclear power plant. However, how to establish the performance indicator system that is reasonable and applicable for plant is still a question to be discussed. Performance indictor is closely tied to the strategic direction of a corporation by a balanced score card, and the performance indicator system is established from the point of performance management and strategic development. The performance indicator system of nuclear power plant is developed by introducing the balanced score card, and can be as a reference for other domestic nuclear power plants. (authors)

  6. Application of artificial intelligence for nuclear power plant surveillance and diagnosis problems

    International Nuclear Information System (INIS)

    Monnier, B.; Ricard, B.; Doutre, J.L.; Martin-Mattei, C.; Fernandes, A.

    1991-01-01

    This paper presents three expert systems in the field of surveillance and diagnosis of nuclear power plants. Each application is described from the point of view of knowledge modeling. Then, a general knowledge model is proposed for a class of diagnosis problems. At the end, the paper shows the future frame of the surveillance of the nuclear power plant main components at EDF in which the greatest part of those expert systems will run

  7. A hierarchical structure for risk criteria applicable to nuclear power plants

    International Nuclear Information System (INIS)

    Hall, R.E.; Mitra, S.P.

    1982-01-01

    This paper discusses the development of a hierarchical structure for risk criteria applicable to nuclear power plants. The structure provides a unified framework to systematically analyze the implications of different types of criteria, each focusing on a particular aspect of nuclear power plant risks. The framework allows investigation of the specific coverage of a particular criterion and comparison of different criteria with regard to areas to which they apply

  8. Status of NDE research and applications for life management of nuclear power plants in india

    Energy Technology Data Exchange (ETDEWEB)

    Raj, B.; Shyamsunder, M.T.; Jayakumar, T. [Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Metallurgy and Materials Group

    1999-08-01

    The development and application of various nondestructive evaluation techniques and methodologies for the life management of nuclear power plants in India are described. The indigenous development carried out to meet the stringent quality requirements in evaluation of fabricated components and innovative methodologies using multidisciplinary approaches and advances for assessment of inservice performance of plants are highlighted. (orig.)

  9. Status of NDE research and applications for life management of nuclear power plants in india

    International Nuclear Information System (INIS)

    Raj, B.; Shyamsunder, M.T.; Jayakumar, T.

    1999-01-01

    The development and application of various nondestructive evaluation techniques and methodologies for the life management of nuclear power plants in India are described. The indigenous development carried out to meet the stringent quality requirements in evaluation of fabricated components and innovative methodologies using multidisciplinary approaches and advances for assessment of inservice performance of plants are highlighted. (orig.)

  10. Probabilistic risk criteria and their application to nuclear chemical plant design

    International Nuclear Information System (INIS)

    Arthur, T.; Barnes, D.S.; Brown, M.L.; Taig, A.R.; Johnston, B.D.; Hayns, M.

    1989-01-01

    A nuclear chemical plant safety strategy is presented. The use of risk criteria in design is demonstrated by reference to a particular area of the plant. This involves the application of Probabilistic Risk Assessment (PRA) techniques. Computer programs developed by the UK Atomic Energy Authority (UKAEA) at its Safety and Reliability Directorate (SRD) are used toe valuate and analyze the resultant fault trees. the magnitude of releases are estimated and individual and societal risks determined. The paper concludes that the application of PRA to a nuclear chemical plant can be structured in such a way as to allow a designer to work to quantitative risk targets

  11. Risk monitor riskangel for risk-informed applications in nuclear power plants

    International Nuclear Information System (INIS)

    Wang, Fang; Wang, Jiaqun; Wang, Jin; Li, Yazhou; Hu, Liqin; Wu, Yican

    2016-01-01

    Highlights: • A general risk monitor riskangel with high-speed cutsets generator engine. • Benchmarks of actual nuclear power plant (NPP) instantaneous risk models. • Applications in daily operation, maintenance plan and component out of service. - Abstract: This paper studied the requirements of risk monitor software and its applications as a plant specific risk monitor, which supports risk-informed configuration risk management for the two CANDU 6 units at the Third Qinshan nuclear power plant (TQNPP) in China. It also describes the regulatory prospective on risk-informed Probabilistic Safety Assessment (PSA) applications and the use of risk monitor at operating nuclear power plants, high level technical and functional requirements for the development of CANDU specific risk monitor software, and future development trends.

  12. Reliability of dc power supplies in nuclear power plant application

    International Nuclear Information System (INIS)

    Eisenhut, D.G.

    1978-01-01

    In June 1977 the reliability of dc power supplies at nuclear power facilities was questioned. It was postulated that a sudden gross failure of the redundant dc power supplies might occur during normal plant operation, and that this could lead to insufficient shutdown cooling of the reactor core. It was further suggested that this potential for insufficient cooling is great enough to warrant consideration of prompt remedies. The work described herein was part of the NRC staff's efforts aimed towards putting the performance of dc power supplies in proper perspective and was mainly directed towards the particular concern raised at that time. While the staff did not attempt to perform a systematic study of overall dc power supply reliability including all possible failure modes for such supplies, the work summarized herein describes how a probabilistic approach was used to supplement our more usual deterministic approach to reactor safety. Our evaluation concluded that the likelihood of dc power supply failures leading to insufficient shutdown cooling of the reactor core is sufficiently small as to not require any immediate action

  13. Applications of RFID into Nuclear Power Plant Maintenance System

    International Nuclear Information System (INIS)

    Lee, Seung Min; Seong, Poong Hyun

    2008-01-01

    RFID (Radio Frequency Identification) system, one of the most anticipated ubiquitous technologies is an automatic identification method using devices called RFID tags. RFID antenna detects each approach of RFID tags and recognizes the tags' ID and transfer to reader to do information processing. Since first introduced in the logistics industry, production management and maintenance organization in various fields of domestic and foreign enterprises introduce the RFID. Nuclear power plants are also using RFID to manage materials lately. However, the current status on the use of RFID is just a little more advanced on the use of bar code. Therefore, it seems that the important characteristic of RFID is not enough actualized to keep seeing. In point of Maintenance Information Field based on ubiquitous technology, the most important concept is real-time information processing. And RFID is quite proper to develop this information field system because it satisfies for the matter of that concept. The leading content in ubiquitous maintenance system is that maintenance personnel can get information what he needs and he can also transfer information what he gets whenever and wherever he is. In this paper, some examples of applying RFID in development of ubiquitous maintenance system are suggested

  14. Nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

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

  15. Technical analysis of magneto-inductive crane cables in nuclear power plants. Application crane Cofrentes Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gavilan Moreno, C. J.

    2010-01-01

    In 2009, the Cofrentes Nuclear Power Plant made a study about crane inspection techniques available on the market and other industries. The result was the location of the magneto-inductive technique inspection. Its use provides an objective assessment of the resistant section and; through these data; it could be made calculations as the maximum voltage allowed. Therefore, the technique is proven and available to all nuclear power plants.

  16. Applications of computer based safety systems in Korea nuclear power plants

    International Nuclear Information System (INIS)

    Won Young Yun

    1998-01-01

    With the progress of computer technology, the applications of computer based safety systems in Korea nuclear power plants have increased rapidly in recent decades. The main purpose of this movement is to take advantage of modern computer technology so as to improve the operability and maintainability of the plants. However, in fact there have been a lot of controversies on computer based systems' safety between the regulatory body and nuclear utility in Korea. The Korea Institute of Nuclear Safety (KINS), technical support organization for nuclear plant licensing, is currently confronted with the pressure to set up well defined domestic regulatory requirements from this aspect. This paper presents the current status and the regulatory activities related to the applications of computer based safety systems in Korea. (author)

  17. UPVAPOR: computer application for the analysis of the results of Cofrentes Nuclear Power Plant production

    International Nuclear Information System (INIS)

    Palomo, M. J.; Baraza Peregrin, A.; Bucho Piqueras, L.; Vaquer Perez, J. I.; Lopez Lopez, B.

    2010-01-01

    UPVapor is a software developed for the Cofrentes Nuclear Power Plant Group of Results. This application presents a graphical environment for analysis in which the user has available many variables registered to configure the graphics. This application saves a lot of time at work because it allows other users to do their own analysis without resorting to analysts.

  18. Application of Advanced Technology to Improve Plant Performance in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2011-01-01

    Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

  19. The main pump motor remote visual check in the application of the domestic nuclear power plants

    International Nuclear Information System (INIS)

    Ge Lianwei; Yu Tao; Fang Jiang; Zhang Ting; Zhang Xingtian; Ding Youyuan

    2014-01-01

    In this paper, the Qinshan nuclear power station the first main pump motor to the successful implementation of remote visual inspection the main pump motor remote visual inspection applications. Qinshan Nuclear Power Plant Units 1 and 2 of the main pump motor inspection results show that the key components of the Qinshan Nuclear Power Plant Units 1 and 2 of the main pump rotor, stator end coils good condition, its problems for 10 years in the motor does not affect the normal use of the motor state disintegration overhaul problems tracking disintegration overhaul in 10 years. (authors)

  20. Study on application of Doppler SODAR as meteorological observation tool at nuclear power plant

    International Nuclear Information System (INIS)

    Katayose, Naoto; Akai, Yukio.

    1993-01-01

    Among the remote sensing devices usable for meteorological observation, which became possible with the advent of modern science and technology, Doppler SODAR was selected for further study aimed at its practical application for nuclear power plants. This device was installed for testing purpose at a Japanese nuclear power and data collection (wind speed and direction) was carried out throughout one year there. The data on the selected SODAR have shown a correlation with those collected by the conventional method which is good enough to justify the SODAR's practical use at nuclear power plants. (author)

  1. Safety considerations for various applications of remote multiplexing in nuclear power plants

    International Nuclear Information System (INIS)

    Leary, J.E.

    1978-01-01

    There is increasing interest in the application of remote multiplexing systems (RMS) for power plant applications. Remote multiplexing can replace the majority of conventional control and instrumentation signal cables. In addition, the RMS can perform control logic functions presently implemented by discrete hardwired circuit elements. The background and trends in the use of RMS and the attendant advantages and concerns are reviewed. Classifications of multiplexed digital systems are presented to show the evolution of this technology in power plant applications. Nuclear safety-related applications of RMS are discussed with emphasis on the impact of selected NRC Regulatory Guides on such applications. (author)

  2. FPGA Design Methodologies Applicable to Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kwong, Yongil; Jeong, Choongheui

    2013-01-01

    In order to solve the above problem, NPPs in some countries such as the US, Canada and Japan have already applied FPGA-based equipment which has advantages as follows: It is easier to verify the performance because it needs only HDL code to configure logic circuits without other software, compared to microprocessor-based equipment, It is much cheaper than ASIC in a small quantity, Its logic circuits are re configurable, It has enough resources like logic blocks and memory blocks to implement I and C functions, Multiple functions can be implemented in a FPGA chip, It is stronger with respect to carboy security than microprocessor-based equipment because its configuration cannot be changed by external access, It is simple to replace it with new one when it is obsolete, Its power consumption is lower. However, FPGA-based equipment does not have only the merits. There are some issues on its application to NPPs. First of all, the experiences in applying it to NPPs are much less than to other industries, and international standards or guidelines are also very few. And there is the small number of FPGA platforms for I and C systems. Finally, the specific guidelines on FPGA design are required because the design has both hardware and software characteristics. In order to handle the above issues, KINS(Korea Institute of Nuclear Safety) built a test platform last year and have developed regulatory guidelines for FPGA-application in NPPs. I and C systems of NPPs have been increasingly using FPGA-based equipment as an alternative of microprocessor-based equipment which is not simple to be evaluated for safety due to its complexity. This paper explained the FPGA design flow and design guidelines. Those methodologies can be used as the guidelines on FPGA verification for safety of I and C systems

  3. A Study on Guidelines for the Utilization of Unproven MMIS Technology In Nuclear Power Plant Application

    International Nuclear Information System (INIS)

    Kang, Sung Kon; Shin, Yeong Cheol; Bae, Byoung Hwan

    2007-01-01

    New MMIS (Man Machine Interface System) technology is rapidly advanced as digital technology provides opportunity for more functionality and better cost effectiveness and NPP (Nuclear Power Plant) operators are inclined to use the new technology for the construction of new plant and for the upgrade of existing plants. However, this new technology poses risks to the NPP operators at the same time. These risks are mainly due to the poor reliability of newly developed technology. KHNP's past experiences with the new MMIS equipment shows many cases of reliability problem. And their consequences include unintended plant trips, lowered acceptance of the new digital technology by the plant I and C maintenance crew, and increased licensing burden in answering for questions from the nuclear regulatory body. Considering the fact that the risk of these failures in the nuclear plant operation is far greater than those in other industry, utilities require proven technology for the MMIS in nuclear power plants. So that new MMIS technology might be testified as proven technology, guidelines for the utilization of unproven MMIS technology in nuclear power plant application is required for applying new advanced MMIS technology which is apparently needed to obtain a definite gain in simplicity or performance

  4. 78 FR 4467 - UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3...

    Science.gov (United States)

    2013-01-22

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3, Exemption 1.0 Background UniStar Nuclear Energy (UNE), on behalf of Calvert Cliffs Nuclear Project, LLC and UniStar Nuclear Operating Services...

  5. Applicability of Operational Research Techniques in CANDU Nuclear Plant Maintenance

    International Nuclear Information System (INIS)

    Doyle, E. Kevin

    2002-01-01

    As previously reported at ICONE 6 in New Orleans, 1996, and ICONE 9 in Niece, 2001, the use of various maintenance optimization techniques at Bruce has lead to cost effective preventive maintenance applications for complex systems. Innovative practices included greatly reducing Reliability Centered Maintenance (RCM) costs while maintaining the accuracy of the analysis. The optimization strategy has undergone further evolution and at the present an Integrated Maintenance Program (IMP) is being put in place. Further cost refinement of the station preventive maintenance strategy whereby decisions are based on statistical analysis of historical failure data is being evaluated. A wide range of Operational Research (OR) literature was reviewed for implementation issues and several encouraging areas were found that will assist in the current effort of evaluating maintenance optimization techniques for nuclear power production. The road ahead is expected to consist first of resolving 25 years of data issues and preserving the data via appropriate knowledge system techniques while post war demographics permit experts to input into the system. Subsequent analytical techniques will emphasize total simplicity to obtain the requisite buy in from Corporate Executives who possibly are not trained in Operational Research. Case studies of containment airlock seal failures are used to illustrate the direct applicability of stochastic processes. Airlocks and transfer chambers were chosen as they have long been known as high maintenance items. Also, the very significant financial consequences of this type of failure will help to focus the attention of Senior Management on the effort. Despite substantial investment in research, improvement in the design of the seal material or configuration has not been achieved beyond the designs completed in the 1980's. Overall, the study showed excellent agreement of the relatively quick stochastic methods with the maintenance programs produced at

  6. Application of NASA Kennedy Space Center system assurance analysis methodology to nuclear power plant systems designs

    International Nuclear Information System (INIS)

    Page, D.W.

    1985-01-01

    The Kennedy Space Center (KSC) entered into an agreement with the Nuclear Regulatory Commission (NRC) to conduct a study to demonstrate the feasibility and practicality of applying the KSC System Assurance Analysis (SAA) methodology to nuclear power plant systems designs. In joint meetings of KSC and Duke Power personnel, an agreement was made to select to CATAWBA systems, the Containment Spray System and the Residual Heat Removal System, for the analyses. Duke Power provided KSC with a full set a Final Safety Analysis Reports as well as schematics for the two systems. During Phase I of the study the reliability analyses of the SAA were performed. During Phase II the hazard analyses were performed. The final product of Phase II is a handbook for implementing the SAA methodology into nuclear power plant systems designs. The purpose of this paper is to describe the SAA methodology as it applies to nuclear power plant systems designs and to discuss the feasibility of its application. The conclusion is drawn that nuclear power plant systems and aerospace ground support systems are similar in complexity and design and share common safety and reliability goals. The SAA methodology is readily adaptable to nuclear power plant designs because of it's practical application of existing and well known safety and reliability analytical techniques tied to an effective management information system

  7. Information to be submitted in support of licensing applications for nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Agency's Safety Series No.50-C-G, entitled ''Governmental Organization for the Regulation of Nuclear Power Plants: A Code of Practice''. It is concerned with the content of documents which should be submitted to the regulatory body by the applicant/licensee in support of licensing applications, with a possible method of classifying these documents and with the scheduling of their submission to the regulatory body at each major stage of the licensing process

  8. Applicability of the proposed evaluation method for social infrastructures to nuclear power plants

    International Nuclear Information System (INIS)

    Ichimura, Tomiyasu

    2015-01-01

    This study proposes an evaluation method for social infrastructures, and verifies the applicability of the proposed evaluation method to social infrastructures by applying it to nuclear power plants, which belong to social infrastructures. In the proposed evaluation method for social infrastructures, the authors chose four evaluation viewpoints and proposed common evaluation standards for the evaluation indexes obtained from each viewpoint. By applying this system to the evaluation of nuclear power plants, the evaluation index examples were obtained from the evaluation viewpoints. Furthermore, when the level of the common evaluation standards of the proposed evaluation method was applied to the evaluation of the activities of nuclear power plants based on the regulations, it was confirmed that these activities are at the highest level. Through this application validation, it was clarified that the proposed evaluation method for social infrastructures had certain effectiveness. The four evaluation viewpoints are 'service,' 'environment,' 'action factor,' and 'operation and management.' Part of the application examples to a nuclear power plant are as follows: (1) in the viewpoint of service: the operation rate of the power plant, and operation costs, and (2) in the viewpoint of environment: external influence related to nuclear waste and radioactivity, and external effect related to cooling water. (A.O.)

  9. The application of FIMS to the Korean nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Seung-Tae; Choi, Dae-Sik; Yang, Choong-Yeol

    2010-01-01

    The smart transmitters have been installed at selected systems of Ulchin Nuclear Units 5 and 6, and diagnosis and calibration for the smart transmitters have been carried out using the mobile calibration tools. In Shin-Kori Nuclear Units 1 and 2 and Shin-Wolsong Nuclear Units 1 and 2, which are under design and construction, the smart transmitters are installed in the places where total integrated radiation dose is below 10 Gy. FIMS (Field Instrument Management System) is applied to Shin-Kori Nuclear Units 1 and 2 and Shin-Wolsong Nuclear Units 1 and 2 to monitor and calibrate the smart transmitters remotely. FIMS is a centralized management system to allow the users to monitor the operating status, to perform the instrument diagnosis, and to carry out the calibration of locally mounted transmitters remotely during the commissioning and normal operation. (authors)

  10. Application of integrated computer-aided engineering for design, construction and operation of nuclear power plant

    International Nuclear Information System (INIS)

    Kyung-shick Min; Byung-hun Lee

    1987-01-01

    Computer-aided-engineering (CAE) is an essential tool for modern nuclear power plant engineering. It greatly varies in definition, application, and technology from project to project and company to company. Despite the fast growing technologies and applications of CAE, its complexty and variety have thrown aonther puzzle to management of a nuclear project. Without due consideration of an integrated CAE system in early planning stage, the overall efficiency of a nuclear project would slow down due to the inefficiency in data flow. In this paper, practices and perspectives of CAE appliation are discussed under the Korea Power Engineering Company (KOPEC) philosophy in CAE approach. (author)

  11. Application of linear scheduling method (LSM) for nuclear power plant (NPP) construction

    International Nuclear Information System (INIS)

    Kim, Woojoong; Ryu, Dongsoo; Jung, Youngsoo

    2014-01-01

    Highlights: • Mixed use of linear scheduling method with traditional CPM is suggested for NPP. • A methodology for selecting promising areas for LSM application is proposed. • A case-study is conducted to validate the proposed LSM selection methodology. • A case-study of reducing NPP construction duration by using LSM is introduced. - Abstract: According to a forecast, global energy demand is expected to increase by 56% from 2010 to 2040 (EIA, 2013). The nuclear power plant construction market is also growing with sharper competition. In nuclear power plant construction, scheduling is one of the most important functions due to its large size and complexity. Therefore, it is crucial to incorporate the ‘distinct characteristics of construction commodities and the complex characteristics of scheduling techniques’ (Jung and Woo, 2004) when selecting appropriate schedule control methods for nuclear power plant construction. However, among various types of construction scheduling techniques, the traditional critical path method (CPM) has been used most frequently in real-world practice. In this context, the purpose of this paper is to examine the viability and effectiveness of linear scheduling method (LSM) applications for specific areas in nuclear power plant construction. In order to identify the criteria for selecting scheduling techniques, the characteristics of CPM and LSM were compared and analyzed first through a literature review. Distinct characteristics of nuclear power plant construction were then explored by using a case project in order to develop a methodology to select effective areas of LSM application to nuclear power plant construction. Finally, promising areas for actual LSM application are suggested based on the proposed evaluation criteria and the case project. Findings and practical implications are discussed for further implementation

  12. Application of linear scheduling method (LSM) for nuclear power plant (NPP) construction

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woojoong, E-mail: minidung@nate.com [Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd, Daejeon 305-343 (Korea, Republic of); Ryu, Dongsoo, E-mail: energyboy@khnp.co.kr [Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd, Daejeon 305-343 (Korea, Republic of); Jung, Youngsoo, E-mail: yjung97@mju.ac.kr [College of Architecture, Myongji University, Yongin 449-728 (Korea, Republic of)

    2014-04-01

    Highlights: • Mixed use of linear scheduling method with traditional CPM is suggested for NPP. • A methodology for selecting promising areas for LSM application is proposed. • A case-study is conducted to validate the proposed LSM selection methodology. • A case-study of reducing NPP construction duration by using LSM is introduced. - Abstract: According to a forecast, global energy demand is expected to increase by 56% from 2010 to 2040 (EIA, 2013). The nuclear power plant construction market is also growing with sharper competition. In nuclear power plant construction, scheduling is one of the most important functions due to its large size and complexity. Therefore, it is crucial to incorporate the ‘distinct characteristics of construction commodities and the complex characteristics of scheduling techniques’ (Jung and Woo, 2004) when selecting appropriate schedule control methods for nuclear power plant construction. However, among various types of construction scheduling techniques, the traditional critical path method (CPM) has been used most frequently in real-world practice. In this context, the purpose of this paper is to examine the viability and effectiveness of linear scheduling method (LSM) applications for specific areas in nuclear power plant construction. In order to identify the criteria for selecting scheduling techniques, the characteristics of CPM and LSM were compared and analyzed first through a literature review. Distinct characteristics of nuclear power plant construction were then explored by using a case project in order to develop a methodology to select effective areas of LSM application to nuclear power plant construction. Finally, promising areas for actual LSM application are suggested based on the proposed evaluation criteria and the case project. Findings and practical implications are discussed for further implementation.

  13. Application of ESER computers to operation management of nuclear power plants

    International Nuclear Information System (INIS)

    Kuhne, E.; Poetter, K.F.; Suschok, G.

    1990-01-01

    Operation management of nuclear reactors is essentially support by calculational studies in which large computers have to be employed. A system of programs is presented that support the solution of those tasks which are related to refuelling and stationary operation of WWER-440 type reactors. Application of this system is made in the Greifswald nuclear power plant 'Bruno Leuschner' using access to the ESER computers at the Neubrandenburg Data Processing Centre in the teleprocessing mode. System solution and hardware used are described. (author)

  14. Inspection of Nuclear Power Plant Structures - Overview of Methods and Related Applications

    International Nuclear Information System (INIS)

    Naus, Dan J.

    2009-01-01

    The objectives of this limited study were to provide an overview of the methods that are available for inspection of nuclear power plant reinforced concrete and metallic structures, and to provide an assessment of the status of methods that address inspection of thick, heavily-reinforced concrete and inaccessible areas of the containment metallic pressure boundary. In meeting these objectives a general description of nuclear power plant safety-related structures was provided as well as identification of potential degradation factors, testing and inspection requirements, and operating experience; methods for inspection of nuclear power plant reinforced concrete structures and containment metallic pressure boundaries were identified and described; and applications of nondestructive evaluation methods specifically related to inspection of thick-section reinforced concrete structures and inaccessible portions of containment metallic pressure boundaries were summarized. Recommendations are provided on utilization of test article(s) to further advance nondestructive evaluation methods related to thick-section, heavily-reinforced concrete and inaccessible portions of the metallic pressure boundary representative of nuclear power plant containments. Conduct of a workshop to provide an update on applications and needed developments for nondestructive evaluation of nuclear power plant structures would also be of benefit.

  15. Inspection of Nuclear Power Plant Structures - Overview of Methods and Related Applications

    Energy Technology Data Exchange (ETDEWEB)

    Naus, Dan J [ORNL

    2009-05-01

    The objectives of this limited study were to provide an overview of the methods that are available for inspection of nuclear power plant reinforced concrete and metallic structures, and to provide an assessment of the status of methods that address inspection of thick, heavily-reinforced concrete and inaccessible areas of the containment metallic pressure boundary. In meeting these objectives a general description of nuclear power plant safety-related structures was provided as well as identification of potential degradation factors, testing and inspection requirements, and operating experience; methods for inspection of nuclear power plant reinforced concrete structures and containment metallic pressure boundaries were identified and described; and applications of nondestructive evaluation methods specifically related to inspection of thick-section reinforced concrete structures and inaccessible portions of containment metallic pressure boundaries were summarized. Recommendations are provided on utilization of test article(s) to further advance nondestructive evaluation methods related to thick-section, heavily-reinforced concrete and inaccessible portions of the metallic pressure boundary representative of nuclear power plant containments. Conduct of a workshop to provide an update on applications and needed developments for nondestructive evaluation of nuclear power plant structures would also be of benefit.

  16. Nuclear power plant monitoring method by neural network and its application to actual nuclear reactor

    International Nuclear Information System (INIS)

    Nabeshima, Kunihiko; Suzuki, Katsuo; Shinohara, Yoshikuni; Tuerkcan, E.

    1995-11-01

    In this paper, the anomaly detection method for nuclear power plant monitoring and its program are described by using a neural network approach, which is based on the deviation between measured signals and output signals of neural network model. The neural network used in this study has three layered auto-associative network with 12 input/output, and backpropagation algorithm is adopted for learning. Furthermore, to obtain better dynamical model of the reactor plant, a new learning technique was developed in which the learning process of the present neural network is divided into initial and adaptive learning modes. The test results at the actual nuclear reactor shows that the neural network plant monitoring system is successfull in detecting in real-time the symptom of small anomaly over a wide power range including reactor start-up, shut-down and stationary operation. (author)

  17. A Production-Rule Analysis System for Nuclear Plant monitoring and emergency response applications

    International Nuclear Information System (INIS)

    Ragheb, M.; Tsoukalas, L.; McDonough, T.; Parker, M.

    1987-01-01

    A Production-Rule Analysis System for Nuclear Power Plant Monitoring is presented. The signals generated by the Zion-1 Plant are considered for emergency Response applications. The integrity of the Plant Radiation, the Reactor Coolant, the Fuel Clad, and the Containment Systems, is monitored. Representation of the system is in the form of a goal-tree generating a Knowledge-Base searched by an Inference Engine functioning in the forward-chaining mode. The Gaol-tree is built from Fault-Trees based on plant operational information. The system is implemented on a VAX-8500 and is programmed in OPS-5

  18. 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)

  19. Application status and performance analysis of robot in nuclear power plants

    International Nuclear Information System (INIS)

    Liu Chengze; Yan Zhi; Deng Jingshan

    2012-01-01

    Application status of robot in nuclear power plants in some countries is summarized. The related robots include accident response robot, dismantling and cleaning robot, in-service inspection robot, special-purpose robot and so on. Finally, some key technologies such as the radiation-tolerance and reliability of the robot systems are analyzed in details. (authors)

  20. Special conditions for the application of coating materials in nuclear power plants

    International Nuclear Information System (INIS)

    Boetius, I.

    1980-01-01

    Proceeding from the special conditions for the application of coating materials in nuclear power plants the following factors influencing the decontamination of surface coatings are discussed from the point of view of radiation protection: abrasion resistance, waterproofness, mechanical and adhesion strength, and permeability. For practical use it is recommended to test the surface tightness of coatings with radiation-exposed specimens

  1. The Transportable Nuclear Plant for Multi Purpose Applications

    International Nuclear Information System (INIS)

    Pahladsingh, R.R.

    2002-01-01

    The DOE (Department of Energy - USA) has started the Generation IV initiative for the new generation of nuclear reactors that have to be much better developed for safety, economy and public acceptance. The SGR (Simplified Gas-cooled Reactor) is being proposed as a Generation IV modular nuclear reactor, using graphite pebbles as fuel, whereby an attempt has been made to meet all the DOE requirements [1,2] to be used for future nuclear reactors. Deregulation and liberalization are changing the global energy-markets. At the same time innovative technologies are introduced in the electricity industry; often as a requirement from the upcoming Digital Society. Energy solutions for the future are more seen as a mix of energy-sources for generation-, transmission- and distribution energy-services. The Internet Energy-web based 'Virtual' enterprises are coming up and will gradually change our society. The focus in this paper is on the changing and emerging global energy-markets and how the nuclear industry can anticipate in the coming Digital Society. (authors)

  2. Optimized Application of MSR and Steam Turbine Retrofits in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Crossland, Robert; McCoach, John [ALSTOM Power, Willans Works, Newbold Road, Rugby, Warwickshire CV21 2NH (United Kingdom); Gagelin, Jean-Philippe [ALSTOM Power Heat Exchange, 19-21 avenue Morane-Saulnier, BP 65, 78143 Velizy Cedex (France)

    2004-07-01

    The benefit to a nuclear power plant from a steam turbine retrofit has often been clearly demonstrated in recent years but, for light water nuclear plants, the Moisture Separator Reheaters (MSRs) are also of prime importance. This paper describes how refurbishment of these crucial components can only provide full potential performance benefit when made in conjunction with a steam turbine retrofit (although in practice these activities are frequently separated). Examples are given to show how combined application is best handled within a single organization to ensure optimized integration into the thermal cycle. (authors)

  3. Optimized Application of MSR and Steam Turbine Retrofits in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Crossland, Robert; McCoach, John; Gagelin, Jean-Philippe

    2004-01-01

    The benefit to a nuclear power plant from a steam turbine retrofit has often been clearly demonstrated in recent years but, for light water nuclear plants, the Moisture Separator Reheaters (MSRs) are also of prime importance. This paper describes how refurbishment of these crucial components can only provide full potential performance benefit when made in conjunction with a steam turbine retrofit (although in practice these activities are frequently separated). Examples are given to show how combined application is best handled within a single organization to ensure optimized integration into the thermal cycle. (authors)

  4. Attributes of Full Scope Level 1 Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2016-10-01

    This publication supersedes IAEA-TECDOC-1511, Determining the Quality of Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants (published in 2006), which provided detailed information on technical features of a restricted scope PSA aimed at analysing only internal initiating events caused by random component failures and human errors, and accident sequences that may lead to reactor core damage during operation. The present publication extends the scope of the PSA to cover a broader range of internal and external hazards, and low power and shutdown modes of nuclear power plant operation. In addition, some PSA aspects relevant to lessons learned from the accident at the Fukushima Daiichi nuclear power plant are also considered

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-17

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

  6. An application of multilevel flow modelling method for nuclear plant state identification

    International Nuclear Information System (INIS)

    Businaro, T.; Di Lorenzo, A.; Meo, G.B.; Rabbani, M.I.; Rubino, E.

    1986-01-01

    With the advent of advanced digital techniques it has been rendered possible, necessity of which has long since been recognised, to develop a computer based man-machine interface and hance an expert system based on knowledge based decision making for operator support in the control rooms of nuclear plants. The Multilevel Flow Modelling method developed at RISO Laboratories, Denmark, has been applied in the present experiment to model Italian PEC reactor and to verify applicability of this method in plant state identification. In MFM method functional structure of a process plant is described in terms of a set of interrelated mass and energy flow structures on different levels of physical aggregation

  7. Barnwell Nuclear Fuel Plant. License application, amendment 10

    International Nuclear Information System (INIS)

    1975-01-01

    Amendment No. 10 provides the applicant's responses to questions raised by the AEC in letters dated November 6 and December 5, 1974. Amendment No. 3, dated February 1975, to the BNFP Separations Facility Final Safety Analysis Report (FSAR) is included. The amendment consists of revision pages for volumes 1 through 5 of the FSAR along with a deletion and insertion guide. (U.S.)

  8. Trial application of reliability technology to emergency diesel generators at the Trojan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Wong, S.M.; Boccio, J.L.; Karimian, S.; Azarm, M.A.; Carbonaro, J.; DeMoss, G.

    1986-01-01

    In this paper, a trial application of reliability technology to the emergency diesel generator system at the Trojan Nuclear Power Plant is presented. An approach for formulating a reliability program plan for this system is being developed. The trial application has shown that a reliability program process, using risk- and reliability-based techniques, can be interwoven into current plant operational activities to help in controlling, analyzing, and predicting faults that can challenge safety systems. With the cooperation of the utility, Portland General Electric Co., this reliability program can eventually be implemented at Trojan to track its effectiveness

  9. Application of laser processing for disassembly of nuclear power plants

    Science.gov (United States)

    Baranov, Gennady A.; Zinchenko, A. V.; Arutyunyan, R. B.

    1998-12-01

    Provision of safety and drop of ecological risk at salvaging of nuclear submarines (NSM) of Russia Navy Forces represents one of the most actual problems of nowadays. It is necessary to remove from services of Russian Navy Forces 170 - 180 nuclear submarines by 2000. At salvaging of Russian Navy Forces NSM it should be necessary to cut out reactor compartments with more than 150 thousand tons of gross weight and to fragment terminal carcasses of submarines with gross weight of 2 million tons. Taking into account overall dimensions of salvaging objects and Euro-standard requirement on the sizes of carcass fragments, for salvaging of one NSM it is necessary to execute more than 10 km of cuts. Using of conventional methods of gas and plasma cutting of ship constructions and equipment polluted with radioactive oxides and bedding of insulation and paint and varnish materials causes contamination of working zones and environment by a mix of radioactive substances and highly toxic combustion products, nomenclature of which includes up to 50 names. Calculations carried out in the Institute of industrial and Marine Medicine have shown that salvage of just one NSM with using of gas and plasma cutting are accompanied by discharge into an environment of up to 11.5 kg of chromium oxides, up to 22.5 kg of manganese oxides, up to 97 kg of carbon oxides and up to 650 kg of nitrogen oxides. Fragmentation of such equipment by a method of directional explosion or hydraulic jet is problematic because of complexity of treated constructions and necessity to create special protective facilities, which will accumulate a bulk of radioactive and toxic discharges, as a consequence of the explosion and spreaded by shock waves and water deluges. In a number of new technological processes the cutting with using of high-power industrial lasers radiation stands out. As compared with other technological processes, laser cutting has many advantages determined by such unique properties of laser

  10. Studies on environment safety and application of advanced reactor for inland nuclear power plants

    International Nuclear Information System (INIS)

    Wei, L.; Jie, L.

    2014-01-01

    To study environment safety assessment of inland nuclear power plants (NPPs), the impact of environment safety under the normal operation was researched and the environment risk of serious accidents was analyzed. Moreover, the requirements and relevant provisions of site selection between international nuclear power plant and China's are comparatively studied. The conclusion was that the environment safety assessment of inland and coastal nuclear power plant have no essential difference; the advanced reactor can meet with high criteria of environment safety of inland nuclear power plants. In this way, China is safe and feasible to develop inland nuclear power plant. China's inland nuclear power plants will be as big market for advanced reactor. (author)

  11. KWU Nuclear Plant Analyzer

    International Nuclear Information System (INIS)

    Bennewitz, F.; Hummel, R.; Oelmann, K.

    1986-01-01

    The KWU Nuclear Plant Analyzer is a real time engineering simulator based on the KWU computer programs used in plant transient analysis and licensing. The primary goal is to promote the understanding of the technical and physical processes of a nuclear power plant at an on-site training facility. Thus the KWU Nuclear Plant Analyzer is available with comparable low costs right at the time when technical questions or training needs arise. This has been achieved by (1) application of the transient code NLOOP; (2) unrestricted operator interaction including all simulator functions; (3) using the mainframe computer Control Data Cyber 176 in the KWU computing center; (4) four color graphic displays controlled by a dedicated graphic computer, no control room equipment; and (5) coupling of computers by telecommunication via telephone

  12. Stochastic models and reliability parameter estimation applicable to nuclear power plant safety

    International Nuclear Information System (INIS)

    Mitra, S.P.

    1979-01-01

    A set of stochastic models and related estimation schemes for reliability parameters are developed. The models are applicable for evaluating reliability of nuclear power plant systems. Reliability information is extracted from model parameters which are estimated from the type and nature of failure data that is generally available or could be compiled in nuclear power plants. Principally, two aspects of nuclear power plant reliability have been investigated: (1) The statistical treatment of inplant component and system failure data; (2) The analysis and evaluation of common mode failures. The model inputs are failure data which have been classified as either the time type of failure data or the demand type of failure data. Failures of components and systems in nuclear power plant are, in general, rare events.This gives rise to sparse failure data. Estimation schemes for treating sparse data, whenever necessary, have been considered. The following five problems have been studied: 1) Distribution of sparse failure rate component data. 2) Failure rate inference and reliability prediction from time type of failure data. 3) Analyses of demand type of failure data. 4) Common mode failure model applicable to time type of failure data. 5) Estimation of common mode failures from 'near-miss' demand type of failure data

  13. The application of PSA techniques to the vital area identification of nuclear power plants

    International Nuclear Information System (INIS)

    Ha, Jae Joo; Jung, Woo Sik; Park, Chang Kue

    2005-01-01

    This paper presents a Vital Area Identification (VAI) method based on the current Fault Tree Analysis (FTA) and Probabilistic Safety Assessment (PSA) techniques for the physical protection of nuclear power plants. A structured framework of a Top Event Prevention set Analysis (TEPA) application to the VAI of nuclear power plants is also delineated. One of the important processes for physical protection in a nuclear power plant is VIA that is a process for identifying areas containing nuclear materials, Structures, Systems or Components (SSCs) to be protected from sabotage, which could directly or indirectly lead to core damage and unacceptable radiological consequences. A software VIP (Vital area Identification Package based on the PSA method) is being developed by KAERI for the VAI of nuclear power plants. Furthermore, the KAERI fault tree solver FTREX (Fault Tree Reliability Evaluation eXpert) is specialized for the VIP to generate the candidates of the vital areas. FTREX can generate numerous MCSs for a huge fault tree with the lowest truncation limit and all possible prevention sets

  14. Application of neural network technology to nuclear plant thermal efficiency improvement

    International Nuclear Information System (INIS)

    Doremus, Rick; Allen Ho, S.; Bailey, James V.; Roman, Harry

    2004-01-01

    to determine which plant systems and components should be manipulated to increase electric output. Each parameter from the current data is replaced, one at a time, with an optimum value found among all the data used to train the neural networks. Each new data record, with one altered parameter, is then processed through the neural network, which calculates a predicted electric output These predictions are then ranked by order of increased electric output. Thermal Performance Engineers then review and perform selected recommendations An initial feasibility study was recently completed. The next phase of the project is the creation of a demonstration application to be tested at Salem Nuclear Generating Station. (author)

  15. Application of subsize specimens in nuclear plant life extension

    International Nuclear Information System (INIS)

    Rosinski, S.T.; Kumar, A.S.; Cannon, N.S.; Hamilton, M.L.

    1993-01-01

    The US Department of Energy is sponsoring a research effort through Sandia National Laboratories and the University of Missouri-Rolla to test a correlation for the upper shelf energy (USE) values obtained from the impact testing of subsize Charpy V-notch specimens to those obtained from the testing of full-size samples. The program involves the impact testing of unirradiated and irradiated full-, half-, and third-size Charpy V-notch specimens. To verify the applicability of the correlation on LWR materials, unirradiated and irradiated full-, half-, and third-size Charpy V-notch specimens of a commercial pressure vessel steel (ASTM A533 Grade B) will be tested. The correlation methodology is based on the partitioning of the USE into crack initiation and crack propagation energies. To accomplish this partition, both precracked and notched-only specimens will be used. Whereas the USE of notched-only specimens is the sum of both crack initiation and crack propagation energies, the USE of precracked specimens reflects only the crack propagation component. The difference in the USE of the two types of specimens represents a measure of the crack initiation energy. Normalizing the values of the crack initiation energy to the fracture volume of the sample produces similar values for the full-, half-, and third-size specimens. In addition, the ratios of the USE and the crack propagation energy are also in agreement for full-, half-, and third-size specimens. These two observations will be used to predict the USE of full-size specimens based on subsize USE data. This paper provides details of the program and presents results obtained from the application of the developed correlation methodology to the impact testing of the unirradiated full-, half-, and third-size A533 Grade B Charpy V-notch specimens

  16. Application of probabilistic safety goals to regulation of nuclear power plants in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Rzentkowski, G.; Akl, Y.; Yalaoui, S. [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

    2013-07-01

    In the Canadian nuclear regulatory framework, Safety Goals are formulated in addition to the deterministic design requirements and the dose acceptance criteria so that risk to the public that originates from accidents outside the design basis is considered. In principle, application of the Safety Goals ensures that the likelihood of accidents with serious radiological consequences is extremely low, and the potential radiological consequences from severe accidents are limited as far as practicable. Effectively, the Safety Goals extend the plant design envelope to include not only the capabilities of the plant to successfully cope with various plant states, but also practical measures to halt the progression of severe accidents. This paper describes the general approach to the development of the Safety Goals and their application to the existing nuclear power plants in Canada. This general approach is consistent with the currently accepted international practice and Canadian regulatory experience. The results of probabilistic safety assessments indicate that the Safety Goals meet or exceed international safety objectives due to effective implementation of the defence-in-depth principle in the reactor design and plant operation. At the same time, the application of the Safety Goals reveal that practicable measures exist to further enhance the overall level of reactor safety by focusing on severe accident prevention and mitigation. These measures are being currently implemented through refurbishment projects and feedback on operating experience. (author)

  17. Technical Survey on Applications of Wireless Sensor Networks in Nuclear Power Plants

    International Nuclear Information System (INIS)

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

    2014-01-01

    Even though there is no general consensus on using wireless technologies in nuclear power plants, potential applications of wireless sensor networks within nuclear power plants (NPPs) has been investigated. The topics of interests include potential interaction of wireless sensor networks with the sensitive protection equipment, radiation damage of the electronics on board sensor nodes, optimal placement of relay nodes that collect and forward data in the network, and possible applications, such as radiation dose and level monitoring, and equipment condition monitoring. Several wireless sensor networks have been deployed on site of NPPs on a trial basis to perform these tasks. Different aspects of deployment of such wireless sensor networks in NPPs have also been examined. Industrial standards or guidelines for deployment of WSNs in NPPs are also been considered. This paper examines the state of the art of wireless sensor networks in NPPs

  18. Technical Survey on Applications of Wireless Sensor Networks in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-08-15

    Even though there is no general consensus on using wireless technologies in nuclear power plants, potential applications of wireless sensor networks within nuclear power plants (NPPs) has been investigated. The topics of interests include potential interaction of wireless sensor networks with the sensitive protection equipment, radiation damage of the electronics on board sensor nodes, optimal placement of relay nodes that collect and forward data in the network, and possible applications, such as radiation dose and level monitoring, and equipment condition monitoring. Several wireless sensor networks have been deployed on site of NPPs on a trial basis to perform these tasks. Different aspects of deployment of such wireless sensor networks in NPPs have also been examined. Industrial standards or guidelines for deployment of WSNs in NPPs are also been considered. This paper examines the state of the art of wireless sensor networks in NPPs.

  19. The selective application of quality assurance activities to nuclear power plant items and services

    International Nuclear Information System (INIS)

    Anderson, J.W.

    1982-01-01

    The definition of quality assurance and the criteria for a quality assurance programme that are contained in both national and international codes and standards provide the principle of selective application of quality assurance activities for cost-effective results. The effective implementation of this principle requires a systematic and disciplined methodology that should be established by or for the owner at the beginning of a nuclear power plant project. The methodology that has proven to be successful generally includes a uniform method of classifying plant items and services at their lowest level of unit assembly and using that classification in the selection of applicable quality assurance activities and the specification of appropriate requirements for those activities. The applicable quality assurance activities are those to be implemented by the organizations designing, manufacturing, installing and operating plant items or performing support services. The methods and techniques provided illustrate the methodology and are one way by which a nuclear power plant project may translate the principle into application in order to achieve the desired results. (author)

  20. GERB viscous dampers in applications for pipelines and other components in Czechoslovak nuclear power plants

    International Nuclear Information System (INIS)

    Masopust, R.; Podrouzek, J.

    1992-01-01

    VISCODAMPERS from GERB, Germany, are now widely used as reliable shock restraints against earthquake and other shock effects for the most important safety-related pipelines and components in several Czechoslovak nuclear power plants. Having many technical advantages they are, at the same time, relatively inexpensive in comparison with conventional snubbers. Their properties are briefly described and several practical applications are explained. (author) 3 tabs., 9 figs., 8 refs

  1. GERB viscous dampers in application for pipelines and other components in nuclear power plants

    International Nuclear Information System (INIS)

    Masopust, R.; Podrouzek, J.; Zach, J.

    1993-01-01

    VISCODAMPERS from GERB, Germany, are now widely used as reliable shock restraints against earthquake and other shock effects for the most important safety-related pipelines and components in several Czech and Slovak nuclear power plants. Having many technical advantages they are, at the same time, relatively inexpensive in comparison to conventionally used snubbers. Their properties are briefly described and several practical applications are explained in this paper. (author)

  2. Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

    International Nuclear Information System (INIS)

    Ware, A.G.; Morton, D.K.; Nitzel, M.E.

    1995-03-01

    Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants

  3. Application of environmentally-corrected fatigue curves to nuclear power plant components

    International Nuclear Information System (INIS)

    Ware, A.G.; Morton, D.K.; Nitzel, M.E.

    1996-01-01

    Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four US nuclear steam supply system vendors. For each facility, six locations were studied including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This paper discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants

  4. On-line monitoring applications at nuclear power plants. A risk informed approach to calibration reduction

    International Nuclear Information System (INIS)

    Shankar, Ramesh; Hussey, Aaron; Davis, Eddie

    2003-01-01

    On-line monitoring of instrument channels provides increased information about the condition of monitored channels through accurate, more frequent evaluation of each cannel's performance over time. This type of performance monitoring is a methodology that offers an alternate approach to traditional time-directed calibration. EPRI's strategic role in on-line monitoring is to facilitate its implementation and cost-effective use in numerous applications at power plants. To this end, EPRI has sponsored an on-line monitoring implementation project at multiple nuclear plants specifically intended to install and use on-line monitoring technology. The selected on-line monitoring method is based on the Multivariate State Estimation Technique. The project has a planned three-year life; seven plants are participating in the project. The goal is to apply on-line monitoring to all types of power plant applications and document all aspects of the implementation process in a series of EPRI reports. These deliverables cover installation, modeling, optimization, and proven cost-benefit. This paper discusses the actual implementation of on-line monitoring to various nuclear plant instrument systems. Examples of detected instrument drift are provided. (author)

  5. Criteria for selecting measures of plant information with application to nuclear reactors

    International Nuclear Information System (INIS)

    Kiguchi, T.; Sheridan, T.B.

    1979-01-01

    Criteria for selecting from alternative measures of plant information have been derived by information theory and the expected-value model of decision theory. Two criteria derived by information theory are minimum ''uncertainty'' of judgement of plant states, and maximum ''surprise'' of human operators. Two criteria derived by decision theory are maximum expected reward to operators, and maximum ratio of the maximum and next-to-maximum expected rewards. These four criteria have been evaluated experimentally in application to human monitoring problems of three ''plants'': an abstract laboratory exercise, a small research reactor, and a conventional nuclear power plant (high-fidelity training simulator). The results show that the criteria derived by decision theory are superior to the others from the viewpoint of correct rate of human subjects' judgement

  6. The application of gamma-spectrometry to nuclear power plant (NPP) and environment

    International Nuclear Information System (INIS)

    Asgharizadeh, Farid.

    1995-01-01

    One of measuring systems is nuclear spectrometry, particularly Gamma-Ray Spectrometry, to measure and determine the radionuclide concentration within plant materials and environmental samples. There are four major applied techniques related to Nuclear Power Plant operation and environmental monitoring aspects. Some details about gamma ray spectrometry technique is discussed in chapter 2. The main emphasis is on the calculation of gamma-ray detector efficiency for different geometries, the minimum detectable activity concepts and dead-time correction. Also,some formula and relations are introduced. In chapter 3, the major applications of gamma-ray spectrometry for analysis of nuclear power plant and environmental samples are discussed. These applications are divided into four topics: Nuclear Fuel survey; based on the activity of fission products concentration in reactor coolant, two other applications are introduced: Fuel Burnup calculation and the calculation of rated activity of natural radionuclides in construction of materials which is the last and most important application: Measurement and determination of radionuclides activity concentr[[[[n in environmental samples is described through section 3.3 Sampling and measuring methods for research and monitoring aspects is evaluated. Some data about sample preparation methods such as pretreatment and solubilization procedures are presented. Quantitative chemical separations of trace constituents from complex sample materials invariably require meticulous work by an analytical chemist. The radiochemical separation deals with this subject. Instrumental aspects, relate to gamma-ray spectrometry, quality assurance, presentation and reporting of results are described. In the experimental part, determination of radionuclides concentration in sediment sample is presented

  7. Application of NASA Kennedy Space Center System Assurance Analysis methodology to nuclear power plant systems designs

    International Nuclear Information System (INIS)

    Page, D.W.

    1985-01-01

    In May of 1982, the Kennedy Space Center (KSC) entered into an agreement with the NRC to conduct a study to demonstrate the feasibility and practicality of applying the KSC System Assurance Analysis (SAA) methodology to nuclear power plant systems designs. North Carolina's Duke Power Company expressed an interest in the study and proposed the nuclear power facility at CATAWBA for the basis of the study. In joint meetings of KSC and Duke Power personnel, an agreement was made to select two CATAWBA systems, the Containment Spray System and the Residual Heat Removal System, for the analyses. Duke Power provided KSC with a full set of Final Safety Analysis Reports (FSAR) as well as schematics for the two systems. During Phase I of the study the reliability analyses of the SAA were performed. During Phase II the hazard analyses were performed. The final product of Phase II is a handbook for implementing the SAA methodology into nuclear power plant systems designs. The purpose of this paper is to describe the SAA methodology as it applies to nuclear power plant systems designs and to discuss the feasibility of its application. (orig./HP)

  8. Procedure for the qualification of a manufacturer of ingot iron pieces for application in nuclear power plant components

    International Nuclear Information System (INIS)

    Rahn, K.M.M.; Jusevicius, E.; Michael, H.

    1981-01-01

    The process for the qualification of 'Sao Caetano do Sul (Acos Villares S/A)' Plant as manufacturers of ingot iron pieces for application in components of Angra 2 and Angra 3 Nuclear Power Plants, is presented. The qualification was executed by IBQN - Instituto Brasileiro de Qualidade Nuclear - the organ officially in charge of the execution of qualification of suppliers of materials for the nuclear industry. (E.G.) [pt

  9. Applicability of base-isolation R ampersand D in non-reactor facilities to a nuclear reactor plant

    International Nuclear Information System (INIS)

    Seidensticker, R.W.; Chang, Y.W.

    1990-01-01

    Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. The question, therefore, is to what extent can research and development (R ampersand D) for non-nuclear use be used to provide technological data needed for seismic isolation of a nuclear power plant. This question, of course is not unique to seismic isolation. Virtually every structural component, system, or piece of equipment used in nuclear power plants is also used in non- nuclear facilities. Experience shows that considerable effort is needed to adapt conventional technology into a nuclear power plant. Usually, more thorough analysis is required, material and fabrication quality-control requirements are more stringent as are controls on field installation. In addition, increased emphasis on maintainability and inservice inspection throughout the life of the plant is generally required to gain acceptance in nuclear power plant application. This paper reviews the R ampersand D programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R ampersand D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R ampersand D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs

  10. Application condition of optical communication technique in the nuclear power plants

    International Nuclear Information System (INIS)

    Sakurai, Jun

    1999-01-01

    As the optical communication technique can process rapidly a lot of information and exclude perfectly error action due to noise, it is adopted gradually to commercial and company communications (containing operational managements in large scale facilities) in worldwide scale in stead of conventional communication technique (containing operational controls and measurements). In application to the nuclear power plants, as forming not only change in properties but also deterioration due to radiation damage in many cases of exposure to various types of radiations such as neutron, gamma-ray, and so forth in difference with conventional using environment, its using range is limited at present. In future, development of optical fibers or elements with excellent high temperature and radiation resistances usable stably at reactor core for a long time is essential. The regular application of the optical communication technique at the nuclear power plants begins just now, which is an expected field for future large development. And, for the old nuclear power plant in present operation, substitution to the optical communication technique in accompany with replace of appliances at periodical inspections will also be conducted. Its response is already required rapidly in the Tokyo Electric Power Co., Ltd.. (G.K.)

  11. 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)

  12. Environmental Standard Review Plan for the review of license renewal applications for nuclear power plants

    International Nuclear Information System (INIS)

    O'Brien, J.; Kim, T.J.; Reynolds, S.

    1991-08-01

    The Environmental Standard Review Plan for the Review of License Applications for Nuclear Power Plants (ESRP-LR) is to be used by the NRC staff when performing environmental reviews of applications for the renewal of power reactor licenses. The use of the ESRP-LR provides a framework for the staff to determine whether or not environmental issues important to license renewal have been identified and the impacts evaluated and provides acceptance standards to help the reviewers comply with the National Environmental Policy Act

  13. Rough set theory and its application in fault diagnosis in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Chen Zhihui; Nuclear Power Inst. of China, Chengdu; Xia Hong; Huang Wei

    2006-01-01

    Rough Set theory is the mathematic theory that can express and deal with vague and uncertain data. There is complicated and uncertain data in the fault feature of Nuclear Power Plant, so that Rough Set theory can be introduced to analyze and process the historical data to find out the rule of fault diagnosis of Nuclear Power Plant. This paper introduces the Rough Set theory and Knowledge Acquisition briefly, and describes the reduction algorithm based on discernibility matrix and its application in the fault diagnosis to generate rules of diagnosis. Using these rules, three kinds of model faults have been diagnosed correctly. The conclusion can be drawn that this method can reduce the redundancy of the fault feature, simplify and optimize the rule of diagnosis. (authors)

  14. Application of an estimation model to predict future transients at US nuclear power plants

    International Nuclear Information System (INIS)

    Hallbert, B.P.; Blackman, H.S.

    1987-01-01

    A model developed by R.A. Fisher was applied to a set of Licensee Event Reports (LERs) summarizing transient initiating events at US commercial nuclear power plants. The empirical Bayes model was examined to study the feasibility of estimating the number of categories of transients which have not yet occurred at nuclear power plants. An examination of the model's predictive ability using an existing sample of data provided support for use of the model to estimate future transients. The estimate indicates that an approximate fifteen percent increase in the number of categories of transient initiating events may be expected during the period 1983--1993, assuming a stable process of transients. Limitations of the model and other possible applications are discussed. 10 refs., 1 fig., 3 tabs

  15. Application of PSA to Assess the Safety Level of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Berg, H. P.; Goertz, R.

    2000-01-01

    This paper reviews the application of PSA in German nuclear power plant regulation. From a fundamental point of view, it has to be mentioned that as stipulated in the corresponding requirements, regulatory decision making in Germany is primarily based on deterministic analyses and evaluations. Therefore, PSA is not used as a stand alone but as a supplementary basis. In this context PSA has developed a valuable tool with continuously growing importance. Level 1+ PSAs are now elaborated for all German nuclear power plants in operation, most of them are already reviewed by the competent supervisory authority and its experts. Current research activities on the federal level primarily concentrate on the further development of the methodology in the areas human factor, common cause failures, accident management measures and reduction of uncertainties in methods and data. (author)

  16. A note on the application of probabilistic structural reliability methodology to nuclear power plants

    International Nuclear Information System (INIS)

    Maurer, H.A.

    1978-01-01

    The interest shown in the general prospects of primary energy in European countries prompted description of the actual European situation. Explanation of the needs for installation of nuclear power plants in most contries of the European Communities are given. Activities of the Commission of the European Communities to initiate a progressive harmonization of already existing European criteria, codes and complementary requirements in order to improve the structural reliability of components and systems of nuclear power plants are summarized. Finally, the applicability of a probabilistic safety analysis to facilitate decision-making as to safety by defining acceptable target and limit values, coupled with a subjective estimate as it is applied in the safety analyses performed in most European countries, is demonstrated. (Auth.)

  17. Artificial intelligence applications to the surveillance and diagnostics of nuclear power plants

    International Nuclear Information System (INIS)

    Zwingelstein, G.; Monnier, B.

    1985-01-01

    Artificial intelligence has come of age; it can be applied with benefits in the nuclear industry for various applications to improve both plant safety and availability. This paper presents four rule-based expert systems currently under development at Electricite de France for the surveillance and the diagnostics of pressurized water reactors (PWRs). The objectives of these experiences with expert system projects are to demonstrate their feasibility, to provide an evaluation of their potential benefits through on-site implementation, to identify the problems due to the knowledge extraction and representation, and finally to specify the classes of problems where expert systems are needed and useful. The specific goals of these expert systems are to provide an aid for the detection and location of failures occurring in nuclear plants

  18. Benchmarking Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jakic, I.

    2016-01-01

    One of the main tasks an owner have is to keep its business competitive on the market while delivering its product. Being owner of nuclear power plant bear the same (or even more complex and stern) responsibility due to safety risks and costs. In the past, nuclear power plant managements could (partly) ignore profit or it was simply expected and to some degree assured through the various regulatory processes governing electricity rate design. It is obvious now that, with the deregulation, utility privatization and competitive electricity market, key measure of success used at nuclear power plants must include traditional metrics of successful business (return on investment, earnings and revenue generation) as well as those of plant performance, safety and reliability. In order to analyze business performance of (specific) nuclear power plant, benchmarking, as one of the well-established concept and usual method was used. Domain was conservatively designed, with well-adjusted framework, but results have still limited application due to many differences, gaps and uncertainties. (author).

  19. Nuclear power plant life management: flow accelerated corrosion and chemical control. Application to Embalse Nuclear power plant

    International Nuclear Information System (INIS)

    Chocron, Mauricio; Saucedo, Ramona E.; Sainz, Ricardo A.; Ovando, Luis E.

    2006-01-01

    The chemistry of a water-steam cycle is one of the main aspects of the Plant Life Management of a Nuclear Power Plant and it is important for the preservation, efficiency and availability of the whole system. In that sense this aspect has to be prioritized in any study whose aim is the life extension of the plant. In particular, the flow-assisted -corrosion or FAC is a problem that worldwide has been considered important due to the piping wall thinning that in some occasions has led to severe accidents. The FAC phenomena is not easy to be interpreted and addressed although nowadays there are some accepted models to understand and predict sensitive areas of the cycle. The objectives of the present paper have been: a) The construction of an integrated code that involves all the aspects that have influence on FAC, i.e., materials, composition, geometry, temperature and flow rate, quality, chemistry, etc.; b) Establish or adapting current models to the circuit of Embalse PHWR NPP; c) Identify new locations for inspection and wall thickness measurement in order to predict residual life; d) Compare different chemistries and e) handle large sets of inspection data. Among the results, new lines have been incorporated to the inspection schedule of the 2005' programmed outage. Also, the evaluation is part of the PLIM-PLEX programme at Embalse-N.A.S.A. in collaboration with C.N.E.A. is being carried out. (author)

  20. Possible uses and applications of drones in a nuclear power plant

    International Nuclear Information System (INIS)

    Celis del A, L.; Palacios, J.; Rivero, T.; Valero, D.

    2016-09-01

    The versatility of drones is one of the strengths that have led to the rapid development of this technology, as they adapt relatively easily to new applications, presenting considerable advantages such as greater energy efficiency, longer life and a significant lower operation cost than manned systems. The current applications of the drones, in addition to the military, are very wide and varied. The nuclear industry represents an important area of opportunity for drones, mainly in response to radiological emergencies, since in this case there is a latent risk of the general population being exposed to high radiation doses. Drones can be used in environments with high chemical and radiological toxicity without endangering human lives. Some of the possible applications of the drones in a nuclear power plant are: perimeter surveillance in physical security, where equipped with a high definition camera can be used as support to physical security systems in general; visual inspection at sites, structures, equipment and pipelines, etc., as part of preventive maintenance in order to avoid the loss of material due to corrosion, oxidation, cracking, subsidence; the visual inspection through thermo-graphic images to be able to detect hot spots in some critical element; measurement and radiological mapping on surfaces to maintain monitoring of radiological safety at nuclear power plant facilities; the monitoring of environmental parameters and the Environmental Impact Assessment to obtain important information to determine the environmental impact of a given area; and accident support by providing information that allows staff to size the magnitude of the damage. (Author)

  1. Nuclear plant license renewal

    International Nuclear Information System (INIS)

    Gazda, P.A.; Bhatt, P.C.

    1991-01-01

    During the next 10 years, nuclear plant license renewal is expected to become a significant issue. Recent Electric Power Research Institute (EPRI) studies have shown license renewal to be technically and economically feasible. Filing an application for license renewal with the Nuclear Regulatory Commission (NRC) entails verifying that the systems, structures, and components essential for safety will continue to perform their safety functions throughout the license renewal period. This paper discusses the current proposed requirements for this verification and the current industry knowledge regarding age-related degradation of structures. Elements of a license renewal program incorporating NRC requirements and industry knowledge including a schedule are presented. Degradation mechanisms for structural components, their significance to nuclear plant structures, and industry-suggested age-related degradation management options are also reviewed

  2. Probabilistic safety analysis for nuclear fuel cycle facilities, an exemplary application for a fuel fabrication plant

    International Nuclear Information System (INIS)

    Gmal, B.; Gaenssmantel, G.; Mayer, G.; Moser, E.F.

    2013-01-01

    In order to assess the risk of complex technical systems, the application of the Probabilistic Safety Assessment (PSA) in addition to the Deterministic Safety Analysis becomes of increasing interest. Besides nuclear installations this applies to e. g. chemical plants. A PSA is capable of expanding the basis for the risk assessment and of complementing the conventional deterministic analysis, by which means the existing safety standards of that facility can be improved if necessary. In the available paper, the differences between a PSA for a nuclear power plant and a nuclear fuel cycle facility (NFCF) are discussed in shortness and a basic concept for a PSA for a nuclear fuel cycle facility is described. Furthermore, an exemplary PSA for a partial process in a fuel assembly fabrication facility is described. The underlying data are partially taken from an older German facility, other parts are generic. Moreover, a selected set of reported events corresponding to this partial process is taken as auxiliary data. The investigation of this partial process from the fuel fabrication as an example application shows that PSA methods are in principle applicable to nuclear fuel cycle facilities. Here, the focus is on preventing an initiating event, so that the system analysis is directed to the modeling of fault trees for initiating events. The quantitative results of this exemplary study are given as point values for the average occurrence frequencies. They include large uncertainties because of the limited documentation and data basis available, and thus have only methodological character. While quantitative results are given, further detailed information on process components and process flow is strongly required for robust conclusions with respect to the real process. (authors)

  3. Evaluation of the Latest Generic Data for PSA Applications of Domestic Nuclear Plants

    International Nuclear Information System (INIS)

    Hwang, Seok Won; Oh, Ji Yong; Lee, Byung Sik

    2009-01-01

    Generic data of domestic PSAs have mostly referred to 'Advanced Light Water Reactor (ALWR) Utility Requirements Document (URD) 'issued by EPRI. Generally, current data of domestic PSA have been customized with the generic and plant specific data through Bayesian analysis. The generic reference has established by collecting US nuclear plant practices from mid 1980s to early 1990s. Over the decade, US plants had showed low performances and capabilities in operation. On the other hand, the current domestic nuclear plants shows world class performance in operation and maintenance compared with the corresponding US nuclear plants in URD. Therefore, it is necessary to apply proper generic sources which can represent the current domestic plant performances and status. In 2007, the latest generic source (NUREG/CR-6928) is published by US NRC, which deals with new types of failure modes and analysis methods. A fundamental improvement in NUREG/CR-6928 compared with previous data source is the distinction between standby and alternating/running component basic events, which shows different failure mechanisms. Significant differences were also noted running failure events occurred within and beyond the first hour for emergency diesel generators, cooling units, and pumps. This was done because the historical perspective on running failure rates indicated approximately a factor of 15 differences between the two failure rates for several component types. ALWR URD uses lognormal distribution in the estimation of failure rates. On the contrary, NUREG/CR-6928 uses beta and gamma distributions for demand and running failures, respectively. This work has proposed an approach to the application of NUREG/CR-6928 to current PSA practice by comparing it with URD data. Moreover, this attempt results in eliciting substantial insights of the establishment of the domestic generic database

  4. Design and application of the HTR-100 industrial nuclear power plant

    International Nuclear Information System (INIS)

    Brandes, S.; Kohl, W.

    1988-01-01

    The small HTR-100 high temperature reactor combines the reactor concept of the AVR reactor, which has been proven for 20 years, with the latest component technology of the THTR power plant which has been in operation since 1985. The nuclear heat supply system is conceived so as to be applicable for the generation of electric power, district heat and process steam according to the customer's demand. The HTR-100 reactor has a thermal power of 258 MW and offers steam parameters of 190 bar/530 0 C. To cover a higher power demand HTR-100 reactors can be combined forming a larger power plant. Economic analyses have shown competitiveness with fossil power plants. (orig.)

  5. Application of Entry-Time Processes to Asset Management in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Nelson, Paul; Wang, Shuwen; Kee, Ernie J.

    2006-01-01

    The entry-time approach to dynamic reliability is based upon computational solution of the Chapman-Kolmogorov (generalized state-transition) equations underlying a certain class of marked point processes. Previous work has verified a particular finite-difference approach to computational solution of these equations. The objective of this work is to illustrate the potential application of the entry-time approach to risk-informed asset management (RIAM) decisions regarding maintenance or replacement of major systems within a plant. Results are presented in the form of plots, with replacement/maintenance period as a parameter, of expected annual revenue, along with annual variance and annual skewness as indicators of associated risks. Present results are for a hypothetical system, to illustrate the capability of the approach, but some considerations related to potential application of this approach to nuclear power plants are discussed. (authors)

  6. Application of Field Programmable Gate Arrays in Instrumentation and Control Systems of Nuclear Power Plants

    International Nuclear Information System (INIS)

    2016-01-01

    Field programmable gate arrays (FPGAs) are gaining increased attention worldwide for application in nuclear power plant (NPP) instrumentation and control (I&C) systems, particularly for safety and safety related applications, but also for non-safety ones. NPP operators and equipment suppliers see potential advantages of FPGA based digital I&C systems as compared to microprocessor based applications. This is because FPGA based systems can be made simpler, more testable and less reliant on complex software (e.g. operating systems), and are easier to qualify for safety and safety related applications. This publication results from IAEA consultancy meetings covering the various aspects, including design, qualification, implementation, licensing, and operation, of FPGA based I&C systems in NPPs

  7. Materials Integrity Analysis for Application of Hyper Duplex Stainless Steels to Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Chang, Hyun Young; Park, Heung Bae; Park, Yong Soo; Kim, Soon Tae; Kim, Young Sik; Kim, Kwang Tae; Jhang, Yoon Young

    2010-01-01

    Hyper duplex stainless steels have been developed in Korea for the purpose of application to the seawater system of Korean nuclear power plants. This system supplies seawater to cooling water heat exchanger tubes, related pipes and chlorine injection system. In normal operation, seawater is supplied to heat exchanger through the exit of circulating water pump headers, and the heat exchanged sea water is extracted to the discharge pipes in circulating water system connected to the circulating water discharge lines. The high flow velocity of some part of seawater system in nuclear power plants accelerates damages of components. Therefore, high strength and high corrosion resistant steels need to be applied for this environment. Hyper duplex stainless steel (27Cr-7.0Ni-2.5Mo-3.2W-0.35N) has been newly developed in Korea and is being improved for applying to nuclear power plants. In this study, the physical and mechanical properties and corrosion resistance of newly developed materials are quantitatively evaluated in comparative to commercial stainless steels in other countries. The properties of weld and HAZ (heat affected zone) are analyzed and the best compositions are suggested. The optimum conditions in welding process are derived for ensuring the volume fraction of ferrite(α) and austenite(γ) in HAZ and controlling weld cracks. For applying these materials to the seawater heat exchanger, CCT and CPT in weldments are measured. As a result of all experiments, it was found that the newly developed hyper duplex stainless steel WREMBA has higher corrosion resistance and mechanical properties than those of super austenitic stainless steels including welded area. It is expected to be a promising material for seawater systems of Korean nuclear power plants

  8. Modelling and data prerequisites for specific applications of PSA in the management of nuclear plant safety

    International Nuclear Information System (INIS)

    1994-04-01

    The IAEA has a programme which supports the performance and use of probabilistic safety assessments (PSAS) to improve nuclear safety internationally. The assistance offered in this areas by the IAEA to Member States has traditionally focused on planning, performance and peer review of PSAs. PSA activities within the IAEA's programme in the area of applications are presently being expanded. The various applications of PSAs require that PSAs being developed have certain characteristics in terms of their scope, the degree of details in the modelling, the flexibility in performing desired calculations, the quality and type of the data used, and the assumptions made in treating safety significant aspects. In many cases, existing PSAs or PSAs being completed can be extended to fulfill the requirements for uses in many applications to enhance the safety of nuclear power plants. This report provides information on how to carry such extensions by matching PSA characteristics to various applications that are being considered. This report was prepared by consultants together with the IAEA following the recommendations of a Technical Committee Meeting on PSA Requirements for Use in Safety Management, held by the IAEA in co-operation with the Swedish Nuclear Power Inspectorate in Stockholm, Sweden, 16-20 September 1991. 42 refs, 1 tab

  9. Very small HTGR nuclear power plant concepts for special terrestrial applications

    International Nuclear Information System (INIS)

    McDonald, C.F.; Goodjohn, A.J.

    1983-01-01

    The role of the very small nuclear power plant, of a few megawatts capacity, is perceived to be for special applications where an energy source as required but the following prevail: 1) no indigenous fossil fuel source, in long transport distances that add substantially to the cost of oil, coal in gas, and 3) secure long-term power production for defense applications with freedom from fuel supply lines. A small High Temperature Gas-Cooled reactor (HTGR) plant could provide the total energy needs for 1) a military installation, 2) an island base of strategic significance, 3) an industrial community or 4) an urban area. The small HTGR is regarded as a fixed-base installation (as opposed to a mobile system). All of the major components would be factory fabricated and transported to the site where emphasis would be placed on minimizing the construction time. The very small HTGR plant, currently in an early stage of design definition, has the potential for meeting the unique needs of the small energy user in both the military and private sectors. The plant may find acceptance for specialized applications in the industrialized nations and to meet the energy needs of developing nations. Emphasis in the design has been placed on safety, simplicity and compactness

  10. Application of RFID to High-Reliability Nuclear Power Plant Construction

    International Nuclear Information System (INIS)

    Kenji Akagi; Masayuki Ishiwata; Kenji Araki; Jun-ichi Kawahata

    2006-01-01

    In nuclear power plant construction, countless variety of parts, products, and jigs more than one million are treated under construction. Furthermore, strict traceability to the history of material, manufacturing, and installation is required for all products from the start to finish of the construction, which enforce much workforce and many costs at every project. In an addition, the operational efficiency improvement is absolutely essential for the effective construction to reduce the initial investment for construction. As one solution, RFID (Radio Frequent Identification) application technology, one of the fundamental technologies to realize a ubiquitous society, currently expands its functionality and general versatility at an accelerating pace in mass-production industry. Hitachi believes RFID technology can be useful of one of the key solutions for the issues in non-mass production industry as well. Under this situation, Hitachi initiated the development of next generation plant concept (ubiquitous plant construction technology) which utilizes information and RFID technologies. In this paper, our application plans of RFID technology to nuclear power is described. (authors)

  11. Application of integrated logistic techniques to operation, maintenance and re engineering processes in Nuclear Power plants

    International Nuclear Information System (INIS)

    Santiago Diez, P.

    1997-01-01

    This paper addresses the advisability of adapting and applying management and Integrated Logistic engineering techniques to nuclear power plants instead of using more traditional maintenance management methods. It establishes a historical framework showing the origins of integrated approaches based on traditional logistic support concepts, their phases and the real results obtained in the aeronautic world where they originated. It reviews the application of integrated management philosophy, and logistic support and engineering analysis techniques regarding Availability, Reliability and Maintainability (ARM) and shows their inter dependencies in different phases of the system's life (Design, Development and Operation). It describes how these techniques are applied to nuclear power plant operation, their impact on plant availability and the optimisation of maintenance and replacement plans. The paper analyses the need for data (type and volume), which will have to be collected, and the different tools to manage such data. It examines the different CALS tools developed by EA for engineering and for logistic management. It also explains the possibility of using these tools for process and data operations through the INTERNET. It also focuses on the qualities of some simple examples of possible applications, and how they would be used in the framework of Integrated Logistic Support (ILS). (Author)

  12. Application of RFID to High-Reliability Nuclear Power Plant Construction

    Energy Technology Data Exchange (ETDEWEB)

    Akagi, Kenji; Ishiwata, Masayuki; Araki, Kenji; Kawahata, Jun-ichi [Hitachi, Ltd. (Japan)

    2006-07-01

    In nuclear power plant construction, countless variety of parts, products, and jigs more than one million are treated under construction. Furthermore, strict traceability to the history of material, manufacturing, and installation is required for all products from the start to finish of the construction, which enforce much workforce and many costs at every project. In an addition, the operational efficiency improvement is absolutely essential for the effective construction to reduce the initial investment for construction. As one solution, RFID (Radio Frequent Identification) application technology, one of the fundamental technologies to realize a ubiquitous society, currently expands its functionality and general versatility at an accelerating pace in mass-production industry. Hitachi believes RFID technology can be useful of one of the key solutions for the issues in non-mass production industry as well. Under this situation, Hitachi initiated the development of next generation plant concept (ubiquitous plant construction technology) which utilizes information and RFID technologies. In this paper, our application plans of RFID technology to nuclear power is described. (authors)

  13. Risk management on nuclear power plant. Application of probabilistic risk assessment

    International Nuclear Information System (INIS)

    Kojima, Shigeo

    2003-01-01

    In U.S.A., nuclear safety regulation is moving to risk-informed regulation (RIR), so necessity of a standard to provide contents of probabilistic risk assessment (PRA) constructing its roots has been discussed for a long time. In 1998, the Committee on Nuclear Risk Management (CNRM) of the American Society of Mechanical Engineers (ASME) began to investigate the standard, of which last edition was published as the Standard for Probabilistic Risk Management for Nuclear Power Plant Applications: RA-S-2002 (PRMA) on April, 2002. As in the Committee, the Nuclear Regulatory Commission (NRC), electric power companies, national institutes, PRA specialists, and so on took parts to carry out many discussions with full energies of participants on risk management in U.S.A., the standard was finished after about four years' efforts. In U.S.A., risk management having already used PRA is successfully practiced, U.S.A. is at a stage with more advancing steps of the risk management than Japan is. Here was described on the standard of PRA and a concrete method of the risk management carried out at nuclear power stations. (G.K.)

  14. Survey of networked control systems and their potential applications in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kadri, A. [Univ. of Western Ontario, Dept. of Electrical and Computer Engineering, London, Ontario (Canada)]. E-mail: akadri@uwo.ca

    2006-07-01

    This paper provides an overview of networked control systems (NCSs) and their industrial applications. Most widely used NCSs based on fieldbus technologies; namely, ControlNet, Profibus (DP/PA), and Foundation Fieldbus have been discussed. The objectives and benefits of using such networks are presented and factors influencing their design and implementation are examined. Then, some of the special requirements in controlling nuclear power plant (NPP) have been considered. The potential of applying networked control systems in such installations has been discussed. Finally, the concept of wireless networked control systems is also described. (author)

  15. The application of CFD to hydrogen risk analysis in nuclear power plants

    International Nuclear Information System (INIS)

    Wang Hui; Han Xu; Chang Meng; Wang Xiaofeng; Wang Shuguo; Lu Xinhua; Wu Lin

    2013-01-01

    Status of the hydrogen risk analysis method is systemically summarized in this paper and the advantages and limits of CFD (Computational Fluid Dynamic) in hydrogen risk analysis is discussed. The international experimental programs on the CFD hydrogen risk analysis are introduced in this paper. The application of CFD to nuclear power plant (NPP) hydrogen risk analysis is introduced in detail by taking EPR and Ling'ao NPP for example. In these bases, the CFD development prospect of hydrogen risk analysis is also summarized in this paper. (authors)

  16. Fuzzy logic and artificial neural networks for nuclear power plant applications

    International Nuclear Information System (INIS)

    Berkan, R.C.; Eryurek, E.; Upadhyaya, B.R.

    1992-01-01

    This paper discusses the feasibility of applying fuzzy logic and neural networks to plant-wide monitoring, diagnostics, and control problems. Different data sets are gathered from several sources including two commercial Pressurized Water Reactors (PWR), the Experimental Breeder Reactor-II (EBR-II), and the conceptual design of Modular Liquid-Metal Reactor (PRISM). These data sets are used to illustrate applications to operating processes, and to PRISM design. The results show that the artificial intelligence approach to a number of operational tasks can considerably improve the safety and availability of nuclear power generation

  17. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    Wood, R.S.

    1991-07-01

    This report indicates percentage ownership of commercial nuclear power plants by utility companies. The report includes all plants operating, under construction, docketed for NRC safety and environmental reviews, or under NRC antitrust review, but does not include those plants announced but not yet under review or those plants formally cancelled. Part 1 of the report lists plants alphabetically with their associated applicants or licensees and percentage ownership. Part 2 lists applicants or licensees alphabetically with their associated plants and percentage ownership. Part 1 also indicates which plants have received operating licenses (OLS)

  18. Selective application of revised source terms to operating nuclear power plants

    International Nuclear Information System (INIS)

    Moon, Joo Hyun; Song, Jae Hyuk; Lee, Young Wook; Ko, Hyun Seok; Kang, Chang Sun

    2001-01-01

    More than 30 years later since 1962 when TID-14844 was promulgated, there has been big change of the US NRC's regulatory position in using accident source terms for radiological assessment following a design basis accident (DBA). To replace the instantaneous source terms of TID-14844, the time-dependent source terms of NUREG-1465 was published in 1995. In the meantime, the radiological acceptance criteria for reactor site evaluation in 10 CFR Part 100 were also revised. In particular, the concept of total effective dose equivalent has been incorporated in accordance with the radiation protection standards set forth in revised 10 CFR Part 20. Subsequently, the publication of Regulatory Guide 1.183 and the revision of Standard Review Plan 15.0.1 followed in 2000, which provided the licensee of operating nuclear power reactor with the acceptable guidance of applying the revised source term. The guidance allowed the holder of an operating license issued prior to January 10, 1997 to voluntarily revise the accident source terms used in the radiological consequence analyses of DBA. Regarding to its type of application, there suggested full and selective applications, Whether it is full or selective, based upon the scope and nature of associated plant modifications being proposed, the actual application of the revised source terms to an operating plant is expected to give a large impact on its facility design basis. Considering scope and cost of the analyses required for licensing, selective application is seemed to be more appealing to an licensee of the operating plant rather than full application. In this paper, hence, the selective application methodology is reviewed and is actally applied to the assessment of offsite radiological consequence following a LOCA at Ulchin Unit 3 and 4, in order to identify and analyze the potential impacts due to application of revised source terms and to assess the considerations taken in each application prior to its actual

  19. Development of wall thinning screening system and its application to a commercial nuclear power plant

    International Nuclear Information System (INIS)

    Ryu, Kyung Ha; Hwang, Il Soon; Kim, Ji Hyun

    2013-01-01

    Highlights: • Wall loss screening system (WalSS) has been developed based on ES-DCPD method. • Screening criteria was established based on the thinning of the actual shape that occur in the power plant. • With the criteria, the WalSS gives priority of the need for inspection. • This technique was successfully applied to commercial nuclear power plant. - Abstract: A new non-destructive evaluation (NDE) method has been developed for metal pipes for the detection wall thinning. The method has been showed to be suitable for applications to electric power generation plants where flow accelerated corrosion (FAC) of carbon steel piping is a significant cause of increased maintenance and plant personnel casualty. The wall thinning screening system (WalSS) was developed in two major phases. In the first phase, the equipotential switching direct current potential drop (ES-DCPD) method was developed for piping wall (Ryu et al., 2008a, 2010). In the second phase, in this paper, a quantitative detection criteria was developed. The relative ES-DCPD change of 3.8% has been defined as the screening criteria for wall thinning schematization. This criteria means that the component with measured ES-DCPD change greater than 3.8% is called for a more comprehensive examination. In the criteria development, all variables were taken into consideration based on commercial plant piping inspection data such as initial thickness distributions, wall thinning shape and nominal thickness. The developed WalSS based on ES-DCPD was applied to a moisture separator reheater (MSR) drain line of a commercial nuclear power plant (NPP) during a scheduled overhaul. The measured ES-DCPD change was 2.16%, which is lower than the ES-DCPD criteria, identifying the pipe having adequate wall thickness. This is confirmed by site thickness inspection using ultrasonic technique (UT)

  20. Applicable approach of the wireless technology for Korean nuclear power plants

    International Nuclear Information System (INIS)

    Ko, Do Young; Lee, Soo Ill

    2013-01-01

    Highlights: • To apply wireless technology for Korean NPPs, several stipulations are proposed. • WLAN is proposed as the most appropriate wireless technology for Korean NPPs. • WLAN can be applied to the specific fields except in the control system. • An attitude survey on wireless showed that 94.7% agree with the necessity of wireless. - Abstract: Recently, many nuclear power plants (NPPs) over the world use various types of wireless systems for the advantages. Unfortunately, wireless technologies are not currently installed in any Korean NPPs because it is difficult to solve the negative impact of unexpected outcomes or failures from the influence of the wireless technologies, which is electromagnetic interference and radio-frequency interference (EMI/RFI). Moreover, a lack of desire on the part of Korean nuclear industry to implement it leads to give up benefit from the wireless technologies. To install the wireless technologies with maximum benefit and minimum risk, a systematic approach, which quantify the negative impact and prevent the influence, is essential; therefore, this paper describes an applicable research result on the wireless technology for Korean NPPs based on regulatory guides and current wireless hardware and software technologies. Also, survey on the needs for the wireless technology for Korean nuclear power plants was conducted, because the level of awareness of workers in NPPs regarding wireless technologies is very important issue. In this paper, we propose an applicable system to enhance the applicability for the wireless technology for Korean NPPs. The result based on proposed applicable system shows that wireless local area network (WLAN) is the representative candidate for Korean NPPs, which can be applied to the specific fields of radiation monitoring, voice and data communication, component monitoring and instrumentation, and wireless cameras

  1. Applicable approach of the wireless technology for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Do Young, E-mail: kodoyoung@khnp.co.kr; Lee, Soo Ill

    2013-12-15

    Highlights: • To apply wireless technology for Korean NPPs, several stipulations are proposed. • WLAN is proposed as the most appropriate wireless technology for Korean NPPs. • WLAN can be applied to the specific fields except in the control system. • An attitude survey on wireless showed that 94.7% agree with the necessity of wireless. - Abstract: Recently, many nuclear power plants (NPPs) over the world use various types of wireless systems for the advantages. Unfortunately, wireless technologies are not currently installed in any Korean NPPs because it is difficult to solve the negative impact of unexpected outcomes or failures from the influence of the wireless technologies, which is electromagnetic interference and radio-frequency interference (EMI/RFI). Moreover, a lack of desire on the part of Korean nuclear industry to implement it leads to give up benefit from the wireless technologies. To install the wireless technologies with maximum benefit and minimum risk, a systematic approach, which quantify the negative impact and prevent the influence, is essential; therefore, this paper describes an applicable research result on the wireless technology for Korean NPPs based on regulatory guides and current wireless hardware and software technologies. Also, survey on the needs for the wireless technology for Korean nuclear power plants was conducted, because the level of awareness of workers in NPPs regarding wireless technologies is very important issue. In this paper, we propose an applicable system to enhance the applicability for the wireless technology for Korean NPPs. The result based on proposed applicable system shows that wireless local area network (WLAN) is the representative candidate for Korean NPPs, which can be applied to the specific fields of radiation monitoring, voice and data communication, component monitoring and instrumentation, and wireless cameras.

  2. A Study on Soft Computing Applications in I and C Systems of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kang, H. T.; Chung, H. Y.

    2006-01-01

    In the paper, the application of the soft computing based nuclear power plant(NPP) is discussed. Soft computing such as neural network(NN), fuzzy logic controller(FLC), and genetic algorithm(GA) and/or their hybrid will be a new frontier for the development of instrument and control(I and C) systems in NPP. The application includes several fields, for example, the diagnostics of system transient, optimal data selection in NN, and intelligent control etc. Two or more combining structure, hybrid system, is more efficient. The concept of FLC, NN, and GA is presented in Section 2. The applications of soft computing used in NPP are presented in Section 3

  3. Development of the methodology for application of revised source term to operating nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Kang, M.S.; Kang, P.; Kang, C.S.; Moon, J.H.

    2004-01-01

    Considering the current trend in applying the revised source term proposed by NUREG-1465 to the nuclear power plants in the U.S., it is expected that the revised source term will be applied to the Korean operating nuclear power plants in the near future, even though the exact time can not be estimated. To meet the future technical demands, it is necessary to prepare the technical system including the related regulatory requirements in advance. In this research, therefore, it is intended to develop the methodology to apply the revised source term to operating nuclear power plants in Korea. Several principles were established to develop the application methodologies. First, it is not necessary to modify the existing regulations about source term (i.e., any back-fitting to operating nuclear plants is not necessary). Second, if the pertinent margin of safety is guaranteed, the revised source term suggested by NUREG-1465 may be useful to full application. Finally, a part of revised source term could be selected to application based on the technical feasibility. As the results of this research, several methodologies to apply the revised source term to the Korean operating nuclear power plants have been developed, which include: 1) the selective (or limited) application to use only some of all the characteristics of the revised source term, such as release timing of fission products and chemical form of radio-iodine and 2) the full application to use all the characteristics of the revised source term. The developed methodologies are actually applied to Ulchin 9 and 4 units and their application feasibilities are reviewed. The results of this research are used as either a manual in establishing the plan and the procedure for applying the revised source term to the domestic nuclear plant from the utility's viewpoint; or a technical basis of revising the related regulations from the regulatory body's viewpoint. The application of revised source term to operating nuclear

  4. Survey of past base isolation applications in nuclear power plants and challenges to industry/regulatory acceptance

    International Nuclear Information System (INIS)

    Malushte, S.R.; Whittaker, A.S.

    2005-01-01

    Seismic base isolation provides many benefits that can facilitate the standardization of future nuclear power plant structures and equipment while reducing the initial/life-cycle cost and construction schedule. This paper presents a survey of past seismic base isolation applications and studies related to nuclear applications and provides a discussion of the challenges that need to be overcome to gain industry and regulatory acceptance for deployment in future US nuclear power plants. Issues related to design, codes/standards/regulations, procurement, and construction, have been identified. (authors)

  5. Results of a nuclear power plant Application of a new technique for human error analysis (ATHEANA)

    International Nuclear Information System (INIS)

    Forester, J.A.; Whitehead, D.W.; Kolaczkowski, A.M.; Thompson, C.M.

    1997-01-01

    A new method to analyze human errors has been demonstrated at a pressurized water reactor (PWR) nuclear power plant. This was the first application of the new method referred to as A Technique for Human Error Analysis (ATHEANA). The main goals of the demonstration were to test the ATHEANA process as described in the frame-of-reference manual and the implementation guideline, test a training package developed for the method, test the hypothesis that plant operators and trainers have significant insight into the error-forcing-contexts (EFCs) that can make unsafe actions (UAs) more likely, and to identify ways to improve the method and its documentation. A set of criteria to evaluate the open-quotes successclose quotes of the ATHEANA method as used in the demonstration was identified. A human reliability analysis (HRA) team was formed that consisted of an expert in probabilistic risk assessment (PRA) with some background in HRA (not ATHEANA) and four personnel from the nuclear power plant. Personnel from the plant included two individuals from their PRA staff and two individuals from their training staff. Both individuals from training are currently licensed operators and one of them was a senior reactor operator open-quotes on shiftclose quotes until a few months before the demonstration. The demonstration was conducted over a 5 month period and was observed by members of the Nuclear Regulatory Commission's ATHEANA development team, who also served as consultants to the HRA team when necessary. Example results of the demonstration to date, including identified human failure events (HFEs), UAs, and EFCs are discussed. Also addressed is how simulator exercises are used in the ATHEANA demonstration project

  6. Quality assurance program application during the decommissioning phase of the Shoreham Nuclear Plant

    International Nuclear Information System (INIS)

    Patch, R.L.

    1993-01-01

    The application of Quality Assurance (QA) requirements for operating nuclear power plants has evolved over the last 30 years. QA programs started as good management practices and evolved to a process that is implemented integral to very detailed Probabilistic Risk Assessments (PRAs). QA programs for controlling activities during decommissioning of nuclear power plants are still in their infancy. Regulatory guidance is currently being developed, and much of what exists is in the form of draft guidance documents. In determining where to apply QA controls during decommissioning, a series of questions must be asked: Is there an existing regulatory commitment? (Safety related or safety significant activity); Are there any postulated accidents which need to be prevented or mitigated; What are the unacceptable risks; Are there other key factors, such as human performance issues and Industrial Safety Programs, to be considered? Which QA controls are needed and to what extent they should be applied must be evaluated on a case by case basis. How much QA to apply is usually a risk evaluation in itself. Can you afford not to apply a specific control? Can you afford to apply costly and rigorous quality control programs? These questions had to be answered at the Shoreham Nuclear Power Station (SNPS) in order to develop and implement an acceptable and effective Quality Assurance program. Exploring the SNPS open-quotes lessons learnedclose quotes on how to apply a quality assurance program during decommissioning is what the following discussion is about

  7. Development of seismic design method for free standing rack and applicability to Japanese nuclear power plant

    International Nuclear Information System (INIS)

    Takaki, Yu; Taniguchi, Katsuhiko; Kishimoto, Junichi; Iwasaki, Akihisa; Nekomoto, Yoshitsugu; Kuga, Tohru; Kameyama, Masashi

    2017-01-01

    Free standing racks which are not anchored to the pool floor nor walls have never been adopted in Japan. Under an earthquake, behaviors of free standing racks are nonlinear and involve a complex combination of motions (sliding, rocking, and twisting) and impacts between a fuel assembly and the fuel cell walls and between a pit floor and rack pedestals. To predict a seismic response of free standing racks, the seismic analysis requires careful considerations of these complex phenomena (sliding, rocking, and twisting), fluid coupling effects and frictional effects. We carried out seismic experiments on the full-scale rack model in both water and dry conditions and obtained the fundamental data about behavior of free standing racks (sliding, and rocking motions). We have developed the nonlinear dynamic analysis method to predict seismic response of free standing racks utilizing the full-scale test result and verified the analysis evaluation method of free standing rack by comparison between analysis results and experimental data. Furthermore, we applied the seismic design method to the free standing rack in the Japanese nuclear plant (Mihama nuclear power station Unit 3), and verified that the free standing rack was applicable to Japanese nuclear plant. (author)

  8. NRC research on the application of advanced I and C technology to commercial nuclear power plants

    International Nuclear Information System (INIS)

    Gollei, K.R.; Hon, A.L.

    1983-01-01

    The operational safety and efficiency of commercial nuclear power plants (NPP's) could possibly be enhanced by utilizing advanced instrumentation and control technology developed by other industries. The NRC is interested in learning about new I and C technology that probably will or could be applied to new or existing plants. This would enable the NRC to be better prepared to evaluate the application without undue delays. It would also help identify any appropriate changes in NRC regulations or guidance necessary to facilitate the application of advanced IandC technology to NPP's. The NRC has initiated a project to work cooperatively with the advanced technology industry, power industry, EPRI, and technical organizations such as ISA toward this goal. This paper describes the objectives and plans of this cooperative effort. It summarizes the highlights of some of the advanced technology already being evaluated by NRC such as microprocessor applications, instruments to detect inadequate core cooling and other two-phase flow measurements, reactor noise surveillance and diagnostic techniques. This paper also suggests potential candidates for consideration such as utilization of advanced instruments for LOCA experiments. It also identifies some of the potential challenges facing the application of advanced technology to NPP's. It concludes that close cooperation between NRC and industry is essential for the success of such applications

  9. Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant

    International Nuclear Information System (INIS)

    Galyean, W.J.; Gertman, D.I.

    1992-04-01

    This report presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in the report provides a state-of-the-art method for identifying and evaluating plant-specific hardware design, human performance issues, and accident consequence factors to relevant to the prediction of the ISLOCA risk. This ISLOCA methodology was developed and then applied to a Babcock and Wilcox (B ampersand W) nuclear power plants. The results from this application are described in detail. For this particular B ampersand W reference plant, the assessment indicated that the probability of a severe ISLOCA is approximately 2.2E-06/reactor-year. This document Volume 3 provides appendices A--H of the report. Topics are: Historical experience related to ISLOCA events; component failure rates; reference B ampersand W plant system descriptions; reference B ampersand W plant ISLOCA event trees; Human reliability analysis for the B ampersand W ISLOCA probabilistic risk assessment; thermal hydraulic calculations; bounding core uncovery time calculations; and system rupture probability

  10. Application of aggregation techniques for model order reduction of nuclear plants for operator guidance systems

    International Nuclear Information System (INIS)

    Zwingelstein, G.C.

    1980-12-01

    After a short description of a disturbance analysis system for nuclear plant based on real time dynamic modelling and simulation, a scheme for generating aggregated reduced models of high order systems is presented. This method allows the choice of dominant dynamic modes and its efficiency is illustrated for the case of a 29th order nuclear plant model

  11. Application study of non-linear reasoning for nuclear plant operation

    International Nuclear Information System (INIS)

    Yoshikawa, Shinji; Yonekawa, Tsuyoshi; Suda, Kazunori; Hasegawa, Makoto

    1999-03-01

    Achievement of improved operation safety of complex nuclear power plants by decision-making functions based on information processing technologies requires real time concluding to be in-time for plant state evolutions, transparency for human operators to understand the derived conclusion, and robustness against local defects inevitably hidden in huge amount of the referred information. These requirements can not be met by the simple rule-based reasoning. The study introduced in this report put a focus on the robustness of the three requirements. This study derives the required feature of robust decision making, after thinking of possible contribution of fast emerging measurement technologies. Finally, two concrete algorithm based on mutual evaluation of relatively simple diagnostic modules are implemented on computer systems and evaluated in views of applicability. (author)

  12. Applications of a methodology for the analysis of learning trends in nuclear power plants

    International Nuclear Information System (INIS)

    Cho, Hang Youn; Choi, Sung Nam; Yun, Won Yong

    1995-01-01

    A methodology is applied to identify the learning trend related to the safety and availability of U.S. commercial nuclear power plants. The application is intended to aid in reducing likelihood of human errors. To assure that the methodology can be easily adapted to various types of classification schemes of operation data, a data bank classified by the Transient Analysis Classification and Evaluation(TRACE) scheme is selected for the methodology. The significance criteria for human-initiated events affecting the systems and for events caused by human deficiencies were used. Clustering analysis was used to identify the learning trend in multi-dimensional histograms. A computer code is developed based on the K-Means algorithm and applied to find the learning period in which error rates are monotonously decreasing with plant age

  13. Application of the V.R. technology to the 3D-CAD system for nuclear plant

    International Nuclear Information System (INIS)

    Katoh, Toshisada; Tanaka, Kazuo; Kasai, Yasusuke; Kimura, Katsumi; Nakakoshi, Tetsuhiro

    1993-01-01

    The technology of the V.R. (Virtual Reality) is expected to improve the interface between the human and the computer by reality and easiness. The application of the V.R. technology to the nuclear power plant will bring the wide-spread use of the computer in various fields such as plant planning, design, training, and operation. The combination of the 3D-CAD plant data and the V.R. technologies will be easy approach to realize these applications because the 3D-CAD data for nuclear plant is constructed in the design stage. The prototype system investigates the feasibility of V.R. technologies in the nuclear plant. The stereo-scopic device and the voice processing device has been integrated to 3D-CAD system by 1992. We confirmed that these devices have a good effect on the improvement of the interface between the man and the computer. (orig.)

  14. Experiences and plot application of maintenance rule for nuclear power plant in Korea

    International Nuclear Information System (INIS)

    Choi, Kwang Hee; Seo, Mi Ro; Kim, Myung Ki; Yoo, Sung Soo

    2007-01-01

    In order to enhance the effectiveness of maintenance, Korea lunched two pilot project to implement the Maintenance Rule(MR) program similar to that of USA. One for the pilot program is Ulchin units 3 and 4, Korean standardized nuclear power(KSNP) Plant, which was started in October 2003 and finished in September 2006. The other program is for Kori units 3 and 4, Westinghouse type plants, which was stared in April 2004 and completed in September 2006. MR processes consists of 'scope determination', 'safety significance determination', 'performance criteria development', 'performance monitoring' and 'disposition process between enforcement monitoring and routine monitoring'. At each process, we gave a expert panel to review output of each process and make a justification on the output. these expert panels meeting made much of technical discussions and decisions of major products on each process. In addition, Maintenance effectiveness and Target observation system(MENTOS) was developed to manage MR implementation, of which data is automatically imported from Enterprise Resource Program(ERP), and outputs are exported to ERP and the final results are shown in ERP screen. In this paper, major results and experiences gained from each application process at Ulchin 3,4 nuclear power plants were introduced

  15. Application of reliability centred maintenance to optimize operation and maintenance in nuclear power plants

    International Nuclear Information System (INIS)

    2007-05-01

    In order to increase Member States capabilities in utilizing good engineering and management practices the Agency has developed a series of Technical Documents (TECDOCs) to describe best practices and members experience in the application of them. This TECDOC describes the concept of Reliability Centred Maintenance (RCM) which is the term used to describe a systematic approach to the evaluation, design and development of cost effective maintenance programmes for plant and equipment. The concept has been in existence for over 25 years originating in the civil aviation sector. This TECDOC supplements previous IAEA publications on the subject and seeks to reflect members experience in the application of the principles involved. The process focuses on the functionality of the plant and equipment and the critical failure mechanisms that could result in the loss of functionality. When employed effectively the process can result in the elimination of unnecessary maintenance activities and the identification and introduction of measures to address deficiencies in the maintenance programme. Overall the process can result in higher levels of reliability for the plant and equipment at reduced cost and demands on finite maintenance resources. The application of the process requires interaction between the operators and the maintenance practitioners which is often lacking in traditional maintenance programmes. The imposition of this discipline produces the added benefit of improved information flows between the key players in plant and equipment management with the result that maintenance activities and operational practices are better informed. This publication was produced within IAEA programme on nuclear power plants operating performance and life cycle management

  16. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  17. GIS Application in Atucha I Nuclear Power Plant Exercise Argentina, 2007

    International Nuclear Information System (INIS)

    Sadaniowski, I.V.; Telleria, D.M.; Jordan, O.D.; Boutet, L.I.; Kunst, J.J.; Bruno, H.A.; Hernandez, D.G.; Rodriguez, M.; Cateriano, M.A.; Rey, H.L.

    2011-01-01

    Geographic Information Systems (GIS) are tools applied to assist in the assessment and solution of many geographical related issues. Recently, their applications have been extended to the areas of disasters and environmental emergencies. GIS not only could be used as a diagnostic tool. Combined with adequate information and other tools capable to predict the transfer of pollutants in the environment and the associated impacts to the public, GIS could be used to support emergency planning and response. The Nuclear Regulatory Authority (NRA) of Argentina has incorporated in 2003 the GIS technology like an innovative resource for its preparation and response activities in emergencies. For this, the NRA acquired the necessary technology (hardware and software) and the technical specialist who were joined to expert's team in the nuclear and radiological emergencies field. The GIS stays operative as support tool in the Emergencies Control Center of NRA. In this paper, the use of GIS as a tool for analysis and advice is presented. The GIS is being used for preparation and development of nuclear emergencies trials and exercises, carried out on-site and off-site at the Nuclear Power Plant Atucha I Buenos Aires, Argentina, in cooperation with civil defense, national and state security and army forces and intensive public involvement. The databases were conformed with information from different sources, including the result of interviews to different actors, as well as other local and national government agencies and forces. Also, educational institutions, local medical centers, etc., were consulted. The information was enriched with outings to field in the surroundings of nuclear power plant. The scope and the detail of the information for this exercise covers 30 kilometers surroundings the nuclear power plant, with a range of significantly different geographical and population conditions. When loading the information in the GIS, a classification scheme is applied and

  18. GIS application in Atucha I nuclear power plant exercise Argentina, 2007

    International Nuclear Information System (INIS)

    Sadaniowski, Ivana; Jordan, Osvaldo; Boutet, Luis; Kunst, Juan; Bruno, Hector; Hernandez, Daniel; Rodriguez, Monica; Cateriano, Miguel; Rey, Hugo; Telleria, Diego

    2008-01-01

    Full text: Geographic Information Systems (GIS) are tools applied to assist in the assessment and solution of many geographical related issues. Recently, their applications have been extended to the areas of disasters and environmental emergencies. GIS not only could be used as a diagnostic tool. Combined with adequate information and other tools capable to predict the transfer of pollutants in the environment and the associated impacts to the public, GIS could be used to support emergency planning and response. The Nuclear Regulatory Authority (NRA) of Argentina has incorporated in 2003 the GIS technology like an innovative resource for its preparation and response activities in emergencies. For this, the NRA acquired the necessary technology (hardware and software) and the technical specialist who were joined to expert's team in the nuclear and radiological emergencies field. The GIS stays operative as support tool in the Emergencies Control Center of NRA. In this paper, the use of GIS as a tool for analysis and advice is presented. The GIS is being used for preparation and development of nuclear emergencies trials and exercises, carried out on-site and off-site at the Nuclear Power Plant Atucha I Buenos Aires, Argentina, in cooperation with civil defense, national and state security and army forces and intensive public involvement. The databases were conformed with information from different sources, including the result of interviews to different actors, as well as other local and national government agencies and forces. Also, educational institutions, local medical centers, etc., were consulted. The information was enriched with outings to field in the surroundings of nuclear power plant. The scope and the detail of the information for this exercise covers 30 kilometers surroundings the nuclear power plant, with a range of significantly different geographical and population conditions. When loading the information in the GIS, a classification scheme is applied

  19. Bayes' theorem and its application to nuclear power plant safety

    International Nuclear Information System (INIS)

    Matsuoka, Takeshi

    2013-01-01

    Bayes' theorem has been paid in much attention for its application to Probabilistic Safety Assessment (PSA). In this lecture, the basis for understanding Bayes' theorem is first explained and how to interpret the Bayes' equation with respect to the pair of conjugate distributions between prior distribution and likelihood. Then for the application to PSA, component failure data are evaluated by Bayes' theorem by using the examples of demand probability of the start of diesel generator and failure of pressure sensor. Frequencies of nuclear power plant accidents are also evaluated by Bayes' theorem for the example case of frequency of 'fires in reactor compartment' and 'core melt' frequency with the experience of Fukushima dai-ichi accidents. Lastly, several contrasting arguments are introduced briefly between favorable and critical peoples regarding the Bayes' methods. (author)

  20. A Fuzzy Multi-Criteria SWOT Analysis: An Application to Nuclear Power Plant Site Selection

    Directory of Open Access Journals (Sweden)

    Mehmet Ekmekcioglu

    2011-08-01

    Full Text Available SWOT (Strengths, Weaknesses, Opportunities and Threats analysis is a commonly used and an important technique for analyzing internal and external environments in order to provide a systematic approach and support for a decision making. SWOT is criticized mostly for considering only qualitative examination of environmental factors, no priority for various factors and strategies, and no vagueness of the factors under fuzziness. In this paper, fuzzy TOPSIS (Technique for Order Preference by Similarity to Ideal Solution integrated with fuzzy AHP (Analytical Hierarchy Process is used to develop fuzzy multi-criteria SWOT analysis in order to overcome these shortcomings. Nuclear power plant site selection, which is a strategic and important issue for Turkeyrs energy policy making, is considered as an application case study that demonstrated the applicability of the developed fuzzy SWOT model.

  1. Application in nuclear engineering: methodology of innovative nuclear reactors: approaches to the safety of future nuclear power plants

    International Nuclear Information System (INIS)

    Alramady, A.M.K

    2008-01-01

    This thesis describes RELAP5 and MATLAB/SIMULINK computer codes for thermal hydraulic analysis of a typical pressurized water reactor (PWR). The two codes are used to calculate the thermal-hydraulic characteristics of the reactor core and the primary loop under steady-state and hypothetical accidents conditions.New designs of nuclear power plants are directed to increase safety by many methods like reducing the dependence on active parts (such as safety pumps, fans, and diesel generators ) and replacing them with passive features such as gravity draining of cooling water from tanks, and natural circulation of water and air. In this work, high and medium pressure injection pumps are replaced by passive injection components. Different break sizes in cold leg pipe are simulated to analyze to what degree the plant is safe (without any operator action) by using only these passive components. The passive design means operators would not need to take immediate action after an accident, with the reactor ,instead, safely shutting down on its own. Different accident scenarios were simulated in this thesis as loss of coolant accidents and station blackout accidents, and complete passive safety systems used to mitigate theses accidents.

  2. Application of flow-controllable accumulator and performance analysis in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jung, Byung-Ryul; Lee, Un-Chul

    1997-01-01

    The Korean Yonggwang Nuclear Power Plants 3 ampersand 4(YGN 3 ampersand 4) are the two-loop pressurized water reactor (PWR) nuclear steam supply systems, rated at 2,815 MW(thermal). They incorporate the safety injection system (SIS) consisting of the two high pressure (HPSI) pumps, two low pressure safety injection (LPSI) pumps, and four accumulators. The SIS is two headered arrangements, each to four cold legs injection (CLI) type which provides cooling to the core in the highly unlikely event of a loss-of-coolant accident (LOCA). In the current SIS, the LPSI pumps automatically start during a LOCA, and also provide the residual heat removal capability during the shutdown cooling. This paper presents the feasibility of the removal of the LPSI from the existing SIS with minor system changes, including the increase up to four in the HPSI pumps, direct vessel injection(DVI), and the flow-controllable accumulators. A double-ended rupture of one of the four cold legs in the YGN 3 ampersand 4 was simulated using RELAP5/MOD3.1 to determine the feasibility of the application of this new SIS design to the current nuclear power plants. As a result, the calculated reflooding peak cladding surface temperature(PCT) was comparable to that of original base calculation, and the downcomer and the core collapsed liquid level during reflooding were also comparable to those in the current safety system design. This large break, cold-leg LOCA analysis addresses the reflooding capability without credit for a LPSI pump system and the applicability of the new flow-controllable accumulator. Also this analysis confirms that the combination of new flow-controllable accumulators, DVI and the increased HPSI pumps maintain the peak cladding temperature below the prescribed limits. 14 refs., 4 figs., 3 tabs

  3. Nuclear power plants

    International Nuclear Information System (INIS)

    Margulova, T.Ch.

    1976-01-01

    The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

  4. Application of integrated computer-aided engineering for design, construction and operation of nuclear power plant: practice and prospects

    International Nuclear Information System (INIS)

    Min, K.S.; Lee, B.H.

    1988-01-01

    Computer-aided-engineering (CAE) is an essential tool for modern nuclear power plant engineering. It greatly varies in definition, application, and technology from project to project and company to company. Despite the fast growing technologies and applications of CAE, its complexity and variety have thrown another puzzle to management of a nuclear project. Without due consideration of an integrated CAE system in early planning stage, the overall efficiency of a nuclear project would slow down due to the inefficiency in data flow. In this application are discussed under the Korea Power engineering Company philosophy in CAE approach

  5. Design engineer perceptions and attitudes regarding human factors application to nuclear power plant design

    International Nuclear Information System (INIS)

    Ma, R.; Jones, J. M.

    2006-01-01

    With the renewed interest in nuclear power and the possibility of constructing new reactors within the next decade in the U.S., there are several challenges for the regulators, designers, and vendors. One challenge is to ensure that Human Factors Engineering (HFE) is involved, and correctly applied in the life-cycle design of the Nuclear Power Plant (NPP). As an important part of the effort, people would ask: 'is the system-design engineer effectively incorporating HFE in the NPPs design?' The present study examines the sagacity of Instrumentation and Control design engineers on issues relating to awareness, attitude, and application of HFE in NPP design. A questionnaire was developed and distributed, focusing on the perceptions and attitudes of the design engineers. The responses revealed that, while the participants had a relatively high positive attitude about HFE, their awareness and application of HFE were moderate. The results also showed that senior engineers applied HFE more frequently in their design work than young engineers. This study provides some preliminary results and implications for improved HFE education and application in NPP design. (authors)

  6. Integrated Nuclear Recycle Plant

    International Nuclear Information System (INIS)

    Patodi, Anuj; Parashar, Abhishek; Samadhiya, Akshay K.; Ray, Saheli; Dey, Mitun; Singh, K.K.

    2017-01-01

    Nuclear Recycle Board (NRB), Tarapur proposes to set up an 'Integrated Nuclear Recycle Plant' at Tarapur. This will be located in the premises of BARC facilities. The project location is at coastal town of Tarapur, 130 Km north of Mumbai. Project area cover of INRP is around 80 hectares. The plant will be designed to process spent fuel received from Pressurized Heavy Water Reactors (PHWRs). This is the first large scale integrated plant of the country. INRP will process spent fuel obtained from indigenous nuclear power plants and perform left over nuclear waste disposal

  7. Improvement of nuclear power plants within the perspective of applications of lean manufacturing practices

    Science.gov (United States)

    Malek, A. K.; Muhammad, H. I.; Rosmaini, A.; Alaa, A. S.; Falah, A. M.

    2017-09-01

    Development and improvement process are essential to the companies and factories of various kinds and this necessity is related aspects of cost, time and risk that can be avoided, these aspects are available at the nuclear power stations essential demands cannot be ignored. The lean management technique is one of the recent trends in the management system. Where the lean management is stated as the system increases the customer value and reduces the wastage process in an industry or in a power plants. Therefore, there is an urgent necessity to ensure the development and improvement in nuclear power plants in the pre-established in process of being established and stage of the management and production. All of these stages according to the study are closely related to the necessity operationalize and apply lean manufacturing practices that these applications are ineffective and clear contribution to reduce costs and control of production processes and the process of reducing future risks that could be exposed to the station.

  8. Response Time Test for The Application of the Data Communication Network to Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shin, Y.C.; Lee, J.Y.; Park, H.Y.; Seong, S.H.; Chung, H.Y.

    2002-01-01

    This paper discusses the response time test for the application of the Data Communication Network (DCN) to Nuclear Power Plant (NPP). Conventional Instrumentation and Control (I and C) Systems using the analog technology in NPP have raised many problems regarding the lack of spare parts, maintenance burden, inaccuracy, etc.. In order to solve the problems, the Korean Next Generation Reactor (KNGR) I and C system has adopted the digital technology and new design features of using the data communication networks. It is essential to prove the response time requirements that arise from the introduction of digital I and C technology and data communication networks to nuclear power plant design. For the response time test, a high reliable data communication network structure has been developed to meet the requirements of redundancy, diversity, and segmentation. This paper presents the results of network load analysis and response time test for the KNGR DCN prototype. The test has been focused on the response time from the field components to the gateway because the response times from the gateway to the specific systems are similar to those of the existing design. It is verified that the response time requirements are met through the prototype test for KNGR I and C systems. (authors)

  9. Application of expert system to nuclear power plant operation and guidance system

    International Nuclear Information System (INIS)

    Goto, M.; Takada, Y.

    1990-01-01

    For a nuclear power plant, it is important that an expert system supplies useful information to the operator to meet the increasing demand for high-level plant operation. It is difficult to build a user-friendly expert system that supplies useful information in real time using existing general-purpose expert system shells. Therefore a domain-specific expert system shell with a useful knowledge representation for problem-solving in nuclear power plant operation was selected. The Plant Table (P/T) representation format was developed for description of a production system for nuclear power plant operation knowledge. The P/T consists of plant condition representation designed to process multiple inputs and single output. A large number of operation inputs for several plant conditions are divided into 'timing conditions', 'preconditions' and 'completion conditions' to facilitate knowledge-base build-up. An expert system for a Nuclear Power Plant Operation and Guidance System utilizing the P/T was developed to assist automatic plant operation and surveillance test operation. In these systems, automatic plant operation signals to the plant equipment and operation guidance messages to the operators are both output based on the processing and assessment of plant operation conditions by the P/T. A surveillance test procedure guide for major safety-related systems, such as those for emergency core cooling systems, is displayed on a CRT (Cathode Ray Tube) and test results are printed out. The expert system for a Nuclear Power Plant Operation and Guidance System has already been successfully applied to Japanese BWR plants

  10. Trial application of guidelines for nuclear plant response to an earthquake

    International Nuclear Information System (INIS)

    Schmidt, W.; Oliver, R.; O'Connor, W.

    1993-09-01

    Guidelines have been developed to assist nuclear plant personnel in the preparation of earthquake response procedures for nuclear power plants. These guidelines are published in EPRI report NP-6695, ''Guidelines for Nuclear Plant Response to an Earthquake,'' dated December 1989. This report includes two sets of nuclear plant procedures which were prepared to implement the guidelines of EPRI report NP-6695. The first set were developed by the Toledo Edison Company Davis-Besse plant. Davis-Besse is a pressurized water reactor (PWR) and contains relatively standard seismic monitoring instrumentation typical of many domestic nuclear plants. The second set of procedures were prepared by Yankee Atomic Electric Company for the Vermont Yankee facility. This plant is a boiling water reactor (BWR) with state-of-the-art seismic monitoring and PC-based data processing equipment, software developed specifically to implement the OBE Exceedance Criterion presented in EPRI report NP-5930, ''A Criterion for Determining Exceedance of the operating Basis Earthquake.'' The two sets of procedures are intended to demonstrate how two different nuclear utilities have interpreted and applied the EPRI guidance given in report NP-6695

  11. Development of resilience evaluation method for nuclear power plants. Part 3. Study of evaluation method and applicability of resilience index

    International Nuclear Information System (INIS)

    Suzuki, Masaaki; Demachi, Kazuyuki; Miyano, Hiroshi

    2017-01-01

    We have developed a new index, called the resilience index, that evaluates the dynamic stability of the system safety of a nuclear power plant during a severe accident by considering the ability to recover system safety functions that have become lost in the situation. In this paper, a detailed evaluation procedure for the resilience index is described. The system safety of a pressurized water reactor plant during a severe accident is then assessed according to the resilience index in order to discuss the applicability of the index. We find that the resilience index successfully represents management capability and, therefore, the resilience capability of a nuclear power plant. (author)

  12. Development of resilience evaluation method for nuclear power plants. Part 3. Study on evaluation method and applicability of resilience index

    International Nuclear Information System (INIS)

    Suzuki, Masaaki; Demachi, Kazuyuki; Murakami, Kenta

    2016-01-01

    We have developed a new index, called the resilience index, that evaluates the dynamic stability of the system safety of a nuclear power plant during a severe accident by considering the ability to recover system safety functions that have become lost in the situation. In this paper, a detailed evaluation procedure for the resilience index is described. The system safety of a PWR plant during a severe accident is then assessed according to the resilience index in order to discuss the applicability of the index. We find that the resilience index successfully represents management capability and, therefore, the resilience capability of a nuclear power plant. (author)

  13. Public regulation of nuclear plants

    International Nuclear Information System (INIS)

    Burtheret, M.; Cormis, de

    1980-01-01

    The construction and operation of nuclear plants are subject to a complex system of governmental administration. The authors list the various governmental authorisations and rules applicable to these plants. In the first part, they describe the national regulations which relate specifically to nuclear plants, and emphasize the provisions which are intended to ensure the safety of the installations and the protection of the public against ionizing radiation. However, while the safety of nuclear plants is a major concern of the authorities, other interests are also protected. This is accomplished by various laws or regulations which apply to nuclear plants as well as other industrial installations. The duties which these texts, and the administrative practice based thereon, impose on Electricite de France are covered in the second part [fr

  14. Application of fire models for risk analysis in french nuclear power plants

    International Nuclear Information System (INIS)

    Brauns, P.

    1989-04-01

    Numerical simulations of compartment fires have been carried out in the French 900 MW and 1 300 MW nuclear power plants, to obtain quantitative data about this particular kind of risk: characteristic spreading times from one redundant electrical train to the other one, behaviour of important electrical components... The main stages of both studies were the following: selection of rooms, the location or function of which are essential for the plant safety in case of fire, on-site inspections to collect information about these rooms (amount of fuel, openings...), definition of fire scenarios, improvement of the fire model VESTA-PLUS, and, finally calculations using this computer code. The simulations have shown two major trends: i) the spreading times, without taking into account any external intervention, are always greater than half an hour, and ii) the specific design of the 1 300 MW power plants generally prevents one of the redundant train from being damaged due to a fire occurring in a room containing the other one. Examples of typical results obtained are given, showing the capability of application of the improved fire model to complex problems

  15. Financial qualifications review of applicants for nuclear power plant construction permits

    International Nuclear Information System (INIS)

    Hendrickson, P.L.; Mullen, M.F.; Carr, D.B.

    1988-09-01

    The NRC and its predecessor the AEC have had a regulatory requirement since 1956 that utilities seeking a construction permit for a nuclear power plant be financially qualified to construct and operate the plant. Several amendments to the requirements were made over the years including an attempt in 1982 to drop financial qualification review for electric utilities. This attempt was subsequently found invalid by a federal court. Nevertheless, financial qualification reviews consume significant amounts of NRC staff time and time at Atomic Safety and Licensing Board hearings. The analysis reported in this study was conducted to determine whether there is any empirical evidence of a relationship between a utility's financial health at the time of its construction permits application and the subsequent safety performance of the operating plant. The principal financial measures used to test for this relationship were bond rating, interest coverage ratio, debt/asset ratio, debt/equity ratio, and rate of return on equity. The principal safety measure was the long-term average of the scores assigned the utility in four key areas by the NRC under the Systematic Assessment of Licensee Performance program. The results of the analysis showed no evidence of a relationship between financial health at the time of the construction permit and subsequent safety performance. 7 refs., 16 figs., 4 tabs

  16. Application of control computer system TESLA RPP-16 in the Bohunice nuclear power plant

    International Nuclear Information System (INIS)

    Spetko, V.

    1976-01-01

    The reasons are given for the installation of a computer at the A-1 nuclear power plant in Czechoslovakia with regard to applied research. The configuration, placement, and software of the computer system is described. The programmes are written in the SAM and FORTRAN-IV languages. The knowledge acquired in the course of tests and the prospect of the future installation of computer control equipment in the A-1 nuclear power plant are described. (J.P.)

  17. Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Perkins, W.C.; Durant, W.S.; Dexter, A.H.

    1980-12-01

    The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents

  18. Application of contemporary integrated manufacture systems to nuclear power plants management

    International Nuclear Information System (INIS)

    Zhou Gang; Wang Lushuai; Tang Yaoyang

    2005-01-01

    In order to improve the safety, economy and reliability of the operation of a nuclear power plant (NPP), a novel integrated management method is proposed based on the 'integration' concept of the computer and contemporary integrated manufacture systems (CIMS). The design of integrated management system for NPP is studied. In the design of this system, information integration method based on the database and product data management (PDM) technology is adopted. In order to design and integrated management system satisfying the needs of NPP management, all activities of NPP are divided into different categories according to its characteristics. There are subsystems under the general management system to conduct the management work of different categories. All subsystems are interrelated in the environment of CIMS, but relatively independent. The application of CIMS to NPP provides a new way for scientific management of NPP, and makes the best of human, material and information resources. (authors)

  19. Application of ion exchange in liquid radioactive waste management of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Pal, Puskar; Chopra, S K; Sharma, P D [Nuclear Power Corporation, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    The operation of nuclear power plants would necessarily result in generation of gaseous, liquid and solid radioactive wastes. The wastes are treated/conditioned to ensure that the permissible discharge limits laid down by Atomic Energy Regulatory Board of India are complied with. The wastes are segregated on activity levels, types of radioisotopes present and chemical nature of liquid streams. The basic philosophy of various treatment techniques is to concentrate and contain as much activity as possible. It is of utmost importance that the wastes are effectively treated by proven methods/processes. The radiochemical nature of waste generated is one of the parameters to select a treatment/conditioning method. The paper presents an outline of various processes adopted for treatment of liquid waste and ion exchange processes, their application in liquid waste management in detail. Projected quantities of liquid wastes for the current designs are included. (author). 2 tabs.

  20. Standards for digital computers used in non-safety nuclear power plant applications: objectives and limitations

    International Nuclear Information System (INIS)

    Rorer, D.C.; Long, A.B.

    1977-01-01

    There are currently a number of efforts to develop standards which would apply to digital computers used in nuclear power plants for functions other than those directly involving plant protection (for example, ANS: 4.3.3 Subworking Group in the U.S., IEC 45A/WGA1 Subcommittee in Europe). The impetus for this activity is discussed and generally attributed to the realization that nonsafety systems computers may affect the assumptions used as the design bases for safety systems, the sizable economic loss which can result from the failure of a critical computer application, and the lingering concern about the misapplication of a still-new technology. At the same time, it is pointed out that these standards may create additional obstacles for the use of this new technology which are not present in the application of more conventional instrumentation and control equipment. Much of the U.S. effort has been directed toward the problem of validation of computer systems in which the potential exists for unplanned interactions between various functions in a multiprogram environment, using common hardware in a time-sharing mode. The goal is to develop procedures for the specification, development implementation, and documentation of testable, modular systems which, in the absence of proven quantitative techniques for assessing software reliability, are felt to provide reasonable assurance that the computer system will function as planned

  1. Investigation of specific applications of laser cutting for dismantling of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Tarroni, G.; De Zaiacomo, T.; Melandri, C.; Formignani, M.; Barilli, L.; Di Fino, M.; Picini, P.; Galuppi, G.; Rocca, C.; Manassero, G.; Migliorati, B.

    1992-01-01

    The aim of this work, performed on an experimental basis in a frame of strict collaboration between industry (FIAT-CIEI and FIAT-CRF in Turin) and public research laboratories (ENEA-PAS-FIBI in Bologna, ENEA-PAS-ISP and ENEA-TIB-TECNLAS in Rome) and supported by a CEC contract, was to bring out the items for better evaluation of the laser beam application possibilities in dismantling nuclear power plants. The main topics of the research have been: study and definition of the relevant basic parameters ruling the aerosol generation rate and behaviour in terms of physical and chemical characteristics. This work has been performed in a facility specifically designed for aerosol measurements and equipped with a 2kW laser source; study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; study of long distance transmission of the laser beam power performed with a 5kW laser source with an evaluation of the power loss and beam characteristic modifications; study of laser beam technique application for dismantling the Garigliano power plant steam drum in order to better demonstrate the feasibility of the use of this technique. The research resulted in the conclusion that the laser beam is actually appropriate for long distance dismantling of metal components.

  2. 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.)

  3. A PLC generic requirements and specification for safety-related applications in nuclear power plants

    International Nuclear Information System (INIS)

    Han, Jea Bok; Lee, C. K.; Lee, D. Y.

    2001-12-01

    This report presents the requirements and specification to be applied to the generic qualification of programmable Logic Controller(PLC), which is being developed as part of the KNICS project, 'Development of the Digital Reactor Safety Systems' of which purpose is the application to safety-related instrumentation and control systems in nuclear power plants. This report defines the essential and critical characteristics that shall be included as part of a PLC design for safety-related application. The characteristics include performance, reliability, accuracy, the overall response time from an input to the PLC exceeding it trip condition to the resulting outputs, and the specification of processors and memories in digital controller. It also specifies the quality assurance process for software development, dealing with executive software, firmware, application software tools for developing the application software, and human machine interface(HMI). In addition, this report reviews the published standards and guidelines that are required for the PLC development and the quality assurance processes such as environment requirements, seismic withstand requirements, EMI/RFI withstand requirements, and isolation test

  4. Application of hydraulic network analysis to motor operated butterfly valves in nuclear power plants

    International Nuclear Information System (INIS)

    Eldiwany, B.H.; Kalsi, M.S.

    1992-01-01

    This paper presents the application of hydraulic network analysis to evaluate the performance of butterfly valves in nuclear power plant applications. Required actuation torque for butterfly valves in high-flow applications is often dictated by peak dynamic torque. The peak dynamic torque, which occurs at some intermediate disc position, requires accurate evaluation of valve flow rate and pressure drop throughout the valve stroke. Valve flow rate and pressure drop are significantly affected by the valve flow characteristics and the hydraulic system characteristics, such as pumping capability, piping resistances, single and parallel flow paths, system hydrostatic pressure, and the location of the motor-operated valve (MOV) within the system. A hydraulic network analysis methodology that addresses the effect of these parameters on the MOV performance is presented. The methodology is based on well-established engineering principles. The application of this methodology requires detailed characteristics of both the MOV and the hydraulic system in which it is installed. The valve characteristics for this analysis can be obtained by flow testing or from the valve manufacturer. Even though many valve users, valve manufacturers, and engineering standards have recognized the importance of performing these analyses, none has provided a detailed procedure for doing so

  5. Nuclear Power Plants. Revised.

    Science.gov (United States)

    Lyerly, Ray L.; Mitchell, Walter, III

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

  6. Standard format and content for the physical protection section of a license application (for facilities other than nuclear power plants)

    International Nuclear Information System (INIS)

    1976-06-01

    The document presented has been prepared as an aid to uniformity and completeness in the preparation and review of the physical protection section of license applications. It is applicable to fuel reprocessing plants, fuel manufacturing plants, SNM tranportation, or other special nuclear material operations involving the possession and use of uranium 235 (contained in uranium enriched to 20 percent or more in the U-235 isotope), uranium 233, or plutonium alone or in any combination in a quantity of 5000 grams or more computed by the formula: grams = (grams contained U-235) + 2.5 (grams U-233 + grams plutonium). The document is not intended to be used for nuclear power plants. The information specified is the minimum needed for a license application. Additional information may be required for completion of the staff review of a particular application

  7. Unplanned unavailability of the French nuclear plants. Evolution. Outstanding facts applications

    International Nuclear Information System (INIS)

    Coppe, P.

    2001-01-01

    The presentation gives a description of the unplanned unavailability of the whole French nuclear units on the aspect performance. The French fleet comprises 58 nuclear units including 34 from the series 900 MW, 20 from the stage 1300 MW and 4 units from the new series N4 of 1450 MW recently commissioned. Because of this width, even if the unavailability of the park remains on a low level on average, the experience feedback on this parameter gives very a rich lesson. The general evolution of unavailability over the last years is the subject of the first part of the talk. Several modes of analysis are examined: by year on the whole of the units, for the various series, by order of age of the various units. The different modes of gathering are examined and others are evoked, in order to reveal those which allow an optimal use of the experience feedback. The outstanding facts are then presented: the principal causes of unavailability are raised and examined. Certain equipment stand out particularly: the reasons of these singularities are exposed as well as the lesson and the modifications brought, the committed actions. Finally the applications resulting from the studies of the unplanned unavailability of the nuclear units are developed. Of course they relate in the forefront to the field of maintenance with the use of these studies within the framework of optimized and adapted programs of maintenance. The contributions are examined. The aging evolution of the plants is also analyzed starting from these studies. The stress is put however on a less obvious application: this one of the future units in design. (author)

  8. Building and application of the performance diagnosis system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.; Kanbara, K.; Sugawara, Y.

    2010-01-01

    To achieve a low-carbon society, we promote utilization of nuclear energy, which plays a zero-emission power generation. Therefore the nuclear power plants have been imposed a stable supply of electricity. The condition based maintenance (CBM) is effective in order to maintain a stable operation of the nuclear power plants. We built the performance diagnosis system based on the heat and mass balance calculation as one of supporting tools for the CBM. Moreover we note that the performance diagnosis system is built for steam turbine cycle operating with saturated steam conditions. (author)

  9. Simplified application of probabilistic safety analysis in nuclear power plants by means of artificial neural networks

    International Nuclear Information System (INIS)

    Oehmgen, T.; Knorr, J.

    2004-01-01

    Probabilistic safety analyses (PSA) are conducted to assess the balanced nature of plant design in terms of technical safety and the administrative management of plant operation in nuclear power plants. In the evaluation shown in this article of the operating experience accumulated in two nuclear power plants, all failures are traced back consistently to the plant media and component levels, respectively, for the calculation of reliability coefficients. Moreover, the use of neural networks for probabilistic calculations is examined. The results are verified on the basis of test examples. Calculations with neural networks are very easy to carry out in a kind of 'black box'. There is a possibility, for instance, to use the system in plant maintenance. (orig.) [de

  10. Application of digital solutions to help the safe and efficient operation of nuclear power plants

    International Nuclear Information System (INIS)

    Ortega P, F.; Fernandez F, S.

    2017-09-01

    In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

  11. Application of the neutron noise analysis technique in nuclear power plants

    International Nuclear Information System (INIS)

    Lescano, Victor H.; Wentzeis, Luis M.

    1999-01-01

    Using the neutron noise analysis in nuclear power plants, and without producing any perturbation in the normal operation of the plant, information of the vibration state of the reactor internals and the behavior of the operating conditions of the reactor primary circuit can be obtained. In Argentina, the neutron noise analysis technique is applied in customary way in the nuclear power plants Atucha I and Embalse. A database was constructed and vibration frequencies corresponding to different reactor internals were characterized. Reactor internals with particular mechanical vibrations have been detected and localized. In the framing of a cooperation project between Argentina and Germany, we participated in the measurements, analysis and modelisation, using the neutron noise technique, in the Obrigheim and Gundremmingen nuclear power plants. In the nuclear power plant Obrigheim (PWR, 350 M We), correlations between the signals measured from self-power neutron detectors and accelerometers located inside the reactor core, were made. In the nuclear power plant Gundremmingen (BWR, 1200 M We) we participated in the study of a particular mechanical vibration detected in one of the instrumentation tube. (author)

  12. Applicability of base-isolation R and D in non-reactor facilities to a nuclear reactor plant

    International Nuclear Information System (INIS)

    Seidensticker, R.W.

    1989-01-01

    Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. This paper reviews the research and development (R and D) programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R and D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R and D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant

  13. Activities of passive cooling applications and simulation of innovative nuclear power plant design

    International Nuclear Information System (INIS)

    Aglar, F.; Tanrykut, A.

    2002-01-01

    This paper gives a general insight on activities of the Turkish Atomic Energy Authority (TAEA) concerning passive cooling applications and simulation of innovative nuclear power plant design. The condensation mode of heat transfer plays an important role for the passive heat removal application in advanced water-cooled reactor systems. But it is well understood that the presence of noncondesable (NC) gases can greatly inhibit the condensation process due to the build up of NC gas concentration at the liquid/gas interface. The isolation condenser of passive containment cooling system of the simplified boiling water reactors is a typical application area of in-tube condensation in the presence of NC. The test matrix of the experimental investigation undertaken at the METU-CTF test facility (Middle East Technical University, Ankara) covers the range of parameters; Pn (system pressure) : 2-6 bar, Rev (vapor Reynolds number): 45,000-94,000, and Xi (air mass fraction): 0-52%. This experimental study is supplemented by a theoretical investigation concerning the effect of mixture flow rate on film turbulence and air mass diffusion concepts. Recently, TAEA participated to an international standard problem (OECD ISP-42) which covers a set of simulation of PANDA test facility (Paul Scherrer Institut-Switzerland) for six different phases including different natural circulation modes. The concept of condensation in the presence of air plays an important role for performance of heat exchangers, designed for passive containment cooling, which in turn affect the natural circulation behaviour in PANDA systems. (author)

  14. Application of reverse osmosis to the treatment of liquid effluents produced by nuclear power plants

    International Nuclear Information System (INIS)

    Huet, Y.; Poulat, B.; Menjeaud, C.

    1989-01-01

    Radioactive liquid effluents generated during the operation of PWR nuclear power units are currently treated by two independent systems. The effluents from the reactor coolant system are recycled, unlike the others, which, after treatment, are released into the river or ocean that provides cooling water for the unit. The objective of the treatment of nonrecycled effluents is to separate from them as much of the radioactive particles that they contain as possible, so as to release into the environment a maximum volume of nonradioactive waste, and to be left with only a minimum volume of concentrated waste, containing most of the initial radioactivity, which must be loaded into casks for storage. Membrane-based filtration techniques, because they have excellent separation performances, can logically be used for this decontamination of the liquid effluents. Having developed its own reverse osmosis membrane, a possible application in a nuclear power plant, i.e., integration of a reverse osmosis unit into a radioactive liquid effluent treatment system is presented. (author)

  15. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2003-01-01

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

  16. Application of Solar Chimney Concept to Solve Potential Safety Issues of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Khasawneh, Khalid; PARK, Youn Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    In this paper two main events and their causes have been investigated and a potential alternative supporting system will be provided. The first event to be addressed is the Station Blackout (SBO) caused by the inherent unreliability of the Emergency Diesel Generators (EDGs) and Alternative AC (AAC) power sources. Different parameters affect The EDG unreliability; for instance, mechanical, operational, maintenance and surveillance. Those parameters will be analyzed and linked to plant safety and Core Damage Frequency (CDF). Also the AACs, the SBO diesel generators, will be studied and their operational requirements similarity with the EDGs will be discussed. The second event to be addressed is the Loss of Ultimate Heat Sink (LUHS) caused by the degradation of heat exchange effectiveness, that is, the poor heat transfer to the Ultimate Heat Sink (UHS). Different causes to such case were observed; intake lines blockages due to ice and foreign biological matters formation and oil spill near the heat sink causing the oil leakage to the heat exchangers tubes. The later cause, oil spill, has been given a special attention here due its potential effects for different nuclear power plants (NPPs) around the world; for example, Finland and the United Arab Emirates (UAE). For the Finnish case, the Finnish nuclear regulator (STUK) took already countermeasures for such scenario by introducing alternative heat sink, cooling towers, for the primary used heat sink, sea water, for one of its nuclear power plants. The abundance of the solar irradiation in the UAE region provides a perfect condition for the implementation of solar power applications. Utilizing this unique characteristic of that region may provide promising alternative and diverse options for solving potential safety related issues of their NPPs. The Solar Chimney Power Plant (SCPP) could be employed to serve as a supporting system to provide emergency power, in the case of SBO, and emergency cooling, in the case of

  17. Application of Solar Chimney Concept to Solve Potential Safety Issues of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Khasawneh, Khalid; PARK, Youn Won

    2014-01-01

    In this paper two main events and their causes have been investigated and a potential alternative supporting system will be provided. The first event to be addressed is the Station Blackout (SBO) caused by the inherent unreliability of the Emergency Diesel Generators (EDGs) and Alternative AC (AAC) power sources. Different parameters affect The EDG unreliability; for instance, mechanical, operational, maintenance and surveillance. Those parameters will be analyzed and linked to plant safety and Core Damage Frequency (CDF). Also the AACs, the SBO diesel generators, will be studied and their operational requirements similarity with the EDGs will be discussed. The second event to be addressed is the Loss of Ultimate Heat Sink (LUHS) caused by the degradation of heat exchange effectiveness, that is, the poor heat transfer to the Ultimate Heat Sink (UHS). Different causes to such case were observed; intake lines blockages due to ice and foreign biological matters formation and oil spill near the heat sink causing the oil leakage to the heat exchangers tubes. The later cause, oil spill, has been given a special attention here due its potential effects for different nuclear power plants (NPPs) around the world; for example, Finland and the United Arab Emirates (UAE). For the Finnish case, the Finnish nuclear regulator (STUK) took already countermeasures for such scenario by introducing alternative heat sink, cooling towers, for the primary used heat sink, sea water, for one of its nuclear power plants. The abundance of the solar irradiation in the UAE region provides a perfect condition for the implementation of solar power applications. Utilizing this unique characteristic of that region may provide promising alternative and diverse options for solving potential safety related issues of their NPPs. The Solar Chimney Power Plant (SCPP) could be employed to serve as a supporting system to provide emergency power, in the case of SBO, and emergency cooling, in the case of

  18. Regulatory application of seismic experience data for nuclear power plants in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Pei-Ying [Nuclear Regulatory Commission, Washington, DC (United States)

    1997-03-01

    On the basis of its review and evaluation (Reference 3) of the SQUG GIP (Reference 2) and on the basis of the differences between current seismic qualification requirements and the criteria and procedures provided in the GIP, the NRC staff does not consider the USI A-46 methodology given in the GIP to be a `seismic qualification` procedure. Rather, the staff considers the GIP methodology to be a seismic adequacy verification procedure, which was developed on the basis of generic equipment earthquake experience data, supplemented by generic equipment test data. The implementation of the GIP approach for USI A-46 plants provides safety enhancement, in certain aspects, beyond the original licensing bases. Therefore, the GIP methodology is an acceptable evaluation method, for USI A-46 plants only, to verify the seismic adequacy of the safe-shutdown equipment installed in the NPPs in the United States. With the new development in the experience-based approach for seismic qualification of equipment currently underway in the U.S. nuclear industry, there is a potential for future regulatory application of an experience-based approach as a seismic qualification method for certain selected equipment installed in NPPs in the United States. However, industry`s use of the experience-based approach will be dependent on the submittal and staff approval of this approach. (J.P.N.)

  19. EPRI's nuclear power plant instrumentation and control program and its applicability to advanced reactors

    International Nuclear Information System (INIS)

    Naser, J.; Torok, R.; Wilkinson, D.

    1997-01-01

    I ampersand C systems in nuclear power plants need to be upgraded over the lifetime of the plant in a reliable and cost-effective manner to replace obsolete equipment, to reduce O ampersand M costs, to improve plant performance, and to maintain safety. This applies to operating plants now and will apply to advanced reactors in the future. The major drivers for the replacement of the safety, control, and information systems in nuclear power plants are the obsolescence of the existing hardware and the need for more cost-effective power production. Competition between power producers is dictating more cost-effective power production. The increasing O ampersand M costs to maintain systems experiencing obsolescence problems is counter to the needs for more cost-effective power production and improved competitiveness. This need for increased productivity applies to government facilities as well as commercial plants. Increasing competition will continue to be a major factor in the operation of both operating plants and advanced reactors. It will continue to dictate the need for improved productivity and cost-effectiveness. EPRI and its member nuclear utilities are working together on an industry wide I ampersand C Program to address I ampersand C issues and to develop cost-effective solutions. A majority of the I ampersand C products and demonstrations being developed under this program will benefit advanced reactors in both the design and operational phases of their life cycle as well as it will benefit existing plants. 20 refs

  20. Application of large-scaled pre-cast components for the construction of water intake for a nuclear power plant

    International Nuclear Information System (INIS)

    Topolnicki, M.

    1976-01-01

    Problem of the construction of water intake for a 4000 MW nuclear power plant located at the seashore is solved. The advantages of application of large-size pre-cast components are presented,. The constructional solutions and proposed technologies are described in detail. (A.S.)

  1. Application of the methodology of safety probabilistic analysis to the modelling the emergency feedwater system of Juragua nuclear power plant

    International Nuclear Information System (INIS)

    Troncoso, M.; Oliva, G.

    1993-01-01

    The application of the methodology developed in the framework of the national plan of safety probabilistic analysis (APS) to the emergency feed water system for the failures of small LOCAS and external electrical supply loss in the nuclear power plant is illustrated in this work. The facilities created by the ARCON code to model the systems and its documentation are also expounded

  2. Nuclear power plant siting

    International Nuclear Information System (INIS)

    Sulkiewicz, M.; Navratil, J.

    The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

  3. The first application of antiseismic friction bearings: the Koeberg nuclear plant

    International Nuclear Information System (INIS)

    Renault, Jean; Richli, Marc; Pavot, Bernard.

    1979-01-01

    The siting of a nuclear plant requires a thoroughgoing analysis of the special seismic conditions of the site chosen and, for certain buildings of the plant, the level of seismicity is a determining factor in the dimensioning of the structures and even of the equipment. The standardization of nuclear plants, however, offers considerable advantages from every point of view, and in particular makes it possible to avoid making a study extending over several years. In order to enable this standardization to spread, it was necessary to make possible, even in highly seismic areas, the building of plants identical with those designed for the French market. With this in view, the SPIE-BATIGNOLLES Company, in association with Electricite de France, has developed a system for reducing the dynamic horizontal effects of an earthquake on the structure of a nuclear plant. This system, featuring essentially a double raft with the interposition of antiseismic bearings composed of blocks of helically reinforced elastomer associated with metal friction plates, is presented. The different phases of its development are shown: preliminary mathematical studies, an experimental study of the bearing apparatus, the elaboration of the technology of manufacture of the bearings, the method of placing at the Koeberg nuclear plant site [fr

  4. Application of extreme value distribution function in the determination of standard meteorological parameters for nuclear power plants

    International Nuclear Information System (INIS)

    Jiang Haimei; Liu Xinjian; Qiu Lin; Li Fengju

    2014-01-01

    Based on the meteorological data from weather stations around several domestic nuclear power plants, the statistical results of extreme minimum temperatures, minimum. central pressures of tropical cyclones and some other parameters are calculated using extreme value I distribution function (EV- I), generalized extreme value distribution function (GEV) and generalized Pareto distribution function (GP), respectively. The influence of different distribution functions and parameter solution methods on the statistical results of extreme values is investigated. Results indicate that generalized extreme value function has better applicability than the other two distribution functions in the determination of standard meteorological parameters for nuclear power plants. (authors)

  5. Proceeding of 35th domestic symposium on applications of structural reliability and risk assessment methods to nuclear power plants

    International Nuclear Information System (INIS)

    2005-06-01

    As the 35th domestic symposium of Atomic Energy Research Committee, the Japan Welding Engineering Society, the symposium was held titled as Applications of structural reliability/risk assessment methods to nuclear energy'. Six speakers gave lectures titled as 'Structural reliability and risk assessment methods', 'Risk-informed regulation of US nuclear energy and role of probabilistic risk assessment', 'Reliability and risk assessment methods in chemical plants', 'Practical structural design methods based on reliability in architectural and civil areas', 'Maintenance activities based on reliability in thermal power plants' and 'LWR maintenance strategies based on Probabilistic Fracture Mechanics'. (T. Tanaka)

  6. Application of risk based inspection as a part of life management of nuclear power plants

    International Nuclear Information System (INIS)

    Vinod, Gopika; Babar, A.K.; Saraf, R.K.; Kushwaha, H.S.; Venkat Raj, V.

    2002-01-01

    Full text: Risk Informed approach is a systematic effort to improve plant safety in a more efficient manner by distributing the available safety resources depending on the importance to plant safety. This approach has found immense application in various aspects associated with Nuclear Power Plants, including design, manufacturing, operation and regulation. Typical applications of Risk Informed approach are in Technical Specification, In-Service Inspection (ISI) requirements, Motor Operated Valve testing, Configuration Control etc. In order to cater to such variety of Probabilistic Safety Assessment (PSA) based Risk Informed requirements, a software package, 'Risk Monitor' has been developed by the authors. An important application of Risk informed approach that has been undertaken for Indian Pressurised Heavy Water Reactor (IPHWR) is towards Risk Informed In-Service Inspection (RI-ISI). Studies are being conducted to evolve an inspection plan that is optimised to provide effective inspections at the right location with a proper inspection frequency. Using risk informed approach, the identification of system / component for inspection resource allocation is based on the results from Level 1 PSA of a NPP. Even though this methodology can be employed on any of the nuclear components/systems such as mechanical systems, instrumentation, etc., as a starting point, piping has been considered for employing Risk Informed Inspection. Plant risk assessment is modelled through the analysis of Core Damage Frequency (CDF) using PSA models. Risk Informed Inspection program of piping involves the estimation of failure probability or frequency of a piping segment and estimation of consequences of piping failures. ISI program changes could affect the failure probability values of piping and can introduce a change in CDF. These effects can be brought out through the implementation of Risk Informed inspection strategy. Various importance measures like Fussel-Vesely, Birnbaum

  7. Loviisa nuclear power plant analyzer

    International Nuclear Information System (INIS)

    Porkholm, K.; Nurmilaukas, P.; Tiihonen, O.; Haenninen, M.; Puska, E.

    1992-12-01

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

  8. Application of sensitivity analysis in nuclear power plant probabilistic risk assessment studies

    International Nuclear Information System (INIS)

    Hirschberg, S.; Knochenhauer, M.

    1986-01-01

    Nuclear power plant probabilistic risk assessment (PRA) studies utilise many models, simplifications and assumptions. Also subjective judgement is widely applied due to lack of actual data. This results in significant uncertainties. Three general types of uncertainties have been identified: (1) parameter uncertainties, (2) modelling uncertainties, and (3) completeness uncertainties. The significance of some of the modelling assumptions and simplifications cannot be investigated by assignment and propagation of parameter uncertainties. In such cases the impact of different options may (and should) be studied by performing sensitivity analyses, which concentrate on the most critical elements. This paper describes several items suitable for close examination by means of application of sensitivity analysis, when performing a level 1 PRA. Sensitivity analyses are performed with respect to: (1) boundary conditions (success criteria, credit for non-safety systems, degree of detail in modelling of support functions), (2) operator actions, (3) treatment of common cause failures (CCFs). The items of main interest are continuously identified in the course of performing a PRA study, as well as by scrutinising the final results. The practical aspects of sensitivity analysis are illustrated by several applications from a recent PRA study. The critical importance of modelling assumptions is also demonstrated by implementation of some modelling features from another level 1 PRA into the reference model. It is concluded that sensitivity analysis leads to insights important for analysts, reviewers and decision makers. (author)

  9. Application of laser cladding method to small-diameter stainless steel pipes in actual nuclear plant

    International Nuclear Information System (INIS)

    Atago, Y.; Yamadera, M.; Tsuji, H.; Shiraiwa, T.; Kanno, M.

    1995-01-01

    Recently, to prevent stress corrosion cracking (SCC) the material of stainless steel (Type 304), a laser cladding method which produces a highly corrosion-resisting coating (cladding) to be formed on the surface of the material was developed. This is applicable to a long distance and narrow space, because of the good accessibility of the YAG (Yttrium-Aluminum Garnet) laser beam that can be transmitted through an optical fiber. In this method, a paste mixed metallic powder and heating resistive organic solvent is firstly placed on the inner surface of a small pipe and then a YAG laser beam transmitted through an optical fiber is irradiated to the paste, which will be melted and formed a clad subsequently, which is excellent in corrosion resistance. Finally, it can be achieved further resistance against the SCC due to the clad layer formed thus on the surface of the material. Recently, this Laser Cladding method was practically and successfully applied to the actual BWR Nuclear Power Plant in Japan. This report introduces the laser cladding technique, the equipments developed for practical application in the field

  10. Study into the applicabilities of lasers for the dismantling of decommissioned nuclear power plant

    International Nuclear Information System (INIS)

    Haferkamp, H.; Bach, F.W.; Vinke, T.; Kinzel, A.; Mack, N.; Kuboschek, M.; Grobe, K.

    1989-01-01

    The project was intended to screen current laser technology for potential applications of laser beams in the dismantling of decommissioned nuclear power plant. As with CO 2 , Nd-YAG, or excimer lasers, developments clearly proceed towards higher output power. The market survey shows the CO 2 -laser to be the most efficient at present, with a great number of laser units available on the market in the range up to 5 kW, and some in the range up to 15 kW. The CO 2 -laser has exclusively been used so far for cutting work in steel plates thicker than 10 mm. Characteristic conditions of application include the high output power of more than 2 kW, long beam lengths, oxygen supply at strongly increased working pressure, sometimes from external sources. The maximum cutting work achieved in the laboratory was 110 mm in structural steel, 90 mm in austenitic steel, and 160 mm in concrete, all under conditions of easy access to the material. It remains to be examined whether steel cutting work at constrained positions will allow separation of wall thicknesses of more than 10 mm. Laser beam cutting under water is feasible in principle but has not been much studied yet. There also are only few sampling results of measurements of dust and aerosol quantities resulting from laser beam cutting work. (orig.) [de

  11. Application of Low Voltage High Resistance Grounding in Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Choong-Koo Chang

    2016-02-01

    Full Text Available Most nuclear power plants now utilize solid grounded low voltage systems. For safety and reliability reasons, the low voltage (LV high resistance grounding (HRG system is also increasingly used in the pulp and paper, petroleum and chemical, and semiconductor industries. Fault detection is easiest and fastest with a solidly grounded system. However, a solidly grounded system has many limitations such as severe fault damage, poor reliability on essential circuits, and electrical noise caused by the high magnitude of ground fault currents. This paper will briefly address the strengths and weaknesses of LV grounding systems. An example of a low voltage HRG system in the LV system of a nuclear power plant will be presented. The HRG system is highly recommended for LV systems of nuclear power plants if sufficient considerations are provided to prevent nuisance tripping of ground fault relays and to avoid the deterioration of system reliability.

  12. Investigation of specific applications of laser cutting for dismantling of nuclear power plants

    International Nuclear Information System (INIS)

    Tarroni, G.; De Zaiacomo, T.; Melandri, C.; Formignani, M.; Barilli, L.; Di Fino, M.; Picini, P.; Galuppi, G.; Rocca, C.; Manassero, G.; Migliorati, B.

    1991-02-01

    The aim of this work, performed on an experimental basis in a frame of strict collaboration between industry (FIAT-CIEI and FIAT-CRF in Turin) and public research laboratories (ENEA-PAS-FIBI in Bologna, ENEA-PAS-ISP and ENEA-TIB-TECNLAS in Rome) and supported by a CEC contract, was to bring out the items for better evaluation of the laser beam application possibilities in dismantling nuclear power plants. The main topics of the research have been: 1) study and definition of the relevant basic parameters ruling the aerosol generation rate and behaviour in terms of physical and chemical characteristics. This work has been performed in a facility specifically designed for aerosol measurements and equipped with a 2kW laser source; 2) study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; 3) study of long distance transmission of the laser beam power performed with a 5kW laser source with an evaluation of the power loss and beam characteristic modifications; 4) study of laser beam technique application for dismantling the Garigliano power plant steam drum in order to better demonstrate the feasibility of the use of this technique. The research resulted in the conclusion that the laser beam is actually appropriate for long distance dismantling of metal components. Although the main aspects of the laser cutting process have been examined, some problems remain to be investigated. This could be performed, after proper cost-benefit evaluation, during a future decommissioning programme. (author)

  13. Investigation of specific applications of laser cutting for dismantling of nuclear power plants

    International Nuclear Information System (INIS)

    Migliorati, B.; Difino, M.; Manassero, G.

    1990-01-01

    The aim of this work, performed on an experimental basis in a frame of strict collaboration between industry (Fiat-CIEI and Fiat-CRF in Turin) and public research laboratories (ENEA-PAS-FIBI in Bologna, ENEA-PAS-ISP and ENEA-TIB-TECNLAS in Rome) and supported by a CEC contract, was to bring out the items for better evaluation of the laser beam application possibilities in dismantling nuclear power plants. The main topics of the research have been: (i) study and definition of the relevant basic parameters ruling the aerosol generation rate and behaviour in terms of physical and chemical characteristics. This work has been performed in a facility specifically designed for aerosol measurements and equipped with a 2kW laser source; (ii) study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; (iii) study of long-distance transmission of the laser beam power performed with a 5KW laser source with an evaluation of the power loss and beam characteristic modifications; (iv) study of laser beam technique application for dismantling the Garigliano power plant steam drum in order to better demonstrate the feasibility of the use of this technique. The research resulted in the conclusion that the laser beam is actually appropriate for long-distance dismantling of metal components. Although the main aspects of the laser cutting process have been examined, some problems remain to be investigated. This could be performed, after proper cost-benefit evaluation, during a future decommissioning programme

  14. Investigation of specific applications of laser cutting for dismantling of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Tarroni, G; De Zaiacomo, T; Melandri, C; Formignani, M; Barilli, L [ENEA - Area Energia, Ambiente e Salute - Centro Ricerche Energia ' Ezio Clementel' - Bologna (Italy); Di Fino, M [ENEA - Area Energia, Ambiente e Salute, Centro Ricerche Energia, Frascati, Rome (Italy); Picini, P; Galuppi, G; Rocca, C [ENEA - Area Energia, Ambiente e Salute, Centro Ricerche Energia, Casaccia, Rome (Italy); Manassero, G [Centro Ricerche FIAT, Orbassano, Torino (Italy); Migliorati, B [FIAT-CIEI, Torino (Italy)

    1991-02-15

    The aim of this work, performed on an experimental basis in a frame of strict collaboration between industry (FIAT-CIEI and FIAT-CRF in Turin) and public research laboratories (ENEA-PAS-FIBI in Bologna, ENEA-PAS-ISP and ENEA-TIB-TECNLAS in Rome) and supported by a CEC contract, was to bring out the items for better evaluation of the laser beam application possibilities in dismantling nuclear power plants. The main topics of the research have been: 1) study and definition of the relevant basic parameters ruling the aerosol generation rate and behaviour in terms of physical and chemical characteristics. This work has been performed in a facility specifically designed for aerosol measurements and equipped with a 2kW laser source; 2) study of the feasibility of local abatement of the aerosols produced and of the pressure drop in the HEPA filters; 3) study of long distance transmission of the laser beam power performed with a 5kW laser source with an evaluation of the power loss and beam characteristic modifications; 4) study of laser beam technique application for dismantling the Garigliano power plant steam drum in order to better demonstrate the feasibility of the use of this technique. The research resulted in the conclusion that the laser beam is actually appropriate for long distance dismantling of metal components. Although the main aspects of the laser cutting process have been examined, some problems remain to be investigated. This could be performed, after proper cost-benefit evaluation, during a future decommissioning programme. (author)

  15. Application of wireless sensor networks in personnel dosage monitoring system of nuclear power plant

    International Nuclear Information System (INIS)

    Chen Yonghong; Zhang Dafa; Jiang Wei; Chen Dengke

    2007-01-01

    Aim to meet the need of personnel dosage monitoring of nuclear power plant, a monitoring system was designed which based on wireless sensor network. First, the basic concept was described; the characteristics of the wireless sensor network applied in the monitoring system of nuclear power plant were also been analyzed; the structure of the system was built too. Finally, the special technologies like the choice of communication mode, the security of communication network and orientation that used in the monitoring system were discussed. (authors)

  16. Application of the Safety Classification of Structures, Systems and Components in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2016-04-01

    This publication describes how to complete tasks associated with every step of the classification methodology set out in IAEA Safety Standards Series No. SSG-30, Safety Classification of Structures, Systems and Components in Nuclear Power Plants. In particular, how to capture all the structures, systems and components (SSCs) of a nuclear power plant to be safety classified. Emphasis is placed on the SSCs that are necessary to limit radiological releases to the public and occupational doses to workers in operational conditions This publication provides information for organizations establishing a comprehensive safety classification of SSCs compliant with IAEA recommendations, and to support regulators in reviewing safety classification submitted by licensees

  17. Review on the application of system engineer model in nuclear power plant

    International Nuclear Information System (INIS)

    Chen Guocai

    2005-01-01

    system engineer was adopted deeply and play important roles in nuclear power plants in United States and Canada, the plant performance indicates that system engineer mode is a good practice. Qinshan CANDU nuclear power plant, established the system engineer mode since commissioning, as a core, system engineer took charge of the preparation of commissioning procedures, organization, coordination and guidance of commissioning execution. Unit 1 was put into commercial operation 43 days in advance and 112 days ahead of schedule for Unit 2 with excellent quality. Commissioning period are just 10.5 and 7.8 months for both Units respectively. Which is the shortest record in the history of CANDU nuclear power plant commissioning up to now. During operation, systems engineer has strength in routine operating and units reliability improvement. Based on the practice of Qinshan CANDU nuclear power plant commissioning and production technical management, the main form of the article in the era of knowledge: its characteristics and advantage and operating mode of the system engineer mode. System engineer is different from project engineer, he act as the master of systems and takes full responsibility for systems technical management. System engineer should do many jobs and improvement schedule to ensure his system in health status. System health monitor is a basic tool in system management, which is useful for equipment performance improvement. At last, the author made a forecast and comment on the prospects for the system engineer in the future. (author)

  18. An application of the 'Bayesian cohort model' to nuclear power plant cost analyses

    International Nuclear Information System (INIS)

    Ono, Kenji; Nakamura, Takashi

    2002-01-01

    We have developed a new method for identifying the effects of calendar year, plant age and commercial operation starting year on the costs and performances of nuclear power plants and also developed an analysis system running on personal computers. The method extends the Bayesian cohort model for time series social survey data proposed by one of the authors. The proposed method was shown to be able to separate the above three effects more properly than traditional methods such as taking simple means by time domain. The analyses of US nuclear plant cost and performance data by using the proposed method suggest that many of the US plants spent relatively long time and much capital cost for modification at their age of about 10 to 20 years, but that, after those ages, they performed fairly well with lower and stabilized O and M and additional capital costs. (author)

  19. Fire risk analysis for nuclear power plants: Methodological developments and applications

    International Nuclear Information System (INIS)

    Kazarians, M.; Apostolakis, G.; Siv, N.O.

    1985-01-01

    A methodology to quantify the risk from fires in nuclear power plants is described. This methodology combines engineering judgment, statistical evidence, fire phenomenology, and plant system analysis. It can be divided into two major parts: (1) fire scenario identification and quantification, and (2) analysis of the impact on plant safety. This article primarily concentrates on the first part. Statistical analysis of fire occurrence data is used to establish the likelihood of ignition. The temporal behaviors of the two competing phenomena, fire propagation and fire detection and suppression, are studied and their characteristic times are compared. Severity measures are used to further specialize the frequency of the fire scenario. The methodology is applied to a switchgear room of a nuclear power plant

  20. Nuclear power plant construction

    International Nuclear Information System (INIS)

    Lima Moreira, Y.M. de.

    1979-01-01

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

  1. Possible applications of power from Temelin nuclear power plant in agriculture of the South Bohemian Region

    International Nuclear Information System (INIS)

    Hosek, V.

    1989-01-01

    The agricultural organizations in the South Bohemian Region have suggested the use of low-potential waste heat from the Temelin nuclear power plant in processing feed potatoes, fodder drying, mushroom production, heating greenhouses and agricultural buildings, drying corn and processing vegetables. Greenhouses should be built on an area of 30 hectares. Hydroponics is expected to be used. The location of the greenhouse area relative to the power plant is described. (M.D.). 6 tabs

  2. Wuergassen nuclear power plant

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The decision of the Federal Court of Administration concerns an application for immediate decommissioning of a nuclear power plant (Wuergassen reactor): The repeal of the permit granted. The decision dismisses the appeal for non-admission lodged by the plaintiffs against the ruling of the Higher Court of Administration (OVG) of North-Rhine Westphalia of December 19th 1988 (File no. 21 AK 8/88). As to the matter in dispute, the Federal Court of Administration confirms the opinion of the Higher Court of Administration. As to the headnotes, reference can be made to that decision. Federal Court of Administration, decision of April 5th 1989 - 7 B 47.89. Lower instance: OVG NW, Az.: 21 AK 8/88. (orig./RST) [de

  3. Application of risk-informed methods to in-service piping inspection in Framatome type nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Jin Hoi; Lee, Jeong Seok; Yun, Eun Sub

    2014-01-01

    The Pressurized water reactor owners group (PWROG) developed and applied a risk-informed in-service inspection (RI-ISI) program, as an alternative to the existing ASME Section XI sampling inspection method. The RI-ISI programs enhance overall safety by focusing inspections of piping at high safety significance (HSS) locations where failure mechanisms are likely to be present. Additionally, the RI-ISI program can reduce nondestructive evaluation (NDE) exams, man-rem exposure for inspectors, and inspection time, among other benefits. The RI-ISI method of in-service piping inspection was applied to 3 units (KSNPs: Korea standard nuclear power plants) and is being deployed to the other units. In this paper, the results of RI-ISI for a Framatome type (France CPI) nuclear power plant are presented. It was concluded that application of RI-ISI to the plant could enhance and maintain plant safety, as well as provide the benefits of greater reliability.

  4. Commercialization of nuclear power plant decommissioning technology

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

    The commercialization of nuclear power plant decommissioning is presented as a step in the commercialization of nuclear energy. Opportunities for technology application advances are identified. Utility planning needs are presented

  5. Application of simulation techniques for accident management training in nuclear power plants

    International Nuclear Information System (INIS)

    2003-05-01

    core. These capabilities include the optimized use of design margins as well as complementary measures for the prevention of accident progression, its monitoring, and the mitigation of severe accidents. Finally, level 5 includes off-site emergency response measures, the objective of which is to mitigate the radiological consequences of significant releases of radioactive material. Accident management is defined in the IAEA Safety Report on Development and Implementation of Accident Management Programmes in Nuclear Power Plants. The IAEA definitions are in line with the definitions of severe accident management in OECD/NEA documents as given, for example. This report describes simulation techniques used in the training of personnel involved in accident management of NPPs. This concerns both the plant personnel and the persons involved in the management of off-site releases. The report pertains to light water reactors (LWRs) and pressurized heavy water reactors (PHWRs), but it can equally be applied to power reactors of other types. The report is intended for use by experts responsible for planning, developing, executing or supervising the training of personnel involved in the implementation of AMPs in NPPs. It concentrates on existing techniques, but future prospects are also discussed. Various simulation techniques are considered, from incorporating graphical interfaces into existing severe accident codes to full-scope replica simulators. Both preventive and mitigative accident management measures, different training levels and different target personnel groups are taken into account. Based on the available information compiled worldwide, present views on the applicability of simulation techniques for the training of personnel involved in accident management are provided in this report. Apart from the introduction, this report consists of four sections and three appendices. In Section 2, specific aspects of accident management are summarized. Basic approaches in the

  6. STAMP model and its application prospect in DCS safety analysis of nuclear power plant

    International Nuclear Information System (INIS)

    Yang Xiaohua; Liu Jie; Liu Zhaohui; Liu Hua; Yu Tonglan

    2013-01-01

    The application of DCS (Digit Control System) is a certain trend for the development of nuclear power. DCS not only improves the control capability of nuclear power system, but also increases the complexity of the system. Traditional safety analysis techniques based on event-chain model are facing challenges. In order to improve the safety performance of nuclear power DCS, the latest research achievement in the field of safety engineering should be focused, studied and applied into nuclear power safety. This paper introduces a new safety analysis model named STAMP (Systems-Theoretic Accident Modeling and Processes) based on the system theory, analyzes its advantages and disadvantages compared with the traditional ones, and explains the basic steps of STPA (STAMP-Based Hazard Analysis) technology. Finally, according to the application status of STAMP at home and abroad, it prospects the development of STAMP in China's nuclear power safety. (authors)

  7. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

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

  8. IAEA'S study on advanced applications of water cooled nuclear power plants

    International Nuclear Information System (INIS)

    Cleveland, J.; McDonald, A.; Rao, A.; )

    2008-01-01

    About one-fifth of the world's energy consumption is used for electricity generation, with nuclear power contributing approximately 15.2% of this electricity. However; most of the world's energy consumption is for heat and transportation. Nuclear energy has considerable potential to penetrate these energy sectors now served by fossil fuels that are characterized by price volatility and finite supply. Advanced applications of nuclear energy include seawater desalination, district heating, and heat for industrial processes. Nuclear energy also has potential to provide a near-term, greenhouse gas free, source of energy for transportation. These applications rely on a source of heat and electricity. Nuclear energy from water-cooled reactors, of course, is not unique in this sense. Indeed, higher temperature heat can be produced by burning natural gas and coal, or through the use of other nuclear technologies such as gas-cooled or liquid-metal-cooled reactors. Water-cooled reactors, however; are being deployed today while other reactor types have had considerably less operational and regulatory experience and will take still some time to be widely accepted in the market. Both seawater desalination and district heating with nuclear energy are well proven, and new seawater desalination projects using water-cooled reactors will soon be commissioned. Provision of process heat with nuclear energy can result in less dependence on fossil fuels and contribute to reductions of greenhouse gases. Importantly, because nuclear power produces base-load electricity at stable and predictable prices, it provides a greenhouse gas free source of electricity for transportation systems (trains and subways), and for electric and plug-in hybrid vehicles, and in the longer term nuclear energy could produce hydrogen for fuel cell vehicles, as well as for other components of a hydrogen economy. These advanced applications can play an important role in enhancing public acceptance of nuclear

  9. Application of the international guidelines for machinery breakdown prevention at nuclear power plants

    International Nuclear Information System (INIS)

    Wendland, W.G.

    2001-01-01

    For more than forty years as a specialized branch of the worldwide insurance industry, the nuclear insurance pools have underwritten property damage protection for nuclear facilities throughout the world. At power plants insured by the pools, an enviable record of operational safety has been attained. Nevertheless, electrical and mechanical equipment does break down occasionally. Although these failures do not necessarily compromise nuclear safety, they can cause significant damage to equipment, leading to a considerable loss of generating revenue and causing sizeable insurance losses. Since insurance companies have a large financial stake in nuclear power plants, their goal is to minimize insurance losses, including the failure of systems and equipment and ensuing consequential damages. To ensure that the insurance risk is properly underwritten, insurance companies analyze loss information, develop loss prevention guidelines and focus loss control activities on those areas where insurance risk is most significant. This paper provides a chronology of the development of the ''International Guidelines for Machinery Breakdown Prevention at Nuclear Power Plants'' and describes the results of insurance inspections conducted using these guidelines. Included is a summary of guideline content and of insurance loss experience between 1962 and 1999. (author)

  10. Application of Nuclear Power Plant Simulator for High School Student Training

    Energy Technology Data Exchange (ETDEWEB)

    Kong, Chi Dong; Choi, Soo Young; Park, Min Young; Lee, Duck Jung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2014-10-15

    In this context, two lectures on nuclear power plant simulator and practical training were provided to high school students in 2014. The education contents were composed of two parts: the micro-physics simulator and the macro-physics simulator. The micro-physics simulator treats only in-core phenomena, whereas the macro-physics simulator describes whole system of a nuclear power plant but it considers a reactor core as a point. The high school students showed strong interests caused by the fact that they operated the simulation by themselves. This abstract reports the training detail and evaluation of the effectiveness of the training. Lectures on nuclear power plant simulator and practical exercises were performed at Ulsan Energy High School and Ulsan Meister High School. Two simulators were used: the macro- and micro-physics simulator. Using the macro-physics simulator, the following five simulations were performed: reactor power increase/decrease, reactor trip, single reactor coolant pump trip, large break loss of coolant accident, and station black-out with D.C. power loss. Using the micro-physics simulator, the following three analyses were performed: the transient analysis, fuel rod performance analysis, and thermal-hydraulics analysis. The students at both high schools showed interest and strong support for the simulator-based training. After the training, the students showed passionate responses that the education was of help for them to get interest in a nuclear power plant.

  11. Application of Nuclear Power Plant Simulator for High School Student Training

    International Nuclear Information System (INIS)

    Kong, Chi Dong; Choi, Soo Young; Park, Min Young; Lee, Duck Jung

    2014-01-01

    In this context, two lectures on nuclear power plant simulator and practical training were provided to high school students in 2014. The education contents were composed of two parts: the micro-physics simulator and the macro-physics simulator. The micro-physics simulator treats only in-core phenomena, whereas the macro-physics simulator describes whole system of a nuclear power plant but it considers a reactor core as a point. The high school students showed strong interests caused by the fact that they operated the simulation by themselves. This abstract reports the training detail and evaluation of the effectiveness of the training. Lectures on nuclear power plant simulator and practical exercises were performed at Ulsan Energy High School and Ulsan Meister High School. Two simulators were used: the macro- and micro-physics simulator. Using the macro-physics simulator, the following five simulations were performed: reactor power increase/decrease, reactor trip, single reactor coolant pump trip, large break loss of coolant accident, and station black-out with D.C. power loss. Using the micro-physics simulator, the following three analyses were performed: the transient analysis, fuel rod performance analysis, and thermal-hydraulics analysis. The students at both high schools showed interest and strong support for the simulator-based training. After the training, the students showed passionate responses that the education was of help for them to get interest in a nuclear power plant

  12. Comparison of methods applicable to evaluation of nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    Cho, N.Z.; Bozoki, G.E.; Youngblood, R.W.

    1986-01-01

    This study compares three probabilistic methods based on the static fault tree analysis, time-dependent unavailability analysis, and Markov analysis, which can be used to evaluate technical specifications in nuclear power plants. They are tested on a sample problem which was devised to closely represent the important and essential characteristics that should be addressed in determination and evaluation of the technical specifications

  13. Study of arcview GIS application in the nuclear power plant emergency response decision support system

    International Nuclear Information System (INIS)

    Li Peng; Chen Lin; Dong Binjiang

    2003-01-01

    It is very significant to apply the technique of GIS to the development of the Nuclear Power Plant Emergency Response Decision Support System. On the basis of the software system ArcView. This paper investigate the framework, the function and the development methods of the system. (authors)

  14. Application of the software system USS to nuclear power plant data handling

    International Nuclear Information System (INIS)

    Wellhausen, U.

    1979-01-01

    The Unified Software System (USS) has been used to establish a data bank of general, economic, and technical nuclear power plant data. On the basis of a test magnetic tape, the principal lay-out of the data bank is described and examples of searches are given. In conclusion an additional programme is presented for sorting numerial parameters in a certain order

  15. Application of the discounted value flows method in production cost calculations for Czechoslovak nuclear power plants

    International Nuclear Information System (INIS)

    Majer, P.

    1990-01-01

    The fundamentals are outlined of the discounted value flows method, which is used in industrial countries for calculating the specific electricity production costs. Actual calculations were performed for the first two units of the Temelin nuclear power plant. All costs associated with the construction, operation and decommissioning of this nuclear power plant were taken into account. With a high degree of certainty, the specific production costs of the Temelin nuclear power plant will lie within the range of 0.32 to 0.36 CSK/kWh. Nearly all results of the sensitivity analysis performed for the possible changes in the input values fall within this range. An increase in the interest rate to above 8% is an exception; this, however, can be regarded as rather improbable on a long-term basis. Sensitivity analysis gave evidence that the results of the electricity production cost calculations for the Temelin nuclear power plant can be considered sufficiently stable. (Z.M.). 7 figs., 2 tabs., 14 refs

  16. Issues arising with the application of optical fiber transmission in class 1E systems in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Antonescu, C.

    1993-01-01

    The application of fiber optic links and networks in safety-critical systems in the next generation of nuclear power plants, as well as in some digital upgrades in present-day plants, will mean that these links must be highly reliable and able to withstand the effect of environmental stressors present at the installation location. This paper discusses the failure modes and age-related mechanisms of fiber optic transmission components and identifies environmental stressors that could adversely affect their reliability over the long term. Some of the standards that could be used in their qualification for safety-critical applications are also discussed briefly

  17. NUCLEAR POWER PLANT

    Science.gov (United States)

    Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

    1963-05-14

    A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

  18. Evaluating the effectiveness of warning systems for nuclear power plant emergencies: criteria and application

    International Nuclear Information System (INIS)

    Sorensen, J.H.

    1984-01-01

    The accident at Three Mile Island Nuclear Power Plant in 1979 was an emergency management disaster. Chief among the problems was ineffective public warning and communications. While it is difficult to assign blame for that condition to any given party or determine if it was due to unique situational factors, the failure led to fairly significant regulatory changes in the arena of public warning and notification. These changes are intended to avoid the problems that arose during the TMI accident. This chapter reviews these regulations and suggests an alternative set of criteria for evaluating warning systems. The criteria are used to assess the effectiveness of the warning system at the Ft. St. Vrain nuclear power plant in Colorado. The paper concludes with some discussion of the lessons learned from the TMI experience as they apply to warning systems for all nuclear generating stations

  19. The development of a task analysis method applicable to the tasks of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Chul; Park, Ji Soo; Baek, Dong Hyeon; Ham, Dong Han; Kim, Huhn [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1996-07-01

    While task analysis is one of the essential processes for human factors studies, traditional methods reveal weaknesses in dealing with the cognitive aspects, which become more critical in modern complex system. This report proposes a cognitive task analysis (CTA) method for identifying cognitive requirements of operators' tasks in nuclear power plants. The proposed CTA method is characterized by the information-oriented concept and procedure-based approach. The task prescription identifies the information requirements and trace the information flow to reveal the cognitive organization of task procedure with emphasis to the relations among the information requirements. The cognitive requirements are then analyzed in terms of cognitive span of task information, cognitive envelope and working memory relief point of t procedures, and working memory load. The proposed method is relatively simple and, possibly being incorporated in a full task analysis scheme, directly applicable to the design/evaluation of human-machine interfaces and operating procedures. A prototype of a computerized support system is developed for supporting the practicality of the proposed method. (Author) 104 refs., 8 tabs., 7 figs.

  20. Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants. Specific Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    The objective of this Safety Guide is to provide recommendations for meeting the IAEA safety requirements in performing or managing a level 2 probabilistic safety assessment (PSA) project for a nuclear power plant; thus it complements the Safety Guide on level 1 PSA. One of the aims of this Safety Guide is to promote a standard framework, standard terms and a standard set of documents for level 2 PSAs to facilitate regulatory and external peer review of their results. It describes all elements of the level 2 PSA that need to be carried out if the starting point is a fully comprehensive level 1 PSA. Contents: 1. Introduction; 2. PSA project management and organization; 3. Identification of design aspects important to severe accidents and acquisition of information; 4. Interface with level 1 PSA: Grouping of sequences; 5. Accident progression and containment analysis; 6. Source terms for severe accidents; 7. Documentation of the analysis: Presentation and interpretation of results; 8. Use and applications of the PSA; Annex I: Example of a typical schedule for a level 2 PSA; Annex II: Computer codes for simulation of severe accidents; Annex III: Sample outline of documentation for a level 2 PSA study.

  1. The development of a task analysis method applicable to the tasks of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Chul; Park, Ji Soo; Baek, Dong Hyeon; Ham, Dong Han; Kim, Huhn [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1996-07-01

    While task analysis is one of the essential processes for human factors studies, traditional methods reveal weaknesses in dealing with the cognitive aspects, which become more critical in modern complex system. This report proposes a cognitive task analysis (CTA) method for identifying cognitive requirements of operators' tasks in nuclear power plants. The proposed CTA method is characterized by the information-oriented concept and procedure-based approach. The task prescription identifies the information requirements and trace the information flow to reveal the cognitive organization of task procedure with emphasis to the relations among the information requirements. The cognitive requirements are then analyzed in terms of cognitive span of task information, cognitive envelope and working memory relief point of t procedures, and working memory load. The proposed method is relatively simple and, possibly being incorporated in a full task analysis scheme, directly applicable to the design/evaluation of human-machine interfaces and operating procedures. A prototype of a computerized support system is developed for supporting the practicality of the proposed method. (Author) 104 refs., 8 tabs., 7 figs.

  2. Applicability of PRA methods and data to the financial risk assessment of nuclear power plants

    International Nuclear Information System (INIS)

    El-Sheik, K.A.

    1985-01-01

    Financial risk assessment, where the probability and severity of financial consequences are estimated, offers a logical framework for organizing and evaluating data pertinent to nuclear power plant accidents. Under the sponsorship of the Electric Power Research Institute, General Electric investigated the feasibility of financial risk assessment of nuclear power plants and of applying PRA methods and data in such an assessment. This paper summarizes the main findings of this investigation. Specifically, the paper discussed the following topics: definition of financial consequences and financial risk; overall approach for financial risk assessment and how it compares with the approach for PRA used in the Reactor Safety Study; and specific financial risk assessment procedures for defining initiating events, plant response sequences, institutional scenarios, and financial consequences and how they compare to analogous procedures for PRA

  3. Nuclear power plants maintenance

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    Nuclear power plants maintenance now appears as an important factor contributing to the competitivity of nuclea energy. The articles published in this issue describe the way maintenance has been organized in France and how it led to an actual industrial activity developing and providing products and services. An information note about Georges Besse uranium enrichment plant (Eurodif) recalls that maintenance has become a main data not only for power plants but for all nuclear industry installations. (The second part of this dossier will be published in the next issue: vol. 1 January-February 1989) [fr

  4. Nuclear Power Plants (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

    Lyerly, Ray L.; Mitchell III, Walter [Southern Nuclear Engineering, Inc.

    1973-01-01

    Projected energy requirements for the future suggest that we must employ atomic energy to generate electric power or face depletion of our fossil-fuel resources—coal, oil, and gas. In short, both conservation and economic considerations will require us to use nuclear energy to generate the electricity that supports our civilization. Until we reach the time when nuclear power plants are as common as fossil-fueled or hydroelectric plants, many people will wonder how the nuclear plants work, how much they cost, where they are located, and what kinds of reactors they use. The purpose of this booklet is to answer these questions. In doing so, it will consider only central station plants, which are those that provide electric power for established utility systems.

  5. Developing a virtual reality application for training Nuclear Power Plant operators: Setting up a database containing dose rates in the refuelling plant

    International Nuclear Information System (INIS)

    Rodenas, J.; Zarza, I.; Burgos, M. C.; Felipe, A.; Sanchez-Mayoral, M. L.

    2004-01-01

    Operators in Nuclear Power Plants can receive high doses during refuelling operations. A training programme for simulating refuelling operations will be useful in reducing the doses received by workers as well as minimising operation time. With this goal in mind, a virtual reality application is developed within the framework of the CIPRES project. The application requires doses, both instantaneous and accumulated, to be displayed at all times during operator training. Therefore, it is necessary to set up a database containing dose rates at every point in the refuelling plant. This database is based on radiological protection surveillance data measured in the plant during refuelling operations. Some interpolation routines have been used to estimate doses through the refuelling plant. Different assumptions have been adopted in order to perform the interpolation and obtain consistent data. In this paper, the procedures developed to set up the dose database for the virtual reality application are presented and analysed. (authors)

  6. Case study: Proposed application of project management techniques for construction of nuclear power plant in Malaysia

    International Nuclear Information System (INIS)

    Syahirah Abdul Rahman; Phongsakorn Prak Tom; Wan Abd Hadi Wan Abu Bakar; Shaharum Ramli

    2010-01-01

    This study discusses the techniques of project management for the construction of nuclear power plants that can be used in Malaysia. Nuclear power reactors are expected to apply is the categories of Gen III + reactor where it is safer and more modern than the first generation of reactors built in the 1970s. The objective of this study is that the construction of this reactor to be completed by the stipulated time and not exceed the cost estimates. In addition, project management is also able to meet all the specifications and achieve the quality standard. In this study, the techniques used in project management to ensure the success of construction projects of nuclear power plants are a Gantt Chart, CPM/ PERT and Microsoft Project. From the study, found that these techniques can assist in facilitating the management of the project for the construction of nuclear power plants to ensure that the estimated time and cost can be managed more effectively as well as quality of care. (author)

  7. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2005-01-01

    This 2005 edition of the Elecnuc booklet summarizes in tables all numerical data relative to the nuclear power plants worldwide. These data come from the PRIS database managed by the IAEA. The following aspects are reviewed: 2004 highlights; main characteristics of reactor types; map of the French nuclear power plants on 2005/01/01; worldwide status of nuclear power plants at the end of 2004; units distributed by countries; nuclear power plants connected to the grid by reactor-type group; nuclear power plants under construction on 2004; evolution of nuclear power plant capacities connected to the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear power plants by country at the end 2004; performance indicator of PWR units in France; trend of the generation indicator worldwide; 2004 load factor by owners; units connected to the grid by countries at 12/31/2004; status of licence renewal applications in USA; nuclear power plants under construction at 12/31/2004; shutdown reactors; exported nuclear capacity in net MWe; exported and national nuclear capacity connected to the grid; exported nuclear power plants under construction or order; exported and national nuclear capacity under construction or order; recycling of plutonium in LWR; Mox licence plant projects; Appendix - historical development; acronyms, glossary

  8. Study on application of operating experience to new nuclear power plant

    International Nuclear Information System (INIS)

    Hong, Nam Pyo

    1991-01-01

    From the standpoint of designing the nuclear power plant, nine operating units have been designed and constructed as turn-key base by foreign Nuclear Steam Supply System (NSSS) Suppliers or as component base by foreign Architect/Engineer companies. In case of the component base project, the owner of electric company generally has merits that owner's operational experiences can be effectively incorporated from the beginning stage of design by A/E. Even though six nuclear units, Kori Units 3 and 4, Yonggwang Units 1 and 2, and Ulchin Units 1 and 2, were designed as component base by foreign A/E's, operational experience feedback from Kori Unit 1, such as design improvement and system upgrade, could not be reflected, because the design process of the following units started well ahead before Kori Unit 1 operating experience is obtained enough to reflect on future nuclear power plant design. It can be stated that foreign A/E's used their experience in designing nuclear projects on very limited basis

  9. Nuclear power plant safety

    International Nuclear Information System (INIS)

    Otway, H.J.

    1974-01-01

    Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

  10. CSRL application to nuclear power plant diagnosis and sensor data validation

    International Nuclear Information System (INIS)

    Hashemi, S.; Punch, W.F. III; Hajek, B.K.

    1988-01-01

    During operational abnormalities, plant operators rely on the information provided by the plant sensors and associated alarms. The sensors' usefulness however, is quickly diminished by their large number and the extremely difficult task of interpreting and comprehending the provided information. Malfunction diagnosis can be further complicated by the existence of conflicting data which can lead to an incorrect diagnostic conclusion. Thus, the value of an operator aid to assist plant personnel in interpreting the available data and diagnosing the plant malfunctions is obvious. Recent work at the Ohio State University Laboratory for Artificial Intelligence Research (OSU-LAIR) and the Nuclear Engineering department has concentrated on the problem of performing expert system diagnosis using potentially invalid sensor data. That is, the authors have been developing expert systems that can perform diagnostic problem solving despite the existence of some conflicting data in the domain. This work has resulted in enhancement of a programming tool, CSRL, that allows domain experts to create a diagnostic system that will be, to some degree, tolerant of bad data. The domain of Boiling Water Nuclear Power Plants was chosen as a test domain to show usefulness of the ideas under real world conditions

  11. CSRL application to nuclear power plant diagnosis and sensor data validation

    International Nuclear Information System (INIS)

    Hashemi, S.; Punch, W.F. III; Hajek, B.K.

    1987-01-01

    During operational abnormalities, plant operators rely on the information provided by the plant sensors and associated alarms. The sensors' usefulness however, is quickly diminished by their large number and the extremely difficult task of interpreting and comprehending the provided information. Malfunction diagnosis can be further complicated by the existence of conflicting data which can lead to an incorrect diagnostic conclusion. Thus, the value of an operator aid to assist plant personnel in interpreting the available data and diagnosing the plant malfunctions is obvious. Recent work at the Ohio State University Laboratory for Artificial Intelligence Research (OSU-LAIR) and the Nuclear Engineering Department has concentrated on the problem of performing expert system diagnosis using potentially invalid sensor data. Expert systems have been developed that can perform diagnostic problem solving despite the existence of some conflicting data in the domain. This work has resulted in enhancement of a programming tool, CSRL, that allows domain experts to create a diagnostic system that will be, to some degree, tolerant of bad data. The domain of Boiling Water Nuclear Power Plants was chosen as a test domain to show usefulness of the ideas under real world conditions

  12. Methodological evolutions in human-machine cooperative problem solving with applications to nuclear plants

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Takahashi, Makoto

    2002-01-01

    A new framework for attaining higher safety of nuclear plants through introducing machine intelligence and robots has been proposed in this paper. The main emphasis of the framework is placed on user-centered human-machine cooperation in solving problems experienced during conducting operation, monitoring and maintenance activities in nuclear plants. In this framework, human operator is supposed to take initiative of actions at any moment of operation. No attempt has been made to replace human experts by machine intelligence and robots. Efforts have been paid to clarify the expertise and behavioral model of human experts so that the developed techniques are consistent with human mental activities in solving highly complicated operational and maintenance problems. Several techniques essential to the functioning of the framework have also been introduced. Modification of environment to provide support information has also been pursued to realize the concept of ubiquitous computing. (author)

  13. Nuclear plant life extension

    International Nuclear Information System (INIS)

    Negin, C.A.

    1989-01-01

    The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

  14. The Evaluation and Application Plan Report for the Development of Nuclear Power Plant DCS Using CASE Tools

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B.Y.; Moon, H.J.; Yoon, M.H.; Lee, Y.K. [Korea Electric Power Research Institute, Taejon (Korea)

    2000-06-01

    This report contains the evaluation and application plan report for the development of nuclear power plant DCS using CASE tools. In this report, the necessity of using CASE tools is considered and a available CASE environment is suggested. And, also according to the IEEE Std 1209 Recommended Practice for Evaluation and Selection of CASE Tools, their functional and economical evaluation about available commercial CASE tools is performed and described. (author). 6 figs., 3 tabs.

  15. Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lyssakov, V.N.; Kang, K.S.

    2005-01-01

    These guidelines have been developed under an International Atomic Energy Agency (IAEA) Co-ordinated Research Project (CRP) titled ''Surveillance Programme Results Application to Reactor Pressure Vessel Integrity Assessment.'' The IAEA has sponsored a series of five CRPs that have led to a focus on measuring the best irradiation fracture parameters using relatively small test specimens for assuring structural integrity of reactor pressure vessel (RPV) materials in Nuclear Power Plants (NPPs)

  16. Real-time variables dictionary (RTVD), and expert system for development of real-time applications in nuclear power plants

    International Nuclear Information System (INIS)

    Senra Martinez, A.; Schirru, R.; Dutra Thome Filho, Z.

    1990-01-01

    It is presented in this paper a computerized methodology based on a data dictionary managed by an expert system called Real-Time Variables Dictionary (RTVD). This system is very usefull for development of real-time applications in nuclear power plants. It is described in details the RTVD functions and its implantation in a VAX 8600 computer. It is also pointed out the concepts of artificial intelligence used in teh RTVD

  17. CAGE: A standard design application to nuclear power plants of Cofrentes, Almaraz and Trillo

    International Nuclear Information System (INIS)

    Cubian Martinez, B.; Gomez Gomez, M.; Zornoza Garcia-Andrade, J.; Turrion Lopez, F.; Barrio, M. A. del; Cobos Perabad, A.; Garcia-Serrano, J. L.

    2016-01-01

    Design, engineering, supply, construction, assembly, supervision and quality control, construction management and commissioning of Alternative Emergency Management Centres (CAGES) of nuclear power plants Cofrentes (CNC), Almaraz (CNA) and Trillo (CNT) were awarded in the first half of 2014 to Iberdrola Engineering and Construction (IIC). After obtaining the required building permits issued by municipalities, following the delivery of the corresponding, basic project and execution, in January 2015, began civil works at CNA, CNT and in February of this year in CNC. (Author)

  18. Development of operator thinking model and its application to nuclear reactor plant operation system

    International Nuclear Information System (INIS)

    Miki, Tetsushi; Endou, Akira; Himeno, Yoshiaki

    1992-01-01

    At first, this paper presents the developing method of an operator thinking model and the outline of the developed model. In next, it describes the nuclear reactor plant operation system which has been developed based on this model. Finally, it has been confirmed that the method described in this paper is very effective in order to construct expert systems which replace the reactor operator's role with AI (artificial intelligence) systems. (author)

  19. High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant

    International Nuclear Information System (INIS)

    Beck, J.M.; Collins, J.W.; Garcia, C.B.; Pincock, L.F.

    2010-01-01

    High Temperature Gas Reactors (HTGR) have been designed and operated throughout the world over the past five decades. These seven HTGRs are varied in size, outlet temperature, primary fluid, and purpose. However, there is much the Next Generation Nuclear Plant (NGNP) has learned and can learn from these experiences. This report captures these various experiences and documents the lessons learned according to the physical NGNP hardware (i.e., systems, subsystems, and components) affected thereby.

  20. Application of a model-based fault detection system to nuclear plant signals

    International Nuclear Information System (INIS)

    Gross, K.C.; Singer, R.M.; Wegerich, S.W.; Herzog, J.P.; VanAlstine, R.; Bockhorst, F.

    1997-01-01

    To assure the continued safe and reliable operation of a nuclear power station, it is essential that accurate online information on the current state of the entire system be available to the operators. Such information is needed to determine the operability of safety and control systems, the condition of active components, the necessity of preventative maintenance, and the status of sensory systems. To this end, ANL has developed a new Multivariate State Estimation Technique (MSET) which utilizes advanced pattern recognition methods to enhance sensor and component operational validation for commercial nuclear reactors. Operational data from the Crystal River-3 (CR-3) nuclear power plant are used to illustrate the high sensitivity, accuracy, and the rapid response time of MSET for annunciation of a variety of signal disturbances

  1. Application of a methodology to determine priorities for nuclear power plant safety issues

    International Nuclear Information System (INIS)

    Daling, P.M.

    1988-01-01

    The Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) is sponsoring a research program to determine priorities of nuclear power plant safety issues. A methodology has been developed at the Pacific Northwest Laboratory (PNL) to provide technical assistance in the development of risk and cost estimates for implementing resolutions to the safety issues. The information development methods are intended to provide the NRC with a consistent level of information for use in ranking the issues. The NRC uses this information, along with judgmental factors, to rank the issues for further consideration by the NRC staff. The primary purpose of the priority rankings are to assist in the allocation of resources to issues that have high potential for reducing public risk as well as to remove issues from further consideration that have little safety significance

  2. Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants

    International Nuclear Information System (INIS)

    2016-05-01

    Revised to take into consideration findings from the Fukushima Daiichi nuclear power plant accident, IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, has introduced some new concepts with respect to the earlier safety standard published in the year 2000. The preparation of SSR-2/1 (Rev. 1) was carried out with constant and intense involvement of IAEA Member States, but some new requirements, because of the novelty of the concepts introduced and the complexity of the issues, are not always interpreted in a unique way. The IAEA is confident that a complete clarification and a full understanding of the new requirements will be available when the supporting safety guides for design and safety assessment of nuclear power plants are prepared. The IAEA expects that the effort devoted to the preparation of this publication, which received input and comments from several Member States and experts, will also facilitate and harmonize the preparation or revision of these supporting standards

  3. Design quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    1986-07-01

    This Standard contains the requirements for the quality assurance program applicable to the design phase of a nuclear plant, and is applicable to the design of safety-related equipment, systems, and structures, as identified by the owner. 1 fig

  4. Design quality assurance for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-07-01

    This Standard contains the requirements for the quality assurance program applicable to the design phase of a nuclear plant, and is applicable to the design of safety-related equipment, systems, and structures, as identified by the owner. 1 fig.

  5. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

    A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. (author)

  6. Monitored Natural Attenuation as a Remediation Strategy for Nuclear Power Plant Applications

    Science.gov (United States)

    Kim, K.; Bushart, S.

    2009-12-01

    A NRC Information Notice (IN 2006-13) was produced to inform holders of nuclear operating licenses “of the occurrence of radioactive contamination of ground water at multiple facilities due to undetected leakage from facility structures, systems, or components (SSCs) that contain or transport radioactive fluids” so that they could consider actions, as appropriate, to avoid similar problems. To reinforce their commitment to environmental stewardship the nuclear energy industry has committed to improving management of situations that have the potential to lead to the inadvertent release of radioactive fluids. This Industry Groundwater Protection Initiative, finalized in June 2007 as [NEI 07-07], calls for implementation and improvement of on-site groundwater monitoring programs and enhanced communications with stakeholders and regulators about situations related to inadvertent releases. EPRI developed its Groundwater Protection Program to provide the nuclear energy industry with the technical support needed to implement the Industry Groundwater Initiative. An objective of the EPRI Groundwater Protection Program is to provide the nuclear industry with technically sound guidance for implementing and enhancing on-site groundwater monitoring programs. EPRI, in collaboration with the EPRI Groundwater Protection Committee of utility members, developed the EPRI Groundwater Protection Guidelines for Nuclear Power Plants (EPRI Report 1015118, November 2007), which provides site-specific guidance for implementing a technically sound groundwater monitoring program. The guidance applies a graded approach for nuclear plants to tailor a technically effective and cost efficient groundwater monitoring program to the site’s hydrogeology and risk for groundwater contamination. As part of the Groundwater Protection Program, EPRI is also investigating innovative remediation technologies for addressing low-level radioactive contamination in soils and groundwater at nuclear power

  7. Backpropagation architecture optimization and an application in nuclear power plant diagnostics

    International Nuclear Information System (INIS)

    Basu, A.; Bartlett, E.B.

    1993-01-01

    This paper presents a Dynamic Node Architecture (DNA) scheme to optimize the architecture of backpropagation Artificial Neural Networks (ANNs). This network scheme is used to develop an ANN based diagnostic adviser capable of identifying the operating status of a nuclear power plant. Specifically, a ''root'' network is trained to diagnose if the plant is in a normal operating condition or not. In the event of an abnormal condition, and other ''classifier'' network is trained to recognize the particular transient taking place. these networks are trained using plant instrumentation data gathered during simulations of the various transients and normal operating conditions at the Iowa Electric Light and Power Company's Duane Arnold Energy Center (DAEC) operator training simulator

  8. Backpropagation architecture optimization and an application in nuclear power plant diagnostics

    International Nuclear Information System (INIS)

    Basu, A.; Bartlett, E.B.

    1993-01-01

    This paper presents a Dynamic Node Architecture (DNA) scheme to optimize the architecture of backpropagation Artificial Neural Networks (ANNs). This network scheme is used to develop an ANN based diagnostic adviser capable of identifying the operating status of a nuclear power plant. Specifically, a root network is trained to diagnose if the plant is in a normal operating condition or not. In the event of an abnormal condition, another classifier network is trained to recognize the particular transient taking place. These networks are trained using plant instrumentation data gathered during simulations of the various transients and normal operating conditions at, the Iowa Electric Light and Power Company's Duane Arnold Energy Center (DAEC) operator training simulator

  9. Basic safety principles for nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1989-01-01

    To ensure the safety operation of nuclear power plant, one should strictly adhere to the implelmentation of safety codes and the establishment of nuclear safety code system, as well as the applicable basic safety principles of nuclear power plants. This article briefly introduce the importance of nuclear codes and its economic benefits and the implementation of basic safety principles to be accumulated in practice for many years by various countries

  10. Development of a dose database in the refuelling scenario of a nuclear power plant for a virtual reality application

    International Nuclear Information System (INIS)

    Rodenas, J.; Zarza, I.; Pascual, A.; Felipe, A.; Sanchez-Mayoral, M.L.

    2002-01-01

    Operators in Nuclear Power Plants can receive high doses during refuelling operation. A training program simulating refuelling operations will be useful to reduce doses received by workers as well as to minimise operation time. With this goal in mind a Virtual Reality application is developed in the frame of CIPRES Project (Calculos Interactivos de Proteccion Radiologica en un Entorno de Simulacion - Interactive Calculations of Radiological Protection in a Simulation Environment), a RD project sponsored by IBERINCO and developed jointly by IBERINCO and the Nuclear Engineering Department of the Polytechnic University of Valencia. The Virtual Reality application requires the possibility of displaying doses, both instantaneous and accumulated, at all times during the operator training. Therefore, it is necessary to elaborate a database containing dose rates at every point of the refuelling plant. This database is elaborated from Radiological Protection Surveillance data measured throughout the plant during refuelling operation. To estimate doses throughout the refuelling plant some interpolation routines have been used. Different assumptions have been adopted in order to perform the interpolation and obtain consistent data. In this paper, procedures developed to elaborate the dose database for the Virtual Reality application are presented and analysed

  11. 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

  12. Generic requirements specification for qualifying a commercially available PLC for safety-related applications in nuclear power plants. Final report

    International Nuclear Information System (INIS)

    Ostenso, A.; May, R.

    1996-12-01

    This is a specification for qualifying a commercially available PLC for application to safety systems in nuclear power plants. The specifications are suitable for evaluating a particular PLC product line as a platform for safety-related applications, establishing a suitable qualification test program, and confirming that the manufacturer has a quality assurance program that is adequate for safety-related applications or is sufficiently complete that, with a reasonable set of compensatory actions, it can be brought into conformance. The specification includes requirements for: (1) quality assurance measures applied to the qualification activities, (2) documentation to support the qualification, and (3) documentation to provide the information needed for applying the qualified PLC platform to a specific application. The specifications are designed to encompass a broad range of safety applications; however, qualifying a particular platform for a different range of applications can be accomplished by appropriate adjustments to the requirements

  13. The Apatity nuclear heating plant project: modern technical and economic issues of nuclear heat application in Russia

    International Nuclear Information System (INIS)

    Adamov, E.O.; Romenkov, A.A.

    1998-01-01

    Traditionally Russia is a country with advanced structure of centralized heat supply. Many thermal plants and heating networks need technical upgrading to improve their technical and economic efficiency. Fossil fuelled heating capacities have a negative influence on ecology, which can be seen especially in the northern regions of Russia. Furthermore, fossil fuel prices are rising in Russia. The above factors tend to intensify the need for alternative heat sources being capable of solving the problem. Nuclear heat sources may be the alternative. In this paper, the main features of a proposed NHP in the Murmansk region are summarized. (author)

  14. Nuclear power plant analyzer

    International Nuclear Information System (INIS)

    Stritar, A.

    1986-01-01

    The development of Nuclear Power Plant Analyzers in USA is described. There are two different types of Analyzers under development in USA, the forst in Idaho and Los Alamos national Lab, the second in brookhaven National lab. That one is described in detail. The computer hardware and the mathematical models of the reactor vessel thermalhydraulics are described. (author)

  15. Nuclear plant scram reduction

    International Nuclear Information System (INIS)

    Wiegle, H.R.

    1986-01-01

    The Nuclear Utility Management and Human Resources Committee (NUMARC) is a confederation of all 55 utilities with nuclear plants either in operation or under construction. NUMARC was formed in April 1984 by senior nuclear executives with hundreds of man-years of plant experience to improve (plant) performance and resolve NRC concerns. NUMARC has adopted 10 commitments in the areas of management, training, staffing and performance. One of these commitments is to strive to reduce automatic trips to 3 per year per unit for calendar year 1985 for plants in commercial operation greater than 3 years (with greater than 25% capacity factor). This goal applies to any unplanned automatic protection system trips at any time when the reactor is critical. Each utility has committed to develop methods to thoroughly evaluate all unplanned automatic trips to identify the root causes and formulate plans to correct the root causes thus reducing future unplanned scrams. As part of this program, the Institute of Nuclear Power Operations (INPO) collects and evaluates information on automatic reactor trips. It publishes the results of these evaluations to aid the industry to identify root causes and corrective actions

  16. Application of an expert system for real time diagnosis of the limiting conditions for operation in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Paiva, Gustavo Varanda; Schirru, Roberto, E-mail: gustavopaiva@poli.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (brazil). Programa de Engenharia Nuclear

    2015-07-01

    In the history of nuclear power plants operation safety is an important factor to be considered and for this, the use of resistant materials and the application of redundant systems are used to make a plant with high reliability. Through the acquisition of experience with time and accidents that happened in the area, it was observed that the importance of creating methods that simplify the operator work in making decisions in accidents scenarios is an important factor in ensuring the safety of nuclear power plants. This work aims to create a program made with the Python language, which with the use of an expert systems be able to apply, in real time, the rules contained in the Limiting Conditions for Operation (LCO) and tell to the operator the occurrence of any limiting conditions and the occurrence of failure to perform the require actions in the time to completion. The generic structure used to represent the knowledge of the expert system was a fault tree where the events of this tree are objects in program. To test the accuracy of the program a simplified model of a fault tree was used that represents the LCO of the nuclear power station named Central Nuclear Almirante Alvaro Alberto 1. With the results obtained in the analysis of the simplified model it was observed a significant reduction in the time to identify the LCO, showing that the implementation of this program to more complex models of fault tree would be viable.(author)

  17. Application of an expert system for real time diagnosis of the limiting conditions for operation in nuclear power plants

    International Nuclear Information System (INIS)

    Paiva, Gustavo Varanda; Schirru, Roberto

    2015-01-01

    In the history of nuclear power plants operation safety is an important factor to be considered and for this, the use of resistant materials and the application of redundant systems are used to make a plant with high reliability. Through the acquisition of experience with time and accidents that happened in the area, it was observed that the importance of creating methods that simplify the operator work in making decisions in accidents scenarios is an important factor in ensuring the safety of nuclear power plants. This work aims to create a program made with the Python language, which with the use of an expert systems be able to apply, in real time, the rules contained in the Limiting Conditions for Operation (LCO) and tell to the operator the occurrence of any limiting conditions and the occurrence of failure to perform the require actions in the time to completion. The generic structure used to represent the knowledge of the expert system was a fault tree where the events of this tree are objects in program. To test the accuracy of the program a simplified model of a fault tree was used that represents the LCO of the nuclear power station named Central Nuclear Almirante Alvaro Alberto 1. With the results obtained in the analysis of the simplified model it was observed a significant reduction in the time to identify the LCO, showing that the implementation of this program to more complex models of fault tree would be viable.(author)

  18. Application of PHEBUS results to benchmarking of nuclear plant safety codes

    International Nuclear Information System (INIS)

    Birchley, J.; Cripps, R.; Guentay, S.; Hosemann, J.P.

    2001-01-01

    The PHEBUS Fission Product project comprises six nuclear reactor severe accident simulations, using prototypic core materials and representative geometry and boundary conditions for the coolant loop and containment. The data thus produced are being used to benchmark the computer tools used for nuclear plant accident analysis to reduce the excessive conservatism typical for estimates of the radiological source term. A set of calculations has been carried out to simulate the results of experiment PHEBUS FPT-1 through each of its main stages, using computer models and methods analogous to those currently employed at PSI for assessments of Swiss nuclear plants. Good agreement for the core degradation and containment behaviour builds confidence in the models, while some open questions remain concerning some aspects of the release of fission products from the fuel, their transport and chemical speciation. Of potentially great importance to the reduction in source term estimates is the formation of the non-volatile species, silver iodide. Current investigations are focused on the uncertainty concerning fission product behaviour and the stability of silver iodide under irradiation. (author)

  19. Development of automated patrol-type monitoring and inspection system for nuclear power plant and application to actual plant

    International Nuclear Information System (INIS)

    Senoo, Makoto; Koga, Kazunori; Hirakawa, Hiroshi; Tanaka, Keiji

    1996-01-01

    An automated patrol-type monitoring and inspection system was developed and applied in a nuclear power plant. This system consists of a monorail, a monitoring robot and an operator's console. The monitoring robot consists of a sensor unit and a control unit. Three kinds of sensor, a color ITV camera, an infrared camera and a microphone are installed in the sensor unit. The features of this monitoring robot are; (1) Weights 15 kg with a cross-sectional dimensions of 152 mm width and 290 mm height. (2) Several automatic monitoring functions are installed using image processing and frequency analysis for three sensor signals. (author)

  20. Application of the failure modes and effects analysis technique to the emergency cooling system of an experimental nuclear power plant

    International Nuclear Information System (INIS)

    Conceicao Junior, Osmar; Silva, Antonio Teixeira e

    2009-01-01

    This study consists on the application of the failure modes and effects analysis (FMEA), a hazard identification and a risk assessment technique, to the emergency cooling system (ECS), of an experimental nuclear power plant. The choice of this technique was due to its detailed analysis of each component of the system, enabling the identification of all possible ways of failure and its related consequences (in order of importance), allowing the designer to improve the system, maximizing its security and reliability. Through the application of this methodology, it could be observed that the ECS is an intrinsically safe system, in spite of the modifications proposed. (author)

  1. Application of space and aviation technology to improve the safety and reliability of nuclear power plant operations. Final report

    International Nuclear Information System (INIS)

    1980-04-01

    This report investigates various technologies that have been developed and utilized by the aerospace community, particularly the National Aeronautics and Space Administration (NASA) and the aviation industry, that would appear to have some potential for contributing to improved operational safety and reliability at commercial nuclear power plants of the type being built and operated in the United States today. The main initiator for this study, as well as many others, was the accident at the Three Mile Island (TMI) nuclear power plant in March 1979. Transfer and application of technology developed by NASA, as well as other public and private institutions, may well help to decrease the likelihood of similar incidents in the future

  2. Nuclear plant safety

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The four-member New York Power Pool Panel concluded that, for a number of reasons, no nuclear power plant in New York State is prone to the type of accident that occurred at Three Mile Island (TMI). The Panel further concluded that changes in operating practices, both regulatory and voluntary, and heightened sensitivity to reactor-core-cooling requirements will substantially reduce the chances for another such accident anywhere. Panel members found that New York State utilities have taken a responsible attitude with regard to requirements set forth by the Nuclear Regulatory Commission (NRC) as a result of the TMI accident. In a cover letter that accompanied the report to Federal and New York state officials, New York Power Pool Executive Committee Chairman Francis E. Drake, Jr. expressed hope that the report will alleviate public fears of nuclear reactors and promote wider acceptance of nuclear energy as an economic and safe means of power production. 17 references

  3. Nuclear plants - military hostages

    International Nuclear Information System (INIS)

    Ramberg, B.

    1986-01-01

    Recent events suggest that nuclear reactors could make tempting military or terrorist targets. Despite the care with which most reactors are built, studies document their vulnerability to willful destruction through disruption of coolant mechanisms both inside and outside the containment building. In addition to reactors, such nuclear support facilities as fuel fabrication, reprocessing, and waste storage installations may be attractive military targets. A nuclear bomb which exploded in the vicinity of a reactor could increase its lethal effects by one-third. The implications of this is vulnerability for Middle East stability as well as to other volatile regions. The author suggests several avenues for controlling the dangers: international law, military and civil defense, facility siting, increasing plant safety, and the international management of nuclear energy. 21 references

  4. A SAS/AF application to administrate and query a file of incidents occurring in foreign nuclear power plants

    International Nuclear Information System (INIS)

    Durbec, V.

    1994-07-01

    The Research and Development Division of Electricite de France has a file of incidents occurring in foreign pressurized water nuclear power stations. These incidents have an impact either on safety or reliability. The file is stored on an IBM 3090. For each incident, a docket is assigned, containing the identity of the nuclear plant and information in the form of code or text on the incident. An application has been built with the SAS System under IBM (MVS) in order to: - allow the input of new nuclear plant identities, monthly operating coefficients and new incidents; - subset data from each SAS data set, according to selection criteria (country, manufacturers, period, materials, etc...) in the form of coded fields and characters strings; -calculate simple statistical analyses on subset data (histograms of break duration, distribution of operating coefficients, cross-tabulation tables of sets and materials which bring about the incident) with a restitution on screen and/or printer; - edit an annual booklet containing general results of functioning of plants. After validation, data retrieved from the database are used in probabilistic safety analysis of nuclear power plants and materials designing studies (comparison with French materials, identification of factors having an impact on performance). The application is an interactive menu-driven tool and contains data entry screens (for new data or selection criteria). These screens have been built with SAS/AF software and Screen Control Language. Data selection and processing have been developed with Base SAS and SAS/GRAPH software. (author). 1 ref., 6 figs., 2 tabs

  5. Applications of SLAR in nuclear power plant siting: A case history

    Science.gov (United States)

    Siegal, B. S.

    1980-01-01

    Over 10,000 square km of side-looking airborne radar (SLAR) imagery was obtained and analyzed for the siting of the first nuclear power plant in the Republic of the Philippines. The imagery was obtained using the Motorola APS/AN-94D (X-band) real aperture system as part of an overall remote sensing program to site and evaluate potential site regions. Analysis of SLAR images, in conjunction with LANDSAT, color, black and white, and thermal infrared images, provided basic information on structure, relative geochronology, stratigraphy, geomorphology, and ground water, which facilitated field operations and data synthesis.

  6. Application of non-monotonic logic to failure diagnosis of nuclear power plant

    International Nuclear Information System (INIS)

    Takahashi, M.; Kitamura, M.; Sugiyama, K.

    1989-01-01

    A prototype diagnosis system for nuclear power plants was developed based on Truth Maintenance systems: TMS and Dempster-Shafer probability theory. The purpose of this paper is to establish basic technique for more intelligent, man-computer cooperative diagnosis system. The developed system is capable of carrying out the diagnostic inference under the imperfect observation condition with the help of the proposed belief revision procedure with TMS and the systematic uncertainty treatment with Dempster-Shafer theory. The usefulness and potentiality of the present non-monotonic logic were demonstrated through simulation experiments

  7. FRAMEWORK AND APPLICATION FOR MODELING CONTROL ROOM CREW PERFORMANCE AT NUCLEAR POWER PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L Boring; David I Gertman; Tuan Q Tran; Brian F Gore

    2008-09-01

    This paper summarizes an emerging project regarding the utilization of high-fidelity MIDAS simulations for visualizing and modeling control room crew performance at nuclear power plants. The key envisioned uses for MIDAS-based control room simulations are: (i) the estimation of human error associated with advanced control room equipment and configurations, (ii) the investigative determination of contributory cognitive factors for risk significant scenarios involving control room operating crews, and (iii) the certification of reduced staffing levels in advanced control rooms. It is proposed that MIDAS serves as a key component for the effective modeling of cognition, elements of situation awareness, and risk associated with human performance in next generation control rooms.

  8. Application of radioactive methods for the measurement of physical parameters used in industrial nuclear plants

    International Nuclear Information System (INIS)

    Bignan, G.

    1989-01-01

    The thesis presents the development of non-destructive and non-intrusive assay using source of rays (neutrons or gammas) which is external to the system to characterize (activation methods). They are intended to measure physical values used in industrial nuclear plants (Fissile matter concentration, neutronic multiplicity, presence of heavy nuclei...). The presentation is as follows: - Theoretical study of the suggested methods and development of signal processing to ensure the representativeness of the measurement. - Experimental qualification. - Implantation of these techniques in an industrial context [fr

  9. Task oriented design of robot kinematics using grid method and its application to nuclear power plant

    International Nuclear Information System (INIS)

    Chang, Pyung-Hun; Park, Joon-Young

    2002-01-01

    This paper presents a Task Oriented Design method for robot kinematics based on grid method, widely used in finite difference method and heat transfer/fluid flow analyses. This approach drastically reduces complexities and computational burden due to previous approaches. More specifically, the grid method with a new formulation simplifies the design to a problem of three-design-variable unit grid, which does not require to solve inverse/forward kinematics. The effectiveness of the grid method has been confirmed through a kinematics design of a robot for nuclear power plants. (author)

  10. FRAMEWORK AND APPLICATION FOR MODELING CONTROL ROOM CREW PERFORMANCE AT NUCLEAR POWER PLANTS

    International Nuclear Information System (INIS)

    Ronald L Boring; David I Gertman; Tuan Q Tran; Brian F Gore

    2008-01-01

    This paper summarizes an emerging project regarding the utilization of high-fidelity MIDAS simulations for visualizing and modeling control room crew performance at nuclear power plants. The key envisioned uses for MIDAS-based control room simulations are: (1) the estimation of human error associated with advanced control room equipment and configurations, (2) the investigative determination of contributory cognitive factors for risk significant scenarios involving control room operating crews, and (3) the certification of reduced staffing levels in advanced control rooms. It is proposed that MIDAS serves as a key component for the effective modeling of cognition, elements of situation awareness, and risk associated with human performance in next generation control rooms

  11. 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)

  12. Materials integrity analysis for application of POSCO developed STS to Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hyun-Young, Ch.; Tae-Eun, J.; Young-Sik, K.

    2009-01-01

    Full text of publication follows: POSCO has developed duplex stainless steel (S32750) and hyper super duplex stainless steels for the purpose of using them in the secondary circulation cooling water system in Korean nuclear power plants. This system supplies seawater to cooling water heat exchanger tubes, related pipes and chlorine injection system. In normal operation, seawater is supplied to heat exchanger through the exit of circulation pump headers and the heat exchanged sea water is extracted to the discharge pipes in circulation cooling water system connected to the circulation water discharge lines. The flow velocity of circulation cooling water system in nuclear power plants is high and damages of components from corrosion are severe. Therefore, this environment makes requiring of using high strength and high corrosion resistant steels. Hyper duplex stainless steel (27Cr-7.0Ni-2.5Mo-3.2W-0.35N) has been newly developed in Korea and is being improved for applying to nuclear power plants. In this study, the physical and mechanical properties and corrosion resistance of currently producing stainless steels and newly developed materials are qualitatively evaluated in comparative to commercial stainless steels in other countries. The properties of weld are analyzed and the best compositions of welding rod are suggested. The optimum weld condition is derived for ensuring HAZ phase ratios and controlling weld cracks. For applying these materials to the seawater heat exchanger, CCT and CPT in weldments are measured using mock-up tube testers that are newly designed for this study. Coupons of candidate materials are introduced in the real system and corrosion resistance of them are analyzed. As results of all experiments, the current CCT and CPT criteria in Korean nuclear power plants are reviewed, and the more actual and strengthened criteria will be suggested. The real scale components made of newly developed hyper super duplex stainless steel will be applied to

  13. Register of international standard NP on IT based wireless application in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, I. W.; Choi, Y. S.; Lee, J. C.

    2011-04-01

    DC draft of standard technical report for wireless applications in NPP is developed, which is a Korean IT technologies. Wireless technologies are forwardwd to converging technologies nuclear and IT area. These technologies are supported to reduce vulnerability against cyber attacks and are forwarded to international standards which met with the nuclear environment requirements. DC draft of standard technical report is provided and circulated. Korean experts participate in Plenary meeting for IEC TC45/SC45A and intermediate meeting for IEC SC45A/WGA3 and 9. Korean expert takes the chair of wireless session at ANS winter conference. Visible light communication is experimented for feasibility study on reducing vulnerability against cyber attacks. VLC is capable of robust wireless communication against cyber attacks. This is suggested to describe a method for technical report. Issue DTR for wireless applications in NPP in 2012

  14. Development of pilot model of virtual nuclear power plant and its application to radiation management

    International Nuclear Information System (INIS)

    Kang, K. D.; Sin, S. W.

    2002-01-01

    Using Virtual Reality (VR) technique, a real model for radiation controlled area in nuclear power plant was developed and a feasibility study to develop a computational program to estimate radiation dose was performed. For this purpose a pilot model with an dynamic function and bi-directional communication was developed. This model was enhanced from the existing 3-D single-directional communication. In this pilot model, a plant visitor needs a series of security checking process initially. If he(she) enters the controlled area and approaches radiation hazard area, the alarms with warning lamp will be initiated automatically. Throughout the test to connect this model from both domestic and international sites in various time zones it has proven that it showed a sufficient performance. Therefore this model can be applied to broad fields as radiation protection procedures photographic data, on-line dose program

  15. Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Swain, A D; Guttmann, H E

    1983-08-01

    The primary purpose of the Handbook is to present methods, models, and estimated human error probabilities (HEPs) to enable qualified analysts to make quantitative or qualitative assessments of occurrences of human errors in nuclear power plants (NPPs) that affect the availability or operational reliability of engineered safety features and components. The Handbook is intended to provide much of the modeling and information necessary for the performance of human reliability analysis (HRA) as a part of probabilistic risk assessment (PRA) of NPPs. Although not a design guide, a second purpose of the Handbook is to enable the user to recognize error-likely equipment design, plant policies and practices, written procedures, and other human factors problems so that improvements can be considered. The Handbook provides the methodology to identify and quantify the potential for human error in NPP tasks.

  16. Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report

    International Nuclear Information System (INIS)

    Swain, A.D.; Guttmann, H.E.

    1983-08-01

    The primary purpose of the Handbook is to present methods, models, and estimated human error probabilities (HEPs) to enable qualified analysts to make quantitative or qualitative assessments of occurrences of human errors in nuclear power plants (NPPs) that affect the availability or operational reliability of engineered safety features and components. The Handbook is intended to provide much of the modeling and information necessary for the performance of human reliability analysis (HRA) as a part of probabilistic risk assessment (PRA) of NPPs. Although not a design guide, a second purpose of the Handbook is to enable the user to recognize error-likely equipment design, plant policies and practices, written procedures, and other human factors problems so that improvements can be considered. The Handbook provides the methodology to identify and quantify the potential for human error in NPP tasks

  17. Estimating the cost of delaying a nuclear power plant: methodology and application

    International Nuclear Information System (INIS)

    Hill, L.J.; Tepel, R.C.; Van Dyke, J.W.

    1985-01-01

    This paper presents an analysis of an actual 24-month nuclear power plant licensing delay under alternate assumptions about regulatory practice, sources of replacement power, and the cost of the plant. The analysis focuses on both the delay period and periods subsequent to the delay. The methodology utilized to simulate the impacts involved the recursive interaction of a generation-costing program to estimate fuel-replacement costs and a financial regulatory model to concomitantly determine the impact on the utility, its ratepayers, and security issues. The results indicate that a licensing delay has an adverse impact on the utility's internal generation of funds and financial indicators used to evaluate financial soundness. The direction of impact on electricity rates is contingent on the source of fuel used for replacement power. 5 references, 5 tables

  18. Pulsed nuclear power plant

    International Nuclear Information System (INIS)

    David, C.V.

    1986-01-01

    This patent describes a nuclear power plant. This power plant consists of: 1.) a cavity; 2.) a detonatable nuclear device in a central region of the cavity; 3.) a working fluid inside of the cavity; 4.) a method to denote a nuclear device inside of the cavity; 5.) a mechanical projection from an interior wall of the cavity for recoiling to absorb a shock wave produced by the detonation of the nuclear device and thereby protecting the cavity from damage. A plurality of segments defines a shell within the cavity and a plurality of shock absorbers, each connecting a corresponding segment to a corresponding location on the wall of the cavity. Each of these shock absorbers regulate the recoil action of the segments; and 6.) means for permitting controlled extraction of a quantity of hot gases from the cavity produced by the vaporization of the working fluid upon detonation of the nuclear device. A method of generating power is also described. This method consists of: 1.) introducing a quantity of water in an underground cavity; 2.) heating the water in the cavity to form saturated steam; 3.) detonating a nuclear device at a central location inside the cavity; 4.) recoiling plate-like elements inside the cavity away from the central location in a mechanically regulated and controlled manner to absorb a shock wave produced by the nuclear device detonation and thereby protect the underground cavity against damage; 5.) extracting a quantity of superheated steam produced by the detonation of the nuclear device; and 6.) Converting the energy in the extracted superheated steam into electrical power

  19. Thermo-mecano-metallurgical modelling of welding: application to welded joints in nuclear power plants

    International Nuclear Information System (INIS)

    Cosimo, Alejandro

    2014-01-01

    framework OOFELIE. It is shown that the speed-ups obtained with the proposed HROMs are good enough, even when the speed-up is computed using the time taken by the full model run in parallel. The developed computational framework is applied to the solution of a real life application problem, more specifically, to the simulation of a large welded structure of a nuclear power plant for the prediction of WRS. (author) [es

  20. Development and application of objective uncertainty measures for nuclear power plant transient analysis[Dissertation 3897

    Energy Technology Data Exchange (ETDEWEB)

    Vinai, P

    2007-10-15

    For the development, design and licensing of a nuclear power plant (NPP), a sound safety analysis is necessary to study the diverse physical phenomena involved in the system behaviour under operational and transient conditions. Such studies are based on detailed computer simulations. With the progresses achieved in computer technology and the greater availability of experimental and plant data, the use of best estimate codes for safety evaluations has gained increasing acceptance. The application of best estimate safety analysis has raised new problems that need to be addressed: it has become more crucial to assess as to how reliable code predictions are, especially when they need to be compared against safety limits that must not be crossed. It becomes necessary to identify and quantify the various possible sources of uncertainty that affect the reliability of the results. Currently, such uncertainty evaluations are generally based on experts' opinion. In the present research, a novel methodology based on a non-parametric statistical approach has been developed for objective quantification of best-estimate code uncertainties related to the physical models used in the code. The basis is an evaluation of the accuracy of a given physical model achieved by comparing its predictions with experimental data from an appropriate set of separate-effect tests. The differences between measurements and predictions can be considered stochastically distributed, and thus a statistical approach can be employed. The first step was the development of a procedure for investigating the dependence of a given physical model's accuracy on the experimental conditions. Each separate-effect test effectively provides a random sample of discrepancies between measurements and predictions, corresponding to a location in the state space defined by a certain number of independent system variables. As a consequence, the samples of 'errors', achieved from analysis of the entire

  1. Development and application of objective uncertainty measures for nuclear power plant transient analysis

    International Nuclear Information System (INIS)

    Vinai, P.

    2007-10-01

    For the development, design and licensing of a nuclear power plant (NPP), a sound safety analysis is necessary to study the diverse physical phenomena involved in the system behaviour under operational and transient conditions. Such studies are based on detailed computer simulations. With the progresses achieved in computer technology and the greater availability of experimental and plant data, the use of best estimate codes for safety evaluations has gained increasing acceptance. The application of best estimate safety analysis has raised new problems that need to be addressed: it has become more crucial to assess as to how reliable code predictions are, especially when they need to be compared against safety limits that must not be crossed. It becomes necessary to identify and quantify the various possible sources of uncertainty that affect the reliability of the results. Currently, such uncertainty evaluations are generally based on experts' opinion. In the present research, a novel methodology based on a non-parametric statistical approach has been developed for objective quantification of best-estimate code uncertainties related to the physical models used in the code. The basis is an evaluation of the accuracy of a given physical model achieved by comparing its predictions with experimental data from an appropriate set of separate-effect tests. The differences between measurements and predictions can be considered stochastically distributed, and thus a statistical approach can be employed. The first step was the development of a procedure for investigating the dependence of a given physical model's accuracy on the experimental conditions. Each separate-effect test effectively provides a random sample of discrepancies between measurements and predictions, corresponding to a location in the state space defined by a certain number of independent system variables. As a consequence, the samples of 'errors', achieved from analysis of the entire database, are

  2. Application of wire sawing method to decommissioning of nuclear power plant. Cutting test with turbine pedestal of thermal power plant

    International Nuclear Information System (INIS)

    Hasegawa, Hideki; Uchiyama, Noriyuki; Sugiyama, Kazuya; Yamashita, Yoshitaka; Watanabe, Morishige

    1995-01-01

    It is very important to reduce radioactive waste volume, and to reduce radiation dose to workers and to the public during dismantling of the activated concrete in the decommissioning stage of a nuclear power plant. For the above, we studied a dismantling method which can separate activated concrete from non-activated concrete safely and effectively. Considering the state of legal regulation about radioactive waste disposal, and the state of developing of decommissioning technologies, we come to a conclusion that wire sawing method is feasible as a concrete cutting method. This study was carried out to evaluate the availability of the wire sawing method to dismantling of concrete structures of nuclear power plants. This study consists of concrete cutting rate test and concrete block cutting test. The former is to obtain data about cutting rate with various steel ratios while the latter is to obtain data about working time and man hour of the whole work with wire sawing. Thirty-six year old turbine pedestal of a thermal power plant was selected as a test piece to simulate actual decommissioning work of nuclear power plant, taking its massive concrete volume and age. Taking account of the handling in the building, the wire sawing machine with motor driven was used in this study considering that it did not produce exhaust gas. The concrete cutting rate test was performed with parameter of steel ratio in the concrete, wire tension and cutting direction. In the concrete block cutting test, imaging the actual cutting situation, cubic blocks which side was approximately 1 meter were taken out, and a large block to be cut and to be taken out is a section of 1m x 1.5m x 10m. Test results are shown below. The difference of cutting rate was mainly caused by the difference of reinforcement steel ratio. Working time data of installation, removal of machines and cutting were obtained. Data on secondary waste (dust, drainage and sludge) and environmental effect (noise and

  3. Beloyarsk Nuclear Power Plant

    International Nuclear Information System (INIS)

    1997-01-01

    The Beloyarsk Nuclear Power Plant (BNPP) is located in Zarechny, approximately 60 km east of Ekaterinberg along the Trans-Siberian Highway. Zarechny, a small city of approximately 30,000 residents, was built to support BNPP operations. It is a closed city to unescorted visitors. Residents must show identification for entry. BNPP is one of the first and oldest commercial nuclear power plants in Russia and began operations in 1964. As for most nuclear power plants in the Russian Federation, BNPP is operated by Rosenergoatom, which is subordinated to the Ministry of Atomic Energy of the Russian Federation (Minatom). BNPP is the site of three nuclear reactors, Units 1, 2, and 3. Units 1 and 2, which have been shut-down and defueled, were graphite moderated reactors. The units were shut-down in 1981 and 1989. Unit 3, a BN-600 reactor, is a 600 MW(electric) sodium-cooled fast breeder reactor. Unit 3 went on-line in April 1980 and produces electric power which is fed into a distribution grid and thermal power which provides heat to Zarechny. The paper also discusses the SF NIKIET, the Sverdiovsk Branch of NIKIET, Moscow, which is the research and development branch of the parent NIKEIT and is primarily a design institute responsible for reactor design. Central to its operations is a 15 megawatt IVV research reactor. The paper discusses general security and fissile material control and accountability at these two facilities

  4. Application of genetic algorithm for reliability allocation in nuclear power plants

    International Nuclear Information System (INIS)

    Yang, Joon-Eon; Hwang, Mee-Jung; Sung, Tae-Yong; Jin, Youngho

    1999-01-01

    Reliability allocation is an optimization process of minimizing the total plant costs subject to the overall plant safety goal constraints. Reliability allocation was applied to determine the reliability characteristics of reactor systems, subsystems, major components and plant procedures that are consistent with a set of top-level performance goals; the core melt frequency, acute fatalities and latent fatalities. Reliability allocation can be performed to improve the design, operation and safety of new and/or existing nuclear power plants. Reliability allocation is a kind of a difficult multi-objective optimization problem as well as a global optimization problem. The genetic algorithm, known as one of the most powerful tools for most optimization problems, is applied to the reliability allocation problem of a typical pressurized water reactor in this article. One of the main problems of reliability allocation is defining realistic objective functions. Hence, in order to optimize the reliability of the system, the cost for improving and/or degrading the reliability of the system should be included in the reliability allocation process. We used techniques derived from the value impact analysis to define the realistic objective function in this article

  5. Application of Digital Technology for the Plant Protection System in Ulchin Nuclear Power Plant Units 5 and 6

    International Nuclear Information System (INIS)

    Deucksoo, Lee; Insik, Kim

    2006-01-01

    Since the completion of construction of Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3 and 4), the first units of the OPR (Optimized Power Reactor) series, various advanced design features have been incorporated to the following OPRs. The Ulchin Nuclear Power Plant Units 5 and 6(UCN 5 and 6) which started commercial operation in Korea from 2004 and 2005 respectively, are designed to provide improvements in safety, reliability and costs by applying both advanced proven technology and experiences gained from the construction and operation of the previous OPRs. Among those improvements, the digital plant protection system (DPPS) and the digital engineered safety feature actuation system (DESFAS) are the key elements to the UCN 5 and 6 designs. The DPPS and DESFAS utilizing the digital computer technology offer a solution to the obsolescence problem of analog system. These features also provide the potential for additional benefits such as ease of maintenance, increased performance, reduction of internal and external cross channel wiring, improvement of the surveillance testability and flexibility of control logic programming change. During the initial design stage, the Korean regulatory body had evaluated these design concepts intensively and concluded it to be acceptable for the safety point of view. Also, in-depth review on the detailed design and the special evaluation/audit for the software design process has been performed to secure the quality of the software. As a result, every issue raised during licensing review has been clarified and the operating licenses for the UCN 5 and 6 were issued in October, 2003 and October, 2004 respectively, by the government. In this paper, design characteristics of the UCN 5 and 6 are introduced, and advanced design features and implementation process are presented focused on the DPPS/DESFAS with some benefit analysis results. (authors)

  6. Nuclear Plant Data Bank

    International Nuclear Information System (INIS)

    Booker, C.P.; Turner, M.R.; Spore, J.W.

    1986-01-01

    The Nuclear Plant Data Bank (NPDB) is being developed at the Los Alamos National Laboratory to assist analysts in the rapid and accurate creation of input decks for reactor transient analysis. The NPDB will reduce the time and cost of the creation or modification of a typical input deck. This data bank will be an invaluable tool in the timely investigation of recent and ongoing nuclear reactor safety analysis. This paper discusses the status and plans for the NPDB development and describes its anticipated structure and capabilities

  7. Application of concrete filled steel bearing wall to inner concrete structure fro PWR nuclear power plant

    International Nuclear Information System (INIS)

    Sekimoto, Hisashi; Tanaka, Mamoru; Inoue, Kunio; Fukihara, Masaaki; Akiyama, Hiroshi.

    1992-01-01

    'Concrete filled steel bearing wall', applied to the inner concrete structure for PWR nuclear power plant, was developed for rationalization of construction procedure at site. It was concluded through preliminary studies that this new type of wall, where concrete is placed between steel plates, is best suited for the strength members of the above structure, due to the high strength and ductility of surface steel plates and the confinement effect of filled concrete. To verify the behavior from the elastic range to the inelastic range, the ultimate strength and the failure mechanism, and to clarify experimentally the structural integrity of the inner concrete structure, which was composed of a concrete filled steel bearing wall, against seismic lateral loads, horizontal loading tests using a 1/10th scale model of the inner concrete structure for PWR nuclear power plant were conducted. As a result of the tests, the inner concrete structure composed of a concrete filled steel bearing wall appeared to have a larger load carrying capacity and a higher ductility as compared with that composed of a reinforced concrete wall. (author)

  8. Design and evaluation of warning systems: application to nuclear power plants

    International Nuclear Information System (INIS)

    Pe Benito-Claudio, C.

    1986-01-01

    This study starts by defining and explaining key concepts about warning, both as a process and a system. Thereafter, it presents a quantitative, probabilistic, and decision-oriented methodology for designing and evaluating a warning system. It illustrates the methodology for the case of rare, controllable, and potentially disastrous technological events, such as accidents in nuclear power plants. The methodology covers and links the three principal components of a warning system - signal (which is mainly technical), warning dissemination, and warning response (which are mainly social) - thereby allowing the relative evaluation of technological and social measures for reducing risks. Analytical principles and techniques of risk and decision analyses are applied. It defines a probabilistic performance measure to characterize each component of a warning system, and a value measure to assess the overall effectiveness of the system. An important aspect of this work is the integration, into one analytical model, of the results of engineering studies, such as probabilistic risk assessments of nuclear power plants, and of empirical findings on human response to warning in sociological research. The models, calculations, and sensitivity analyses are done with influence diagrams that are both intuitive and mathematical. This work puts particular emphasis on the study of behavioral response of individuals to warning

  9. Application of optical diagnosis to aged low-voltage cable insulation in nuclear plants

    International Nuclear Information System (INIS)

    Katagiri, Junichi; Takezawa, Yoshitaka; Shouji, Hiroshi

    2008-01-01

    We have developed a novel non-destructive optical diagnosis technique for low-voltage cable insulations used in nuclear power plants. The key features of this diagnosis are the use of two wavelengths to measure the change in reflective absorbance (ΔA R ), the use of polarized light to measure crystallinity and the use of element volatilizing to measure fluorescence. Chemical kinetics is used to predict the lifetimes of the cable insulations. When cable insulations darken and harden by time degradation, the ΔA R and depolarization parameters increase. This means that the cross-linking density in the cable insulations increases due to deterioration reactions. When the cross-linking density of insulation increases, its elasticity, corresponding to the material's life, increases. Similarly, as the crystallinity increases due to the change in the high-order structure of the insulating resin caused by irradiation, its elongation property decreases. The elongation property of insulation is one of the most important parameters that can be used to evaluate material lifetimes, because it relates to elasticity. The ΔA R correlated with the elongation property, and the correlation coefficient of an accelerated experiment using model pieces was over 0.9. Thus, we concluded that this optical diagnosis should be applied to evaluate the degradation of cable insulations used in nuclear power plants. (author)

  10. Feasibility study for application of mixture working fluid cycle to nuclear reactor power plant

    International Nuclear Information System (INIS)

    Takeuchi, Yutaka; Ohshima, Iwao; Shiomi, Hirozo; Miyamae, Nobuhiko; Hiramatsu, Miki; Montani, Mitsuto

    1999-01-01

    There exists a large amount of unused energy in nuclear power plants. However, it consists of relatively low temperature energy, so it is difficult to generate electricity by the conventional water-steam cycle. In order to utilize such low temperature energy, we applied a mixture working fluid cycle called as the Kalina cycle to a light water nuclear reactor power plant. The Kalina cycle uses a working fluid composed of ammonia and water to create a variable temperature boiling process. We applied a saturation type Kalina cycle with single stage ammonia-water separation process as a bottoming cycle to a conventional water-steam cycle of a 1100MWe class BWR as an example case. The input heat source is the exhaust or the partial extraction of a low pressure turbine (LPT). A steady state chemical process modeling code ASPENPLUS was used for the sensitivity analyses. The maximum efficiency was calculated to be realized when using the lowest heat sink temperature, 8degC. The additional electrical output is about 95 MWe when using the exhaust of LPT and is about 127 MWe when using the partial extraction of LPT. Namely, about 4.3% of the exhaust heat for the former case and about 5.8% for the latter case can be utilized as electrical power, respectively. (author)

  11. Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Park, Hae Kyun; Kim, Sang Nyung

    2013-01-01

    Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was conservatively calculated

  12. Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hae Kyun; Kim, Sang Nyung [Kyung Hee Univ., Yongin (Korea, Republic of)

    2013-10-15

    Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was

  13. Ardennes nuclear power plant

    International Nuclear Information System (INIS)

    1974-12-01

    The SENA nuclear power plant continued to operate, as before, at authorized rated power, namely 905MWth during the first half year and 950MWth during the second half year. Net energy production:2028GWh; hours phased to the line: 7534H; availability factor: 84%; utilization factor: 84%; total shutdowns:19; number of scrams:10; cost per KWh: 4,35 French centimes. Overall, the plant is performing very satisfactory. Over the last three years net production has been 5900GWh, corresponding to in average utilization factor of 83%

  14. Nuclear power plant

    International Nuclear Information System (INIS)

    Orlov, V.V.; Rineisky, A.A.

    1975-01-01

    The invention is aimed at designing a nuclear power plant with a heat transfer system which permits an accelerated fuel regeneration maintaining relatively high initial steam values and efficiency of the steam power circuit. In case of a plant with three circuits the secondary cooling circuit includes a steam generator with preheater, evaporator, steam superheater and intermediate steam superheater. At the heat supply side the latter is connected with its inlet to the outlet of the evaporator and with its outlet to the low-temperature side of the secondary circuit

  15. An improved gate valve for critical applications in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kalsi, M.S.; Alvarez, P.D.; Wang, J.K.; Somagyi, D. [Kalsi Engineering, Inc., Sugar Land, TX (United States)] [and others

    1996-12-01

    U.S. Nuclear Regulatory Commission Generic Letters 89-10 for motor-operated valves (MOVs) and 95-07 for all power-operated valves document in detail the problems related to the performance of the safety-related valves in nuclear power plants. The problems relate to lack of reliable operation under design basis conditions including higher than anticipated stem thrust, unpredictable valve behavior, damage to the valve internals under blowdown/high flow conditions, significant degradation of performance when cycled under AP and flow, thermal binding, and pressure locking. This paper describes an improved motor-operated flexible wedge gate valve design, the GE Sentinel Valve, which is the outcome of a comprehensive and systematic development effort undertaken to resolve the issues identified in the NRC Generic Letters 89-10 and 95-07. The new design provides a reliable, long-term, low maintenance cost solution to the nuclear power industry. One of the key features incorporated in the disc permits the disc flexibility to be varied independently of the disc thickness (pressure boundary) dictated by the ASME Section III Pressure Vessel & Piping Code stress criteria. This feature allows the desired flexibility to be incorporated in the disc, thus eliminating thermal binding problems. A matrix of analyses was performed using finite element and computational fluid dynamics approaches to optimize design for stresses, flexibility, leak-tightness, fluid flow, and thermal effects. The design of the entire product line was based upon a consistent set of analyses and design rules which permit scaling to different valve sizes and pressure classes within the product line. The valve meets all of the ASME Section III Code design criteria and the N-Stamp requirements. The performance of the valve was validated by performing extensive separate effects and plant in-situ tests. This paper summarizes the key design features, analyses, and test results.

  16. An improved gate valve for critical applications in nuclear power plants

    International Nuclear Information System (INIS)

    Kalsi, M.S.; Alvarez, P.D.; Wang, J.K.; Somagyi, D.

    1996-01-01

    U.S. Nuclear Regulatory Commission Generic Letters 89-10 for motor-operated valves (MOVs) and 95-07 for all power-operated valves document in detail the problems related to the performance of the safety-related valves in nuclear power plants. The problems relate to lack of reliable operation under design basis conditions including higher than anticipated stem thrust, unpredictable valve behavior, damage to the valve internals under blowdown/high flow conditions, significant degradation of performance when cycled under AP and flow, thermal binding, and pressure locking. This paper describes an improved motor-operated flexible wedge gate valve design, the GE Sentinel Valve, which is the outcome of a comprehensive and systematic development effort undertaken to resolve the issues identified in the NRC Generic Letters 89-10 and 95-07. The new design provides a reliable, long-term, low maintenance cost solution to the nuclear power industry. One of the key features incorporated in the disc permits the disc flexibility to be varied independently of the disc thickness (pressure boundary) dictated by the ASME Section III Pressure Vessel ampersand Piping Code stress criteria. This feature allows the desired flexibility to be incorporated in the disc, thus eliminating thermal binding problems. A matrix of analyses was performed using finite element and computational fluid dynamics approaches to optimize design for stresses, flexibility, leak-tightness, fluid flow, and thermal effects. The design of the entire product line was based upon a consistent set of analyses and design rules which permit scaling to different valve sizes and pressure classes within the product line. The valve meets all of the ASME Section III Code design criteria and the N-Stamp requirements. The performance of the valve was validated by performing extensive separate effects and plant in-situ tests. This paper summarizes the key design features, analyses, and test results

  17. The performance regulatory approach in quality assurance: Its application to safety in nuclear power plants

    International Nuclear Information System (INIS)

    Sajaroff, Pedro M.

    2000-01-01

    In early 1991, the IAEA assembled an Advisory Group on the Comprehensive Revision of the Code and the Safety on Quality Assurance of the NUSS Programme. The Group was made up by specialists from a number of countries and from ISO, FORATOM, the EC and the IAEA itself, and its objective was completed in June 1995. This paper is aimed at describing the conceptual contents of the final draft of the revision 2 of the 50-C-QA Code 'Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Facilities' (hereinafter, the Code) which is essentially based on performance. Although the performance regulatory approach is not new in Argentina and in other countries, what is indeed novel is applying performance based QA. In such a way the Code will contribute to preventing both QA misinterpretations (i.e., a formalistic regulatory requirement) and the execution of non-effective work without attaining the needed quality level (what may be seen as a pathological deviation of QA). The Code contains ten basic requirements to be adopted when QA programmes are established and implemented in nuclear power plants. The goal is improving safety through an improvement in the methods applied for attaining quality. In line with the current developments in quality management techniques, priority is given to effectiveness of the QA programme. All the involved individuals (that is those in the managerial level, those performing the work and those assessing the work performed) must contribute to quality in a co-ordinated manner. The revised Safety Guides are being introduced, standing out those non existing before. Interrelation between quality assurance, safety culture and quality culture is to be noted. Besides QA for safety-related software mentioned as an issue to be considered by the IAEA. (author)

  18. Exxon Nuclear WREM-based NJP-BWR ECCS evaluation model and example application to the Oyster Creek Plant

    International Nuclear Information System (INIS)

    Krysinski, T.L.; Bjornard, T.A.; Steves, L.H.

    1975-01-01

    A proposed integrated ECCS model for non-jet pump boiling water reactors is presented, using the RELAP4-EM/BLOWDOWN and RELAP4-EM/SMALL BREAK portions of the Exxon Nuclear WREM-based Generic PWR Evaluation Model coupled with the ENC NJP-BWR Fuel Heatup Model. The results of the application of the proposed model to Oyster Creek are summarized. The results of the break size sensitivity study using the proposed model for the Oyster Creek Plant are presented. The application of the above results yielded the MAPLHGR curves. Included are a description of the proposed non-jet pump boiling water reaction evaluation model, justification of its conformance with TOCFR50, Appendix K, the adopted Oyster Creek plant model, and results of the analysis and sensitivity studies. (auth)

  19. Reliability analysis of operator's monitoring behavior in digital main control room of nuclear power plants and its application

    International Nuclear Information System (INIS)

    Zhang Li; Hu Hong; Li Pengcheng; Jiang Jianjun; Yi Cannan; Chen Qingqing

    2015-01-01

    In order to build a quantitative model to analyze operators' monitoring behavior reliability of digital main control room of nuclear power plants, based on the analysis of the design characteristics of digital main control room of a nuclear power plant and operator's monitoring behavior, and combining with operators' monitoring behavior process, monitoring behavior reliability was divided into three parts including information transfer reliability among screens, inside-screen information sampling reliability and information detection reliability. Quantitative calculation model of information transfer reliability among screens was established based on Senders's monitoring theory; the inside screen information sampling reliability model was established based on the allocation theory of attention resources; and considering the performance shaping factor causality, a fuzzy Bayesian method was presented to quantify information detection reliability and an example of application was given. The results show that the established model of monitoring behavior reliability gives an objective description for monitoring process, which can quantify the monitoring reliability and overcome the shortcomings of traditional methods. Therefore, it provides theoretical support for operator's monitoring behavior reliability analysis in digital main control room of nuclear power plants and improves the precision of human reliability analysis. (authors)

  20. Application of flow network models of SINDA/FLUINT{sup TM} to a nuclear power plant system thermal hydraulic code

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Ji Bum [Institute for Advanced Engineering, Yongin (Korea, Republic of); Park, Jong Woon [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    In order to enhance the dynamic and interactive simulation capability of a system thermal hydraulic code for nuclear power plant, applicability of flow network models in SINDA/FLUINT{sup TM} has been tested by modeling feedwater system and coupling to DSNP which is one of a system thermal hydraulic simulation code for a pressurized heavy water reactor. The feedwater system is selected since it is one of the most important balance of plant systems with a potential to greatly affect the behavior of nuclear steam supply system. The flow network model of this feedwater system consists of condenser, condensate pumps, low and high pressure heaters, deaerator, feedwater pumps, and control valves. This complicated flow network is modeled and coupled to DSNP and it is tested for several normal and abnormal transient conditions such turbine load maneuvering, turbine trip, and loss of class IV power. The results show reasonable behavior of the coupled code and also gives a good dynamic and interactive simulation capabilities for the several mild transient conditions. It has been found that coupling system thermal hydraulic code with a flow network code is a proper way of upgrading simulation capability of DSNP to mature nuclear plant analyzer (NPA). 5 refs., 10 figs. (Author)

  1. Nuclear power plant

    International Nuclear Information System (INIS)

    Aisaka, Tatsuyoshi; Kamahara, Hisato; Yanagisawa, Ko.

    1982-01-01

    Purpose: To prevent corrosion stress cracks in structural materials in a BWR type nuclear power plant by decreasing the oxygen concentration in the reactor coolants. Constitution: A hydrogen injector is connected between the condensator and a condensate clean up system of a nuclear power plant. The injector is incorporated with hydrogenated compounds formed from metal hydrides, for example, of alloys such as lanthanum-nickel alloy, iron titanium alloy, vanadium, palladium, magnesium-copper alloy, magnesium-nickel alloy and the like. Even if the pressure of hydrogen obtained from a hydrogen bomb or by way of water electrolysis is changed, the hydrogen can always be injected into a reactor coolant at a pressure equal to the equilibrium dissociation pressure for metal hydride by introducing the hydrogen into the hydrogen injector. (Seki, T.)

  2. Third generation nuclear plants

    Science.gov (United States)

    Barré, Bertrand

    2012-05-01

    After the Chernobyl accident, a new generation of Light Water Reactors has been designed and is being built. Third generation nuclear plants are equipped with dedicated systems to insure that if the worst accident were to occur, i.e. total core meltdown, no matter how low the probability of such occurrence, radioactive releases in the environment would be minimal. This article describes the EPR, representative of this "Generation III" and a few of its competitors on the world market.

  3. Nuclear power plant

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1976-01-01

    The invention concerns a quick-acting valve on the main-steam pipe of a nuclear power plant. The engineering design of the valve is to be improved. To the main valve disc, a piston-operated auxiliary valve disc is to be assigned closing a section of the area of the main valve disc. This way it is avoided that the drive of the main valve disc has to carry out different movements. 15 sub-claims. (UWI) [de

  4. Possible uses and applications of drones in a nuclear power plant; Posibles usos y aplicaciones de los drones en una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Celis del A, L.; Palacios, J.; Rivero, T.; Valero, D., E-mail: lina.celis@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    The versatility of drones is one of the strengths that have led to the rapid development of this technology, as they adapt relatively easily to new applications, presenting considerable advantages such as greater energy efficiency, longer life and a significant lower operation cost than manned systems. The current applications of the drones, in addition to the military, are very wide and varied. The nuclear industry represents an important area of opportunity for drones, mainly in response to radiological emergencies, since in this case there is a latent risk of the general population being exposed to high radiation doses. Drones can be used in environments with high chemical and radiological toxicity without endangering human lives. Some of the possible applications of the drones in a nuclear power plant are: perimeter surveillance in physical security, where equipped with a high definition camera can be used as support to physical security systems in general; visual inspection at sites, structures, equipment and pipelines, etc., as part of preventive maintenance in order to avoid the loss of material due to corrosion, oxidation, cracking, subsidence; the visual inspection through thermo-graphic images to be able to detect hot spots in some critical element; measurement and radiological mapping on surfaces to maintain monitoring of radiological safety at nuclear power plant facilities; the monitoring of environmental parameters and the Environmental Impact Assessment to obtain important information to determine the environmental impact of a given area; and accident support by providing information that allows staff to size the magnitude of the damage. (Author)

  5. Psychological scaling of expert estimates of human error probabilities: application to nuclear power plant operation

    International Nuclear Information System (INIS)

    Comer, K.; Gaddy, C.D.; Seaver, D.A.; Stillwell, W.G.

    1985-01-01

    The US Nuclear Regulatory Commission and Sandia National Laboratories sponsored a project to evaluate psychological scaling techniques for use in generating estimates of human error probabilities. The project evaluated two techniques: direct numerical estimation and paired comparisons. Expert estimates were found to be consistent across and within judges. Convergent validity was good, in comparison to estimates in a handbook of human reliability. Predictive validity could not be established because of the lack of actual relative frequencies of error (which will be a difficulty inherent in validation of any procedure used to estimate HEPs). Application of expert estimates in probabilistic risk assessment and in human factors is discussed

  6. Surveillance system for nuclear power plants

    International Nuclear Information System (INIS)

    Mizeracki, M.T.

    1981-01-01

    This paper describes an integrated surveillance system for nuclear power plant application. The author explores an expanded role for closed circuit television, with remotely located cameras and infrared scanners as the basic elements. The video system, integrated with voice communication, can enhance the safe and efficient operation of the plant, by improving the operator's knowledge of plant conditions. 7 refs

  7. Expertise of the Oeko-Institute on the application to obtain permission to partially dismantle the Niederaichbach nuclear power plant

    International Nuclear Information System (INIS)

    1985-01-01

    This expertise gives an overview on the problems associated with the decommissioning and dismantling of the Niederaichbach nuclear power plant, considering technical and legal aspects. It wants to prove that the dismantling of this reactor cannot serve as evidence to prove the general feasibility of reactor dismantling. Much space is dedicated to the discussion about where the borderline should be drawn between radioactive and non-radioactive materials according to the ordinance on radiation protection. The reasons for rejecting the partial dismantling application are given. (DG) [de

  8. Application of the failure modes and effects analysis technique to theemergency cooling system of an experimental nuclear power plant

    International Nuclear Information System (INIS)

    Conceicao Junior, Osmar

    2009-01-01

    This study consists on the application of the Failure Modes and EffectsAnalysis (FMEA), a hazard identification and a risk assessment technique, tothe Emergency Cooling System (ECS) of an experimental nuclear power plant,which is responsible for mitigating the consequences of an eventual loss ofcoolant accident on the Pressurized Water Reactor (PWR). Such analysisintends to identify possible weaknesses on the design of the system andpropose some improvements in order to maximize its reliability. To achievethis goal a detailed study of the system was carried on (through itstechnical documentation), the correspondent reliability block diagram wasobtained, the FMEA analysis was executed and, finally, some suggestions werepresented. (author)

  9. Application of aluminium in nuclear power plants; the role of corrosion under breakdown conditions within the hermetic zone

    International Nuclear Information System (INIS)

    Szontagh, Endre; Eva, Andras; Koevari, Tiborne

    1987-01-01

    Basic corrosion processes of aluminium determining the application possibilities as construction material within the containment of nuclear power plants were studied. The structure and stability of the oxide layers formed on aluminium surfaces depend on the pH, the temperature and the composition of the media and on the presence of alloying elements in the metal. It could be stated that hydrogen evolution due to the corrosion interaction of aluminium with the coolant of WWER-type reactors was less significant than calculated values. (V.N.)

  10. Artificial Intelligence application to surveillance and diagnosis of nuclear power plants

    International Nuclear Information System (INIS)

    Brunet, E.; Monnier, B.; Zwingelstein, G.

    1986-01-01

    Acquisition and representation of knowledge are fundamental problems in Aritificial Intellegence and especially in expert system domain. In this article, the authors propose a conceptual model allowing to describe the universe the expert is working on when trying to make a diagnosis. The expert determines the descriptors and predicates with which he describes laws, states, objects involved in his reasoning. With this model, they are presenting design and development of Knowledge Acquisition Module allowing a dialogue in a specialized natural language used by the expert system to assist in the detection of loose parts in nuclear power plants. Using a classical lexical and syntactic analysis, they propose to associate grammatical semantic properties to the specialized language words. The method used allows the design of a sub expert system for understanding of the specialized natural language

  11. An industrial application virtual reality. An aid for designing maintenance in nuclear plants

    International Nuclear Information System (INIS)

    Fertey, G.; Thibault, G.; Delpy, T.; Lapierre, M.

    1995-09-01

    This paper shows a use of virtual reality in the industrial context of nuclear plant maintenance. The objective is to build a realistic simulation fool by means of virtual reality techniques. With such a tool, the designer of a maintenance operation can validate tools and sequencing of operations, reduce the time of intervention and minimize the radiation doses received by the operator on site. Several major functionalities have been studied: a navigation in 3D geometries faithfully reproducing terrain, geometries obtained by 3D digitization of installations; an optimized navigation to the intervention sites with both management of obstacles present along the way and room walls and guiding of navigator from one room to another by means of visual indicators (arrows) which he can capture and which virtually carry him; a programming of the environment in keeping with and translating faithfully the breakdown and sequencing of intervention operations; real time information on the surrounding radiation. (author)

  12. A probabilistic seismic risk assessment procedure for nuclear power plants: (II) Application

    Science.gov (United States)

    Huang, Y.-N.; Whittaker, A.S.; Luco, N.

    2011-01-01

    This paper presents the procedures and results of intensity- and time-based seismic risk assessments of a sample nuclear power plant (NPP) to demonstrate the risk-assessment methodology proposed in its companion paper. The intensity-based assessments include three sets of sensitivity studies to identify the impact of the following factors on the seismic vulnerability of the sample NPP, namely: (1) the description of fragility curves for primary and secondary components of NPPs, (2) the number of simulations of NPP response required for risk assessment, and (3) the correlation in responses between NPP components. The time-based assessment is performed as a series of intensity-based assessments. The studies illustrate the utility of the response-based fragility curves and the inclusion of the correlation in the responses of NPP components directly in the risk computation. ?? 2011 Published by Elsevier B.V.

  13. Practical applications of probabilistic structural reliability analyses to primary pressure systems of nuclear power plants

    International Nuclear Information System (INIS)

    Witt, F.J.

    1980-01-01

    Primary pressure systems of nuclear power plants are built to exacting codes and standards with provisions for inservice inspection and repair if necessary. Analyses and experiments have demonstrated by deterministic means that very large margins exist on safety impacting failures under normal operating and upset conditions. Probabilistic structural reliability analyses provide additional support that failures of significance are very, very remote. They may range in degree of sophistication from very simple calculations to very complex computer analyses involving highly developed mathematical techniques. The end result however should be consistent with the desired usage. In this paper a probabilistic structural reliability analysis is performed as a supplement to in-depth deterministic evaluations with the primary objective to demonstrate an acceptably low probability of failure for the conditions considered. (author)

  14. Application of a two-phase injector in the safety systems of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Popov, E; Stanev, I [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    A concept for simplification of the active part of the safety system (ASS) of nuclear power plants is presented. A two-phase injection jet device (IJD) is proposed to substitute the currently used IP-EM (impeller pumps -electric motors) couple. It is capable of sustaining a constant flow rate regardless of the variation in the system hydraulic resistance. The conditions for effective work of IJD are: development of the necessary head and flow rate, reliable supply of working medium and maintaining of the temperature of the injected water. IJD efficiency, steam and water flow rates have been calculated and compared with experimentally measured values. A short analysis of different typical accident regimes is carried out. It shows that IJD introduction brings significant advantages especially in the steam generator emergency feedwater system making it completely insensitive to loss of electricity supply accidents. 8 refs., 7 figs.

  15. Application of a two-phase injector in the safety systems of nuclear power plants

    International Nuclear Information System (INIS)

    Popov, E.; Stanev, I.

    1995-01-01

    A concept for simplification of the active part of the safety system (ASS) of nuclear power plants is presented. A two-phase injection jet device (IJD) is proposed to substitute the currently used IP-EM (impeller pumps -electric motors) couple. It is capable of sustaining a constant flow rate regardless of the variation in the system hydraulic resistance. The conditions for effective work of IJD are: development of the necessary head and flow rate, reliable supply of working medium and maintaining of the temperature of the injected water. IJD efficiency, steam and water flow rates have been calculated and compared with experimentally measured values. A short analysis of different typical accident regimes is carried out. It shows that IJD introduction brings significant advantages especially in the steam generator emergency feedwater system making it completely insensitive to loss of electricity supply accidents. 8 refs., 7 figs

  16. Application of thermal comfort theory in probabilistic safety assessment of a nuclear power plant

    International Nuclear Information System (INIS)

    Zhou Tao; Sun Canhui; Li Zhenyang; Wang Zenghui

    2011-01-01

    Human factor errors in probabilistic safety assessment (PSA) of a nuclear power plant (NPP) can be prevented using thermal comfort analysis. In this paper, the THERP + HCR model is modified by using PMV (Predicted Mean Vote) and PPD (Predicted Percentage Dissatisfied) index system, so as to obtain the operator cognitive reliability,and to reflect and analyze human perception, thermal comfort status,and cognitive ability in a specific NPP environment. The mechanism of human factors in the PSA is analyzed by operators of skill, rule and knowledge types. The THERP + HCR model modified by thermal comfort theory can reflect the conditions in actual environment, and optimize reliability analysis of human factors. Improving human thermal comfort for different types of operators reduces adverse factors due to human errors, and provides a safe and optimum decision-making for NPPs. (authors)

  17. Application of neural networks to signal prediction in nuclear power plant

    International Nuclear Information System (INIS)

    Wan Joo Kim; Soon Heung Chang; Byung Ho Lee

    1993-01-01

    This paper describes the feasibility study of an artificial neural network for signal prediction. The purpose of signal prediction is to estimate the value of undetected next time step signal. As the prediction method, based on the idea of auto regression, a few previous signals are inputs to the artificial neural network and the signal value of next time step is estimated with the outputs of the network. The artificial neural network can be applied to the nonlinear system and answers in short time. The training algorithm is a modified backpropagation model, which can effectively reduce the training time. The target signal of the simulation is the steam generator water level, which is one of the important parameters in nuclear power plants. The simulation result shows that the predicted value follows the real trend well

  18. Optimization of reload core design for PWR and application to Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shen Wei; Zhongsheng Xie; Banghua Yin

    1995-01-01

    A direct efficient optimization technique has been effected for automatically optimizing the reload of PWR. The objective functions include: maximization of end-of-cycle (EOC) reactivity and maximization of average discharge burnup. The fuel loading optimization and burnable poison (BP) optimization are separated into two stages by using Haling principle. In the first stage, the optimum fuel reloading pattern without BP is determined by the Linear Programming method using enrichments as control variable. In the second stage the optimum BP allocation is determined by the Flexible Tolerance Method using the number of BP rods as control variable. A practical and efficient PWR reloading optimization program based on above theory has been encoded and successfully applied to Qinshan Nuclear Power Plant(QNP)cycle 2 reloading design

  19. Application of probabilistic risk assessment to nuclear fuel reprocessing at the Savannah River Plant

    International Nuclear Information System (INIS)

    Durant, W.S.

    1980-01-01

    The Savannah River Laboratory has developed an integrated risk assessment methodology that has been applied to systems in the nuclear fuel reprocessing facilities at the Savannah River Plant. The methodology can be applied to several types of design and operational problems. Basically, the analysis is subdivided into individual modules that can be either utilized separately or integrated into an overall risk analysis. Computer codes and computer data banks are utilized extensively to minimize the manual effort. The flow of information begins with a definition of the system to be analyzed followed by an evaluation of sources of fault information, storage of this information in data banks, design analysis and data treatment, risk calculations, and end product options

  20. Application of extended statistical combination of uncertainties methodology for digital nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    In, Wang Ki; Uh, Keun Sun; Chul, Kim Heui [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    A technically more direct statistical combinations of uncertainties methodology, extended SCU (XSCU), was applied to statistically combine the uncertainties associated with the DNBR alarm setpoint and the DNBR trip setpoint of digital nuclear power plants. The modified SCU (MSCU) methodology is currently used as the USNRC approved design methodology to perform the same function. In this report, the MSCU and XSCU methodologies were compared in terms of the total uncertainties and the net margins to the DNBR alarm and trip setpoints. The MSCU methodology resulted in the small total penalties due to a significantly negative bias which are quite large. However the XSCU methodology gave the virtually unbiased total uncertainties. The net margins to the DNBR alarm and trip setpoints by the MSCU methodology agree with those by the XSCU methodology within statistical variations. (Author) 12 refs., 17 figs., 5 tabs.

  1. Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The Technical Committee Meeting on Procedures for Use of PSA for Optimizing Operational Limits and Conditions for Nuclear Power Plants was held in Barcelona from 20 to 23 September 1993 to serve as a forum for discussion of the development of methods and approaches for PSA applications. The meeting was co-sponsored by the IAEA and the Asco and Vandellos nuclear power plants in Spain and was attended by more than 85 participants from 23 countries. The 35 papers and presentations reflected the extent of activities in this area worldwide. Most of the papers discuss PSA application programmes and/or specific methods and approaches used. This TECDOC, which was prepared by the participants of the Technical Committee meeting, summarizes the insights gained from the papers and plenary discussions. It also presents the conclusions of the work of three working groups which discussed the advantages and limitations of specific aspects of PSA. It provides an up-to-date description of computerized tools for risk monitoring in used or under development in Member States. It is hoped that this report will be a useful source of information on PSA applications. Refs, figs, tabs.

  2. Application of neural networks to validation of feedwater flow rate in a nuclear power plant

    International Nuclear Information System (INIS)

    Khadem, M.; Ipakchi, A.; Alexandro, F.J.; Colley, R.W.

    1993-01-01

    Feedwater flow rate measurement in nuclear power plants requires periodic calibration. This is due to the fact that the venturi surface condition of the feedwater flow rate sensor changes because of a chemical reaction between the surface coating material and the feedwater. Fouling of the venturi surface, due to this chemical reaction and the deposits of foreign materials, has been observed shortly after a clean venturi is put in operation. A fouled venturi causes an incorrect measurement of feedwater flow rate, which in turn results in an inaccurate calculation of the generated power. This paper presents two methods for verifying incipient and continuing fouling of the venturi of the feedwater flow rate sensors. Both methods are based on the use of a set of dissimilar process variables dynamically related to the feedwater flow rate variable. The first method uses a neural network to generate estimates of the feedwater flow rate readings. Agreement, within a given tolerance, of the feedwater flow rate instrument reading, and the corresponding neural network output establishes that the feedwater flow rate instrument is operating properly. The second method is similar to the first method except that the neural network predicts the core power which is calculated from measurements on the primary loop, rather than the feedwater flow rates. This core power is referred to the primary core power in this paper. A comparison of the power calculated from the feedwater flow measurements in the secondary loop, with the calculated and neural network predicted primary core power provides information from which it can be determined whether fouling is beginning to occur. The two methods were tested using data from the feedwater flow meters in the two feedwater flow loops of the TMI-1 nuclear power plant

  3. Application of perturbation methods for sensitivity analysis for nuclear power plant steam generators

    International Nuclear Information System (INIS)

    Gurjao, Emir Candeia

    1996-02-01

    The differential and GPT (Generalized Perturbation Theory) formalisms of the Perturbation Theory were applied in this work to a simplified U-tubes steam generator model to perform sensitivity analysis. The adjoint and importance equations, with the corresponding expressions for the sensitivity coefficients, were derived for this steam generator model. The system was numerically was numerically solved in a Fortran program, called GEVADJ, in order to calculate the sensitivity coefficients. A transient loss of forced primary coolant in the nuclear power plant Angra-1 was used as example case. The average and final values of functionals: secondary pressure and enthalpy were studied in relation to changes in the secondary feedwater flow, enthalpy and total volume in secondary circuit. Absolute variations in the above functionals were calculated using the perturbative methods, considering the variations in the feedwater flow and total secondary volume. Comparison with the same variations obtained via direct model showed in general good agreement, demonstrating the potentiality of perturbative methods for sensitivity analysis of nuclear systems. (author)

  4. Applications of Nuclear Physics

    OpenAIRE

    Hayes, Anna C.

    2017-01-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that und...

  5. On nuclear power plant uprating

    International Nuclear Information System (INIS)

    Ho, S. Allen; Bailey, James V.; Maginnis, Stephen T.

    2004-01-01

    Power uprating for commercial nuclear power plants has become increasingly attractive because of pragmatic reasons. It provides quick return on investment and competitive financial benefits, while involving low risks regarding plant safety and public objection. This paper briefly discussed nuclear plant uprating guidelines, scope for design basis analysis and engineering evaluation, and presented the Salem nuclear power plant uprating study for illustration purposes. A cost and benefit evaluation of the Salem power uprating was also included. (author)

  6. Accelerating learning of neural networks with conjugate gradients for nuclear power plant applications

    International Nuclear Information System (INIS)

    Reifman, J.; Vitela, J.E.

    1994-01-01

    The method of conjugate gradients is used to expedite the learning process of feedforward multilayer artificial neural networks and to systematically update both the learning parameter and the momentum parameter at each training cycle. The mechanism for the occurrence of premature saturation of the network nodes observed with the back propagation algorithm is described, suggestions are made to eliminate this undesirable phenomenon, and the reason by which this phenomenon is precluded in the method of conjugate gradients is presented. The proposed method is compared with the standard back propagation algorithm in the training of neural networks to classify transient events in neural power plants simulated by the Midland Nuclear Power Plant Unit 2 simulator. The comparison results indicate that the rate of convergence of the proposed method is much greater than the standard back propagation, that it reduces both the number of training cycles and the CPU time, and that it is less sensitive to the choice of initial weights. The advantages of the method are more noticeable and important for problems where the network architecture consists of a large number of nodes, the training database is large, and a tight convergence criterion is desired

  7. Evaluation of applicability of alternative source terms to operating nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Lim, S. N.; Park, Y. S.; Nam, K. M.; Song, D. B.; Bae, Y. J.; Lee, Y. J.; Jung, C. Y.

    2002-01-01

    In 1995 and 2000, NRC issued NUREG-1465 and Regulatory Guide 1.183 with respect to Alternative Source Terms(AST) replacing the existing source terms of TID-14844 and Regulatory Guide 1.4, 1.25, and 1.77 for radiological Design Basis Accidents(DBA) analysis. In 1990, ICRP published ICRP Pub. 60 which represents new recommendations on dose criteria and concepts. In Korea, alternative source terms were used for evaluation of effective doses for design basis accidents of Advanced Power Reactor(APR1400) using the computer program developed by an overseas company. Recently, DBADOSE, new computer program for DBA analysis incorporating AST and effective dose concept was developed by KHNP and KOPEC, and reanalysis applying AST to operating nuclear power plants, Kori units 3 and 4 in Korea using DBADOSE has been performed. As the results of this analysis, it was concluded that some conservative variables or operation procedures of operating plants could be mitigated or simplified by virtue of increased safety margin and consequently, economical and operational benefits ensue. In this paper, methodologies and results of Kori 3 and 4 DBA reanalysis and sensitivity analysis for mitigation of main design variables are introduced

  8. Application of the SSMRP methodology to the seismic risk at the Zion Nuclear Power Plant

    International Nuclear Information System (INIS)

    Bohn, M.P.; Shieh, L.C.; Wells, J.E.

    1983-11-01

    The Seismic Safety Margins Research Program (SSMRP) has the goal of developing a fully coupled analysis procedure for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. The risk analysis included a detailed seismological evaluation of the region around Zion, Illinois, which provided the earthquake-hazard function and a randomized set of 180 time histories (having peak ground acceleration values up to 1.8 g). These time histories were used as input for dynamic structural response calculations for four different Zion buildings. Detailed finite-element models of the buildings were used. Calculated time histories at piping support points were then used to determine moments throughout critical piping systems. Twenty separate piping models were analyzed. Finally, the responses of piping and safety system components within the buildings were combined with probabilistic failure criteria and event-tree/fault-tree models of the plant safety systems to produce an estimate of the frequency of core melt and radioactive release due to earthquakes

  9. Expert robots in nuclear plants

    International Nuclear Information System (INIS)

    Byrd, J.S.; Fisher, J.J.; DeVries, K.R.; Martin, T.P.

    1987-01-01

    Expert robots enhance a safety and operations in nuclear plants. E.I. du Pont de Nemours and Company, Savannah River Laboratory, is developing expert mobile robots for deployment in nuclear applications at the Savannah River Plant. Knowledge-based expert systems are being evaluated to simplify operator control, to assist in navigation and manipulation functions, and to analyze sensory information. Development work using two research vehicles is underway to demonstrate semiautonomous, intelligence, expert robot system operation in process areas. A description of the mechanical equipment, control systems, and operating modes is presented, including the integration of onboard sensors. A control hierarchy that uses modest computational methods is being used to allow mobile robots to autonomously navigate and perform tasks in known environments without the need for large computer systems

  10. Expert robots in nuclear plants

    International Nuclear Information System (INIS)

    Byrd, J.S.; Fisher, J.J.; DeVries, K.R.; Martin, T.P.

    1987-01-01

    Expert robots will enhance safety and operations in nuclear plants. E. I. du Pont de Nemours and Company, Savannah River Laboratory, is developing expert mobile robots for deployment in nuclear applications at the Savannah River Plant. Knowledge-based expert systems are being evaluated to simplify operator control, to assist in navigation and manipulation functions, and to analyze sensory information. Development work using two research vehicles is underway to demonstrate semiautonomous, intelligent, expert robot system operation in process areas. A description of the mechanical equipment, control systems, and operating modes is presented, including the integration of onboard sensors. A control hierarchy that uses modest computational methods is being used to allow mobile robots to autonomously navigate and perform tasks in known environments without the need for large computer systems

  11. Nuclear Power Plant 1996

    International Nuclear Information System (INIS)

    1997-01-01

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

  12. Material property requirements for application leak-before-break technology on nuclear power plant high-energy piping

    International Nuclear Information System (INIS)

    Li Chengliang; Deng Xiaoyun; Yin Zhiying; Liu Meng

    2012-01-01

    The application of leak-before-break (LBB) technology on nuclear power plant high-energy piping systems can improve their safety and economy, while propose some new requirements on testing material properties. The U.S. Nuclear Regulatory Commission's LBB related standard review plan and implementation specifications were analyzed, and test items, object, temperature, quantity and thermal aging effect of five general requirements were summarized. In addition, four key testing technical requirements, such as specimen size, side grooves, strain range and the orientation of specimens were also discussed to ensure the test data usefulness, representativeness and integrity. This study can provide some guidance for the aforementioned test program on domestic materials. (authors)

  13. Siting nuclear power plants

    International Nuclear Information System (INIS)

    Yellin, J.; Joskow, P.L.

    1980-01-01

    The first edition of this journal is devoted to the policies and problems of siting nuclear power plants and the question of how far commercial reactors should be placed from urban areas. The article is divided into four major siting issues: policies, risk evaluation, accident consequences, and economic and physical constraints. One concern is how to treat currently operating reactors and those under construction that were established under less-stringent criteria if siting is to be used as a way to limit the consequences of accidents. Mehanical cost-benefit analyses are not as appropriate as the systematic use of empirical observations in assessing the values involved. Stricter siting rules are justified because (1) opposition because of safety is growing: (2) remote siting will make the industry more stable; (3) the conflict is eliminated between regulatory policies and the probability basis for nuclear insurance; and (4) joint ownership of utilities and power-pooling are increasing. 227 references, 7 tables

  14. Nuclear power plant disasters

    International Nuclear Information System (INIS)

    Trott, K.R.

    1979-01-01

    The possibility of a nuclear power plant disaster is small but not excluded: in its event, assistance to the affected population mainly depends on local practitioners. Already existing diseases have to be diagnosed and treated; moreover, these physicians are responsible for the early detection of those individuals exposed to radiation doses high enough to induce acute illness. Here we present the pathogenesis, clinical development and possible diagnostic and therapeutical problems related to acute radiation-induced diseases. The differentiation of persons according to therapy need and prognosis is done on the sole base of the clinical evidence and the peripheral blood count. (orig.) [de

  15. Nuclear reactor plant

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1977-01-01

    The invention is concerned with a quick-closing valve on the main-steam pipe of a nuclear reactor plant. The quick-closing valve serves as isolating valve and as safety valve permitting depressurization in case of an accident. For normal operation a tube-shaped gate valve is provided as valve disc, enclosing an auxiliary valve disc to be used in case of accidents and which is opened at increased pressure to provide a smaller flow cross-section. The design features are described in detail. (RW) [de

  16. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  17. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

    1976-03-01

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

  18. Application of Safety Instrumented System (SIS) approach in older nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Nasimi, Elnara; Gabbar, Hossam A., E-mail: hossam.gabbar@uoit.ca

    2016-05-15

    Highlights: • Study Safety Instrumented System (SIS) design for older nuclear power plant. • Apply SIS on Reheater Drains (RD) system. • Apply IEC 61508/61511 to design safety system. • Evaluate risk reduction based on proposed SIS design. - Abstract: In order to remain economically effective and financially profitable, the modern industries have to take their safety culture to a higher level and consider production losses in addition to simple accident prevention techniques. Ideally, compliance with safety requirements start during early design stages, but in some older facilities provisions for Safety Instrumented Systems (SIS) may not have been originally included. In this paper, a case study of a Reheater Drains (RD) system is used to illustrate such an example. Frequent failures of tank level controller lead to transients where the operation of shutting down RD pumps requires operators to manually isolate the quenching water and to close the main steam admission valves. Water in this system is at saturation temperature for the reheater steam side pressure, and any manual operation of the system is highly undesirable due to hazards of working with wet steam at approximately 758 kPa(g) pressure, preheated to 237 °C. Additionally, losses of inventory are highly undesirable as well and challenge other systems in the plant. In this paper, it is suggested that RD system can benefit from installation of an independent SIS system in order to address current challenges. This idea is being explored using IEC 61508 framework for “Functional safety of electrical/electronic/programmable electronic safety-related systems” to provide assurance that the SIS will offer the necessary risk reduction required to achieve required safety for the equipment.

  19. Application of monitoring, diagnosis, and prognosis in thermal performance analysis for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyeong Min; Heo, Gyun Young [Kyung Hee University, Yongin (Korea, Republic of); Na, Man Gyun [Chosun University, Gwangju (Korea, Republic of)

    2014-12-15

    As condition-based maintenance (CBM) has risen as a new trend, there has been an active movement to apply information technology for effective implementation of CBM in power plants. This motivation is widespread in operations and maintenance, including monitoring, diagnosis, prognosis, and decision-making on asset management. Thermal efficiency analysis in nuclear power plants (NPPs) is a longstanding concern being updated with new methodologies in an advanced IT environment. It is also a prominent way to differentiate competitiveness in terms of operations and maintenance costs. Although thermal performance tests implemented using industrial codes and standards can provide officially trustworthy results, they are essentially resource-consuming and maybe even a hind-sighted technique rather than a foresighted one, considering their periodicity. Therefore, if more accurate performance monitoring can be achieved using advanced data analysis techniques, we can expect more optimized operations and maintenance. This paper proposes a framework and describes associated methodologies for in-situ thermal performance analysis, which differs from conventional performance monitoring. The methodologies are effective for monitoring, diagnosis, and prognosis in pursuit of CBM. Our enabling techniques cover the intelligent removal of random and systematic errors, deviation detection between a best condition and a currently measured condition, degradation diagnosis using a structured knowledge base, and prognosis for decision-making about maintenance tasks. We also discuss how our new methods can be incorporated with existing performance tests. We provide guidance and directions for developers and end-users interested in in-situ thermal performance management, particularly in NPPs with large steam turbines.

  20. Application of monitoring, diagnosis, and prognosis in thermal performance analysis for nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Hyeong Min; Heo, Gyun Young; Na, Man Gyun

    2014-01-01

    As condition-based maintenance (CBM) has risen as a new trend, there has been an active movement to apply information technology for effective implementation of CBM in power plants. This motivation is widespread in operations and maintenance, including monitoring, diagnosis, prognosis, and decision-making on asset management. Thermal efficiency analysis in nuclear power plants (NPPs) is a longstanding concern being updated with new methodologies in an advanced IT environment. It is also a prominent way to differentiate competitiveness in terms of operations and maintenance costs. Although thermal performance tests implemented using industrial codes and standards can provide officially trustworthy results, they are essentially resource-consuming and maybe even a hind-sighted technique rather than a foresighted one, considering their periodicity. Therefore, if more accurate performance monitoring can be achieved using advanced data analysis techniques, we can expect more optimized operations and maintenance. This paper proposes a framework and describes associated methodologies for in-situ thermal performance analysis, which differs from conventional performance monitoring. The methodologies are effective for monitoring, diagnosis, and prognosis in pursuit of CBM. Our enabling techniques cover the intelligent removal of random and systematic errors, deviation detection between a best condition and a currently measured condition, degradation diagnosis using a structured knowledge base, and prognosis for decision-making about maintenance tasks. We also discuss how our new methods can be incorporated with existing performance tests. We provide guidance and directions for developers and end-users interested in in-situ thermal performance management, particularly in NPPs with large steam turbines.

  1. Applications of nuclear physics

    Science.gov (United States)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  2. Applications of nuclear physics

    International Nuclear Information System (INIS)

    Hayes-Sterbenz, Anna Catherine

    2017-01-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  3. Nuclear power plant emergency preparedness

    International Nuclear Information System (INIS)

    2005-01-01

    The guide sets forth detailed requirements on how the licensee of a nuclear power plant shall plan, implement and maintain emergency response arrangements. The guide is also applied to nuclear material and nuclear waste transport in situations referred to in guide YVL 6.5. Requirements on physical protection are presented in a separate guide of Finnish Radiation and Nuclear Safety Authority (STUK)

  4. Sabotage at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Purvis, James W.

    1999-07-21

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

  5. Sabotage at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Purvis, James W.

    1999-01-01

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

  6. Artificial intelligence application to diagnosis and supervision of nuclear power plants

    International Nuclear Information System (INIS)

    Corvalan, P.J.

    1991-06-01

    A diagnostic expert system was developed, in the Process Control Division at the Centro Atomico Bariloche, for the Embalse nuclear power plant simulator. The diagnostic system task is to interpret and show the probable cause of an abnormal transitory behaviour in the simulated process. The system was developed using artificial intelligence techniques such as: knowledge representation using rules, heuristic programming, inference under uncertainty and fuzzy sets. The diagnostic technique used consists of finding the possible cause of failure using the fault hypothesis confirmation. The faults hypothesis are organized in hierarchical form into a tree structure. The Best First search strategy is used to direct the search to those hypothesis which are confirmed with a higher degree of certainty. The diagnostic is finished when a specific hypothesis is confirmed with a high certainty factor. The diagnostic result obtained by different process fault simulation is shown. An alternative diagnostic technique is presented where the knowlegde of process structure and behaviour are represented in the form of mathematical constraints. This diagnostic method detects a suspicious component through constraints satisfaction and localizes it through constraints suspension. The validity of the method is shown by an easy example. (Author) [es

  7. A technology-assessment methodology for electric utility planning: With application to nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Lough, W.T.

    1987-01-01

    Electric utilities and public service commissions have not taken full advantage of the many proven methodologies and techniques available for evaluating complex technological issues. In addition, evaluations performed are deficient in their use of (1) methods for evaluating public attitudes and (2) formal methods of analysis for decision making. These oversight are substantiated through an examination of the literature relevant to electric utility planning. The assessment process known as technology assessment or TA is proposed, and a TA model is developed for route in use in utility planning by electric utilities and state regulatory commissions. Techniques to facilitate public participation and techniques to aid decision making are integral to the proposed model and are described in detail. Criteria are provided for selecting an appropriate technique on a case-by-case basis. The TA model proved to be an effective methodology for evaluating technological issues associated with electric utility planning such as decommissioning nuclear power plants. Through the use of the nominal group technique, the attitudes of a group of residential ratepayers were successfully identified and included in the decision-making process

  8. Application of analytical redundancy methods for early fault detection in nuclear power plant. Final report

    International Nuclear Information System (INIS)

    Seliger, R.

    1993-01-01

    The project activities proceeded along the following lines: Determination of the class of non-linear models to serve as a basis for the development of the residue generators. The models are to describe both the nominal and the faulty dynamic processes as precise and well-structured as possible. An aspect of particular importance was to explicitly simulate also modelling defects, such as parameter uncertainties, in order to be able to generate appropriate robustness against such effects. The class of models had to cover nonlinear space of states models for U-tube steam generators, as the algorithms developed were to be applied to this typical example of steam generators in nuclear power plant. Derivation and implementation of a mathematical model for a U-tube steam generator as required. This model was to serve as a basis for the residue generators. Verification of the mathematical decoupling conditions for the model. Implementation of a reference model on the digital computer. This reference model is not to be confused with the mathematical model for the design of the residue generators. The reference model is exclusively for the generation of test data, i.e. for generating transients and defects for testing the performance of the residue generators [de

  9. Application of 4-Face Fuel Visual Inspection System during Outage in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shin, J. C.; Kim, J. I.; Choi, C. B.; Kim, Y. C.; Kang, C. B.

    2008-01-01

    Recently, as a measure to reduce an outage duration in nuclear power plants (NPPs), a four-face fuel visual inspection system (4-FFVIS) built in 4 cameras was introduced by Ahlberg Electronics, Sweden. The 4- FFVIS is used to inspect the external appearance of irradiated fuel assemblies in order to confirm their integrity against mechanical defects and foreign materials. Until now, however, a typical one-face fuel inspection system(1-FFVIS) has been world-widely utilized in NPPs. The 1-FFVIS requires four turns with 90 degree to inspect every face of the fuel assembly, causing a relatively long inspecting time. But the 4- FFVIS allow us to inspect every face of the fuel assembly at the same time. The inspection time with the 4-FFVIS may be less than two minutes per fuel assembly, whereas that with the 1-FFVIS is about six minutes per fuel assembly. In viewpoint of this merit, the 4-FFVIS is expected to be world-widely used in the near future. In this paper, the technical requirements necessary to develop the 4-FFVIS as well as some improvements to complement the current 4-FFVIS are described

  10. Design and development of innovative passive valves for Nuclear Power Plant applications

    Energy Technology Data Exchange (ETDEWEB)

    Sapra, M.K., E-mail: sapramk@barc.gov.in; Kundu, S.; Pal, A.K.; Vijayan, P.K.; Vaze, K.K.; Sinha, R.K.

    2015-05-15

    Highlights: • Passive valves are self-acting valves requiring no external energy to function. • These valves have been developed for Advanced Heavy Water Reactor (AHWR) of India. • Passive valves are core components of passive safety systems of the reactor. • Accumulator Isolation Passive Valve (AIPV) has been developed and tested for ECSS. • AIPV provided passive isolation and flow regulation in ECCS of Integral Test Loop. - Abstract: The recent Fukushima accident has resulted in an increased need for passive safety systems in upcoming advanced reactors. In order to enhance the global contribution and acceptability of nuclear energy, proven evidence is required to show that it is not only green but also safe, in case of extreme natural events. To achieve and establish this fact, we need to design, demonstrate and incorporate reliable ‘passive safety systems’ in our advanced reactor designs. In Nuclear Power Plants (NPPs), the use of passive safety systems such as accumulators, condensing and evaporative heat exchangers and gravity driven cooling systems provide enhanced safety and reliability. In addition, they eliminate the huge costs associated with the installation, maintenance and operation of active safety systems that require multiple pumps with independent and redundant electric power supplies. As a result, passive safety systems are preferred for numerous advanced reactor concepts. In current NPPs, passive safety systems which are not participating in day to day operation, are kept isolated, and require a signal and external energy source to open the valve. It is proposed to replace these valves by passive components and devices such as self-acting valves, rupture disks, etc. Some of these innovative passive valves, which do not require external power, have been recently designed, developed and tested at rated conditions. These valves are proposed to be used for various passive safety systems of an upcoming Nuclear Power Plant being designed

  11. On line surveillance of large systems: applications to nuclear and chemical plant

    International Nuclear Information System (INIS)

    Zwingelstein, G.

    1978-01-01

    An on line surveillance method for large scale and distributed parameter systems is achieved by comparing in real time the internal physical parameter values to the reference values. It is shown that the following steps are necessary: modeling, model validation using dynamic testing and on line estimation of parameters. For large scale systems where only few outputs are measurable, an estimation algorithm was developed, selecting the measurable output giving the minimum variance of the physical parameters. This estimation scheme uses a quasilinearization technique associated to the sensitivity equation and the recursive least squares techniques. For large scale systems of order greater than 100, two versions of the estimation scheme are proposed to decrease the computation time. An application to a nuclear reactor core (state variable model of order 29) is proposed and used real data. For distributed systems the estimation scheme was developed with either measurements at fixed time or at fixed space. The estimation algorithm selects the set of measurements that gives the minimum variance of the estimates. An application to a liquid-liquid extraction column, modelized by a set of four coupled partial differential equations, demonstrates the efficiency of the method

  12. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants

    International Nuclear Information System (INIS)

    Wang, Chia-Nan; Chen, Hsin-Po; Hsueh, Ming-Hsien; Chin, Fong-Li

    2017-01-01

    The Fukushima nuclear disaster in 2011 has raised widespread concern over the safety of nuclear power plants. This study employed knowledge management in conjunction with the Teoriya Resheniya Izobreatatelskih Zadatch (TRIZ) method in the formulation of a database to facilitate the evaluation of post-fire safe shutdown capability with the aim of safeguarding nuclear facilities in the event of fire. The proposed approach is meant to bring facilities in line with US Nuclear Regulatory Commission (NRC) standards. When implemented in a case study of an Asian nuclear power plant, our method proved highly effective in the detection of 22 cables that fell short of regulatory requirements, thereby reducing 850,000 paths to 0. This study could serve as reference for industry and academia in the development of systematic approaches to the upgrading of nuclear power plants.

  13. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Chia-Nan; Chen, Hsin-Po; Hsueh, Ming-Hsien; Chin, Fong-Li [National Kaohsiung Univ. of Applied Sciences, Kaohsiung City, Taiwan (China). Dept. of Industrial Engineering and Management

    2017-11-15

    The Fukushima nuclear disaster in 2011 has raised widespread concern over the safety of nuclear power plants. This study employed knowledge management in conjunction with the Teoriya Resheniya Izobreatatelskih Zadatch (TRIZ) method in the formulation of a database to facilitate the evaluation of post-fire safe shutdown capability with the aim of safeguarding nuclear facilities in the event of fire. The proposed approach is meant to bring facilities in line with US Nuclear Regulatory Commission (NRC) standards. When implemented in a case study of an Asian nuclear power plant, our method proved highly effective in the detection of 22 cables that fell short of regulatory requirements, thereby reducing 850,000 paths to 0. This study could serve as reference for industry and academia in the development of systematic approaches to the upgrading of nuclear power plants.

  14. The application of an integrated approach to design, procurement and construction in reducing overall nuclear power plant costs. Annex 19

    International Nuclear Information System (INIS)

    Didsbury, R.; Shalaby, B.A.; Torgerson, D.F.

    2002-01-01

    As part of its on-going efforts to reduce the cost of CANDU nuclear power plants, AECL has embarked on an integrated approach to design, procurement and construction activities associated with new CANDU 6 and CANDU 9 projects. The approach is predicated on the fact there is a vast quantity of information that needs to be managed and controlled over the life of a nuclear power plant project. Therefore, ensuring the completeness and correctness of all the information needed by all project participants, facilitating sharing of this information amongst the project's participants, and automating the various deliverable production processes offers significant potential not only for overall project cost (and schedule) savings but also for reducing operations and maintenance costs once the plant enters service. Facilitating and indeed of key importance to this approach is the use of a suite of integrated information technology-based engineering, procurement and project control tools used throughout the design, engineering, procurement and construction phases of the project. A unique and important feature of these tools is their high degree of integration both from a work process and a data perspective. Use of these tools is well underway on AECL's Qinshan Project which is realizing significant benefits in cost and schedule. This paper will describe the approach AECL is taking, along with the tools it has both put in place, and those additional items planned for the future along with the cost, schedule and quality benefits that arise from their use. Progress to date on the Qinshan project also will be discussed as well as the expected application to the plant once it has gone into service will also be discussed. (author)

  15. Design of nuclear power plants

    International Nuclear Information System (INIS)

    Lobo, C.G.

    1987-01-01

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

  16. Fuzzy logic control of nuclear power plant

    International Nuclear Information System (INIS)

    Yao Liangzhong; Guo Renjun; Ma Changwen

    1996-01-01

    The main advantage of the fuzzy logic control is that the method does not require a detailed mathematical model of the object to be controlled. In this paper, the shortcomings and limitations of the model-based method in nuclear power plant control were presented, the theory of the fuzzy logic control was briefly introduced, and the applications of the fuzzy logic control technology in nuclear power plant controls were surveyed. Finally, the problems to be solved by using the fuzzy logic control in nuclear power plants were discussed

  17. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    1997-01-01

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

  18. Characterization of ion exchange resins for nuclear power plants: Application and validation of a dedicated model

    International Nuclear Information System (INIS)

    Mabrouk, A.

    2012-01-01

    In pressurized water reactor, ion exchange resins (IER) are used in systems purification. In this thesis, a qualitative study has been performed to predict the behavior of IER while used in nuclear plants conditions. Then, we searched to characterize the IER behavior in column through a quantitative study using analytical solutions. But these solutions worked only for particular cases. In order to find a general solution, we used a new numerical solution: OPTIPUR. To validate this general solution and get a better understanding of the kinetic in column, we performed an experimental study to characterize the resistance to mass transfer in column and to study the sensibility on the parameters influencing this phenomenon. This study is based on the characterization of the initial leakage (initial pollutant concentration at the column outlet). We tested numerous parameters on the initial leakage. We understood the importance of the superficial velocity and indeed of the hydrodynamic conditions on the initial leakage. These numerous results about initial leakage were modeled with an empirical correlation of Dwivedi and Upadhyay in order to validate it. Then, we modeled our results with the two options of OPTIPUR software: option Mass Transfer Coefficient (MTC) and Nernst-Planck (NP). These options encircle experimental results. The MTC option of OPTIPUR gives lower results while those obtained with the NP option are higher than the experimental results. We observed also that only the NP option was valid for a ternary exchange. We proposed solutions to get a better fit with the results obtained with OPTIPUR. We performed other simulations to check the prediction abilities of the software for longer experiments (until the IER saturation). The tendencies were those expected. The OPTIPUR software showed is accuracy and robustness to study column kinetic. (author)

  19. Images of nuclear power plants

    International Nuclear Information System (INIS)

    Hashiguchi, Katsuhisa; Misumi, Jyuji; Yamada, Akira; Sakurai, Yukihiro; Seki, Fumiyasu; Shinohara, Hirofumi; Misumi, Emiko; Kinjou, Akira; Kubo, Tomonori.

    1995-01-01

    This study was conducted to check and see, using Hayashi's quantification method III, whether or not the respondents differed in their images of a nuclear power plant, depending on their demographic variables particularly occupations. In our simple tabulation, we compared subject groups of nuclear power plant employees with general citizens, nurses and students in terms of their images of a nuclear power plant. The results were that while the nuclear power plant employees were high in their evaluations of facts about a nuclear power plant and in their positive images of a nuclear power plant, general citizens, nurses and students were overwhelmingly high in their negative images of a nuclear power plant. In our analysis on category score by means of the quantification method III, the first correlation axis was the dimension of 'safety'-'danger' and the second correlation axis was the dimension of 'subjectivity'-'objectivity', and that the first quadrant was the area of 'safety-subjectivity', the second quadrant was the area of 'danger-subjectivity', the third quadrant as the area of 'danger-objectivity', and the forth quadrant was the area of 'safety-objectivity'. In our analysis of sample score, 16 occupation groups was compared. As a result, it was found that the 16 occupation groups' images of a nuclear power plant were, in the order of favorableness, (1) section chiefs in charge, maintenance subsection chiefs, maintenance foremen, (2) field leaders from subcontractors, (3) maintenance section members, operation section members, (4) employees of those subcontractors, (5) general citizens, nurses and students. On the 'safety-danger' dimension, nuclear power plant workers on the one hand and general citizens, nurses and students on the other were clearly divided in terms of their images of a nuclear power plant. Nuclear power plant workers were concentrated in the area of 'safety' and general citizens, nurses and students in the area of 'danger'. (J.P.N.)

  20. Nuclear power plant

    International Nuclear Information System (INIS)

    Uruma, Hiroshi

    1998-01-01

    In the first embodiment of the present invention, elements less activated by neutrons are used as reactor core structural materials placed under high neutron irradiation. In the second embodiment of the present invention, materials less activated by neutrons when corrosive materials intrude to a reactor core are used as structural materials constituting portions where corrosion products are generated. In the third embodiment, chemical species comprising elements less activated by neutrons are used as chemical species to be added to reactor water with an aim of controlling water quality. A nuclear power plant causing less radioactivity can be provided by using structural materials comprising a group of specific elements hardly forming radioactivity by activation of neutrons or by controlling isotope ratios. (N.H.)

  1. Nuclear power plant

    International Nuclear Information System (INIS)

    Schabert, H.P.

    1976-01-01

    A nuclear power plant is described which includes a steam generator supplied via an input inlet with feedwater heated by reactor coolant to generate steam, the steam being conducted to a steam engine having a high pressure stage to which the steam is supplied, and which exhausts the steam through a reheater to a low pressure stage. The reheater is a heat exchanger requiring a supply of hot fluid. To avoid the extra load that would be placed on the steam generator by using a portion of its steam output as such heating fluid, a portion of the water in the steam generator is removed and passed through the reheater, this water having received at least adequate heating in the steam generator to make the reheater effective, but not at the time of its removal being in a boiling condition

  2. Quality assurance organization for nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

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

  3. Nuclear power plants

    International Nuclear Information System (INIS)

    Kiyokawa, Teruyuki; Soman, Yoshindo.

    1985-01-01

    Purpose: To constitute a heat exchanger as one unit by integrating primary and secondary coolant circuits with secondary coolant circuit and steam circuit into a single primary circuit and steam circuit. Constitution: A nuclear power plant comprises a nuclear reactor vessel, primary coolant pipeways and a leakage detection system, in which a dual-pipe type heat exchanger is connected to the primary circuit pipeway. The heat conduction tube of the heat exchanger has a dual pipe structure, in which the inside of the inner tube is connected to the primary circuit pipeway, the outside of the outer tube is connected to steam circuit pipeway and a fluid channel is disposed between the inner and outer tubes and the fluid channel is connected to the inside of an expansion tank for intermediate heat medium. The leak detection system is disposed to the intermediate heat medium expansion tank. Sodium as the intermediate heat medium is introduced from the intermediate portion (between the inner and outer tubes) by way of inermediate heat medium pipeways to the intermediate heat medium expansion tank and, further, to the intermediate portion for recycling. (Kawakami, Y.)

  4. Review of nuclear electricity generation and desalination plants and evaluation of SMART application

    International Nuclear Information System (INIS)

    Kang, Han Ok; Kang, Hyung Suk; Cho, Bong Hyun; Yoon, Ju Hyeon; Kim, Hwan Yeol; Lee, Young Jin; Kim, Joo Pyung; Lee, Doo Jeong; Chang, Moon Hee

    1998-03-01

    KAERI are developing a new advanced integral reactor named SMART for dual application purpose of the electric power generation and seawater desalination. This report are describing the general desalting methods with its technology development and the coupling schemes between electricity generation system and desalting system. Though MSF takes the most part of currently operating seawater desalination plants, MED and RO has been preferred in the past decade. MED has a advantage over MSF with the view to investment costs and energy efficiency. The coupling between electricity generation system and desalination system can be realized by using one of back pressure cycle, extraction cycle, and multi-shaft cycle. New design and operating strategy has to be established for various environment and load conditions. To evaluate the candidate desalination systems of SMART and the coupling method of it with other secondary systems, the desalted water and electricity were calculated through the several options. The result shows that back pressure cycle is preferred at the high water/power ratio and extraction cycle at the low value. If energy efficiency are only considered, RO will be best choice. (author). 17 refs., 12 tabs., 31 figs

  5. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    International Nuclear Information System (INIS)

    Yang, Chih Wei; Cheng, Tsung Chieh; Lin, Chiuhsiang Joe

    2011-01-01

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner

  6. Design and implementation of remote robotic control system for nuclear power plant application achieved through kinesthetic force feedback model

    International Nuclear Information System (INIS)

    Roy, D.

    1995-01-01

    The technology of telerobotic control through a universal and transparent Man-Machine Interface is a growing field of robotics research in today's industrial scenario because of its promising application in hazardous and unstructured environments. The joystick, a sophisticated information receiver-translator-transmitter device, serves as a Man-Machine Interface for telerobots. The present paper describes the development paradigms of a remote control system for a planar four degrees-of-freedom joystick following position feed-forward force/torque feedback strategy in a bi-lateral mode. This joystick based control technology is designed to actuate an industrial robot working in nuclear power plant. The remote control system has been illustrated with model, algorithm, electronic hardware and software routines along with experimental results in order to have effective telemanipulation

  7. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chih Wei; Cheng, Tsung Chieh [Institute of Nuclear Energy Research, Taoyuan (China); Lin, Chiuhsiang Joe [Chung-Yuan Christian University, Chung Li (China)

    2011-08-15

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner.

  8. Perspectives of nuclear power plants

    International Nuclear Information System (INIS)

    Vajda, Gy.

    2001-01-01

    In several countries the construction of nuclear power plants has been stopped, and in some counties several plants have been decommissioned or are planned to. Therefore, the question arises: have nuclear power plants any future? According to the author, the question should be reformulated: can mankind survive without nuclear power? To examine this challenge, the global power demand and its trends are analyzed. According to the results, traditional energy sources cannot be adequate to supply power. Therefore, a reconsideration of nuclear power should be imminent. The economic, environmental attractions are discussed as opposite to the lack of social support. (R.P.)

  9. The application of VMEbus system to the safety related parameters indication and alarm system for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chul Kwon; Koo, In Soo; Jang, Gwi Sook; Shin, Jae Hwal

    1996-12-01

    This report presents the basic feature, the status of technical development, and it`s application for the VMEbus which has been utilized in industrial application such as controller, robotics, automation control. The application software of VMEbus is also reviewed. The design considerations are presented when applying the system to the instrumentation and control technique of nuclear power plants. The conceptual design of safety related parameter using the integrated VMEbus system. The results indicate that the application of VMEbus has advantages such as easy maintenance, accurate and reliable operation, easy expansion and upgrade. Also, the integrated VMEbus system is capable of limited real-time processing because it can be processed by multi-processors and can reduce the effort of software development by using off-the-shelf software. However, the adoption of digital system is produced problems such as software common mode failure, EMI and RFI, and verification and validation methods of off-the-shelf hardware and software. To resolve these problems in the future, further research are required. (author). 7 tabs., 19 figs., 24 refs.

  10. An improvement of the applicability of human factors guidelines for coping with human factors issues in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Y. H.; Lee, J. Y.

    2003-01-01

    Human factors have been well known as one of the key factors to the system effectiveness as well as the efficiency and safety of nuclear power plants(NPPs). Human factors engineering(HFE) are included in periodic safety review(PSR) on the existing NPPs and the formal safety assessment for the new ones. However, HFE for NPPs is still neither popular in practice nor concrete in methodology. Especially, the human factors guidelines, which are the most frequent form of human factors engineering in practice, reveal the limitations in their applications. We discuss the limitations and their casual factors found in human factors guidelines in order to lesson the workload of HFE practitioners and to improve the applicability of human factors guidelines. According to the purposes and the phases of HFE for NPPs, more selective items and specified criteria should be prepared carefully in the human factors guidelines for the each HFE applications in practice. These finding on the human factors guidelines can be transferred to the other HFE application field, such as military, aviation, telecommunication, HCI, and product safety

  11. The application of VMEbus system to the safety related parameters indication and alarm system for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Chul Kwon; Koo, In Soo; Jang, Gwi Sook; Shin, Jae Hwal.

    1996-12-01

    This report presents the basic feature, the status of technical development, and it's application for the VMEbus which has been utilized in industrial application such as controller, robotics, automation control. The application software of VMEbus is also reviewed. The design considerations are presented when applying the system to the instrumentation and control technique of nuclear power plants. The conceptual design of safety related parameter using the integrated VMEbus system. The results indicate that the application of VMEbus has advantages such as easy maintenance, accurate and reliable operation, easy expansion and upgrade. Also, the integrated VMEbus system is capable of limited real-time processing because it can be processed by multi-processors and can reduce the effort of software development by using off-the-shelf software. However, the adoption of digital system is produced problems such as software common mode failure, EMI and RFI, and verification and validation methods of off-the-shelf hardware and software. To resolve these problems in the future, further research are required. (author). 7 tabs., 19 figs., 24 refs

  12. New treatment of low probability events with particular application to nuclear power plant incidents

    Energy Technology Data Exchange (ETDEWEB)

    Critchley, O.H.

    1986-01-01

    The 'New Treatment' attempts to resolve the 'Zero-Infinity Dilemmas' posed by the threat of low probability events (LPE) philosophical approach which rejects mathematical idealism in favour of the engineering pragmatism that is characteristic of the scientific method. The LPE is seen as a rare singularity in the stream of 'Event-noise' of mundane, untoward incidents that afflict industrial systems. Engineering inspection which has evolved as a regulatory mechanism can be effective in reducing this 'noise' and the competent inspector is able to recognise the 'loss of resistance to failure' which so often comes before an LPE. Despite that an intractable residual risk remains, but this can be made societally tolerable if there is a justifiable conviction that safety is defended by trustworthy engineering. In an age marked by an increasing complexity and sophistication in its science and technology, the engineer is emerging as the proper central decision maker in such matters standing, athwart pure administration and theory on the one hand and expertise and practice on the other. Moreover, evidence that his intellect may be peculiarly adapted for such a role is coming from recent findings in neuropsychology. The Nuclear Installations Inspectorate is cited as an exemplar of the engineering inspection needed to apprehend those human fallibilities in design and application to which most catastrophic failures of technology are due. However, such regulatory systems and the assessment functions associated with them lack accountability and, as an interpretation of Goedel's theorem suggests, cannot assess their own efficiency. Independent, disinterested appraisal assisted by Signal Detection Theory is offered as a remedy.

  13. Nuclear power plants in the world - 2010 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2009 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2010/01/01, Worldwide status of nuclear power plants (12/31/2009), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2009, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear power plants by country at the end 2009, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2009, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2009, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2009, Long term shutdown units at 12/31/2009, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

  14. Elecnuc - Nuclear power plants in the world - 2009 edition

    International Nuclear Information System (INIS)

    2009-01-01

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2008 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2008/01/01, Worldwide status of nuclear power plants (12/31/2008), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2008, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear powe plants by country at the end 2008, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2008, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2008, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2008, Long term shutdown units at 12/31/2008, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

  15. ELECNUC Nuclear power plants in the world - 2013 edition

    International Nuclear Information System (INIS)

    2013-01-01

    This small booklet summarizes in a series of tables the figures relative to the nuclear power plants worldwide. Data come from the IAEA's PRIS database and from specific I-tese studies. The following aspects are reviewed: 2012 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2012/01/01; Worldwide status of nuclear power plants (12/31/2012); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2012; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2012; Performance indicator of french PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2012; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2012; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2012; Long term shutdown units at 12/31/2012; COL (Combined Licence) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

  16. Owners of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-11-01

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

  17. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-13

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

  18. An application of risk-informed evaluation on MOVs and AOVs for Taiwan BWR-type nuclear power plants

    International Nuclear Information System (INIS)

    Ting, K.; Chen, K.T.; Li, Y.C.; Hwang, S.H.; Chien, F.T.; Kang, J.C.

    2008-01-01

    Implementing a risk-informed inservice testing (RI-IST) program provides a good aspect to the nuclear power plant licensee as an alternating program in the current ASME Section XI and 10 CFR 50.55a relevant testing programs. RI-IST concentrates testing resources on highly significant components, reduces excess testing burden, increases plant's availability, decreases dose rate on the plant's staff and also reduces cost on plant's operation and maintenance under nuclear safety expectations. Furthermore, RI-IST also gives a feature on prospective licensing change basis to a nuclear power plant's licensee. This study will focus on safety-related and PRA-molded motor-operated valves (MOVs) and air-operated valves (AOVs) under the inservice testing program in boiling water reactor (BWR)-type nuclear power plant. As MOVs and AOVs have crucial safety functions throughout the nuclear power plant's safety systems, the steady operation and performance of MOVs and AOVs will definitely ensure that the nuclear power plant operates under safety expectations; therefore, this is the key reason to implement risk-informed evaluation for MOVs and AOVs in this study and being able to provide the safety significance classification for MOVs and AOVs under the current IST program to the plant's management. As a pilot study of RI-IST, the methodology of qualitative assessment will incorporate with probabilistic risk assessment (PRA) analyzing MOVs' and AOVs' safety significance within the current PRA model. The evaluating result will then classify its safety significance into a high-safety significant component (HSSC) and a low-safety significant component (LSSC) for MOVs and AOVs based on relevant regulatory criteria. With this initiating achievement, it can provide a cornerstone for further studies on the other types of valves and pumps in RI-IST program and also provide a valuable reference as proposing license change to the licensee

  19. Regulatory requirements for desalination plant coupled with nuclear reactor plant

    International Nuclear Information System (INIS)

    Yune, Young Gill; Kim, Woong Sik; Jo, Jong Chull; Kim, Hho Jung; Song, Jae Myung

    2005-01-01

    A small-to-medium sized reactor has been developed for multi-purposes such as seawater desalination, ship propulsion, and district heating since early 1990s in Korea. Now, the construction of its scaled-down research reactor, equipped with a seawater desalination plant, is planned to demonstrate the safety and performance of the design of the multi-purpose reactor. And the licensing application of the research reactor is expected in the near future. Therefore, a development of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant is necessary for the preparation of the forthcoming licensing review of the research reactor. In this paper, the following contents are presented: the design of the desalination plant, domestic and foreign regulatory requirements relevant to desalination plants, and a draft of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant

  20. Environmental standard review plans for the environmental review of construction permit applications for nuclear power plants

    International Nuclear Information System (INIS)

    1979-05-01

    Information is presented concerning environmental descriptions; plant description; environmental impacts of construction; environmental impacts of station operation; environmental measurements and monitoring programs; environmental impacts of postulated accidents involving radioactive materials; the need for the plant; alternatives to the project; and evaluation of the proposed action

  1. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    1998-01-01

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

  2. Nuclear power plant performance monitoring using Data Validation and Reconciliation (DVR). Application at the Brazilian Angra 2 PWR plant

    International Nuclear Information System (INIS)

    Tran Quang, Anh Tho; Closon, Hervé; Chares, Robert; Azola, Edson

    2011-01-01

    Operational decisions related to plant performance monitoring mainly result from raw process measurement analysis. When first signs of sub-optimal behavior occur, traditional methods mainly focus on the observation of selective pieces of information. The main disadvantages of these methods are: Investigation efforts are required to localize the problems, entailing time losses and costs; Validity and reliability of the pieces of information cannot be checked as long as the measurements are observed individually. The problem is not the lack of methods and techniques but rather a lack of reliable and consistent data and information across the entire plant. To overcome drawbacks of traditional methods, measurements are considered as interacting with one another. When related to the other measurements of the plant, the observed information becomes of an interest: its incoherency to the others identifies and localizes a problem. The Data Validation and Reconciliation technology (DVR) is based on an advanced process data coherency treatment. By using all available plant information and by closing the plant heat and mass balances based on rigorous thermodynamics, the method generates: A single set of reliable and most accurate plant process data; Alarms for incoherent measurements, highlighting potential problems; Alarms for equipment and process performance degradation; Alarms for faulty and drifting measurements. The use of the advanced DVR software package VALI offers various benefits as it allows to base operational decisions on reliable and accurate data. (author)

  3. Linguistic control of a nuclear power plant

    International Nuclear Information System (INIS)

    Feeley, J.J.; Johnson, J.C.

    1987-01-01

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

  4. Nuclear Technology applications

    International Nuclear Information System (INIS)

    Cibils Machado, W. E- mail: wrcibils@adinet.com.uy

    2002-01-01

    The present work tries on the applications of the nuclear technology in the life daily, such as agriculture and feeding, human health, industry, non destructive essays, isotopic hydrology, and the nuclear power stations for electricity production and radioisotopes production

  5. Formal specification and verification of interactive systems with plasticity: Applications to nuclear-plant supervision

    International Nuclear Information System (INIS)

    Oliveira, Raquel Araujo de

    2015-01-01

    specification. Usability properties verify whether the system follows ergonomic properties to ensure a good usability. Validity properties verify whether the system follows the requirements that specify its expected behavior.-The comparison of different versions of UIs. Using equivalence checking, our approach verifies to which extent UIs present the same interaction capabilities and appearance. We can show whether two UI models are equivalent or not. When they are not equivalent, the UI divergences are listed, thus providing the possibility of leaving them out of the analysis. Furthermore, the approach shows that one UI can contain at least all interaction capabilities of another. We also present in this thesis three industrial case studies in the nuclear power plant domain which the approach was applied to, providing additional examples of successful use of formal methods in industrial systems. (author)

  6. A human error analysis methodology, AGAPE-ET, for emergency tasks in nuclear power plants and its application

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Whan; Jung, Won Dea [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-03-01

    This report presents a procedurised human reliability analysis (HRA) methodology, AGAPE-ET (A Guidance And Procedure for Human Error Analysis for Emergency Tasks), for both qualitative error analysis and quantification of human error probability (HEP) of emergency tasks in nuclear power plants. The AGAPE-ET is based on the simplified cognitive model. By each cognitive function, error causes or error-likely situations have been identified considering the characteristics of the performance of each cognitive function and influencing mechanism of PIFs on the cognitive function. Then, error analysis items have been determined from the identified error causes or error-likely situations to help the analysts cue or guide overall human error analysis. A human error analysis procedure based on the error analysis items is organised. The basic scheme for the quantification of HEP consists in the multiplication of the BHEP assigned by the error analysis item and the weight from the influencing factors decision tree (IFDT) constituted by cognitive function. The method can be characterised by the structured identification of the weak points of the task required to perform and the efficient analysis process that the analysts have only to carry out with the necessary cognitive functions. The report also presents the the application of AFAPE-ET to 31 nuclear emergency tasks and its results. 42 refs., 7 figs., 36 tabs. (Author)

  7. Nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Urata, Hidehiro; Oya, Takashi

    1996-11-05

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  8. Nuclear power plant

    International Nuclear Information System (INIS)

    Urata, Hidehiro; Oya, Takashi.

    1996-01-01

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  9. Nuclear power plants

    International Nuclear Information System (INIS)

    Ushijima, Susumu.

    1984-01-01

    Purpose: To enable to prevent the degradation in the quality of condensated water in a case where sea water leakage should occur in a steam condenser of a BWR type nuclear power plant. Constitution: Increase in the ion concentration in condensated water is detected by an ion concentration detector and the leaking factor of sea water is calculated in a leaking factor calculator. If the sea water leaking factor exceeds a predetermined value, a leak generation signal is sent from a judging device to a reactor power control device to reduce the reactor power. At ehe same tiem, the leak generation signal is also sent to a steam condenser selection and isolation device to interrupt the sea water pump of a specified steam condenser based on the signal from the ion concentration detector, as well as close the inlet and outlet valves while open vent and drain valves to thereby forcively discharge the sea water in the cooling water pipes. This can keep the condensate desalting device from ion breaking and prevent the degradation in the quality of the reactor water. (Horiuchi, T.)

  10. Underground nuclear power plant

    International Nuclear Information System (INIS)

    Takahashi, Hideo.

    1997-01-01

    In an underground-type nuclear power plant, groups of containing cavities comprising a plurality of containing cavities connected in series laterally by way of partition walls are disposed in parallel underground. Controlled communication tunnels for communicating the containing cavities belonging to a control region to each other, and non-controlled communication tunnels for communicating containing cavities belonging to a non-controlled area to each other are disposed underground. A controlled corridor tunnel and a non-controlled corridor tunnel extended so as to surround the containing cavity groups are disposed underground, and the containing cavities belonging to the controlled area are connected to the controlled corridor tunnel respectively, and the containing cavities belonging to the non-controlled area are connected to the non-controlled corridor tunnel respectively. The excavating amount of earth and sand upon construction can be reduced by disposing the containing cavity groups comprising a plurality of containing cavities connected in series laterally. The time and the cost for the construction can be reduced, and various excellent effects can be provided. (N.H.)

  11. Nuclear power plant diagnostic system

    International Nuclear Information System (INIS)

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  12. Experience on the application of safeguard systems to the Italian nuclear power plants

    International Nuclear Information System (INIS)

    Marzocchi, A.; Venchiarutti, R.; Gatti, S.; Bertini, A.; Zaffiro, B.

    1977-01-01

    The safeguard systems applied in Italy to the various fuel cycle phases, including nuclear power stations, are presented in this paper in view of the present situation resulting from the Rome Treaty obligations and from the obligations to be defined in relation to the ratification of TNP by Italy. This short survey concerns not only the systems usually applied, but also the research and development aspects of new systems that facilitate the attainment of the aims specified in the Treaties. Moreover this paper illustrates the philosophy of nuclear material physical security, aiming at supplementing the efficiency of the safeguard systems [fr

  13. Dose reduction and the application of the ALARP principle to occupational exposure at the nuclear fuel reprocessing plant at Sellafield in Cumbria

    International Nuclear Information System (INIS)

    Anderson, R.W.; Coates, R.

    1991-01-01

    This paper presents information on the application of the ALARP principle to Dose Reduction at the British Nuclear Fuels plc site at Sellafield in Cumbria. The development of the Operational methods employed to effect dose reductions on existing plants and the impact of stringent targets for new plants is described in addition to discussion of the factors initiating the change and the success of the initiatives. (Author)

  14. Nuclear power plant V-1

    International Nuclear Information System (INIS)

    1998-01-01

    The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

  15. UPVAPOR: computer application for the analysis of the results of Cofrentes Nuclear Power Plant production; UPVAPOR: Aplicacion informatica para el analisis de resultados de produccion en Central Nuclear Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, M. J.; Baraza Peregrin, A.; Bucho Piqueras, L.; Vaquer Perez, J. I.; Lopez Lopez, B.

    2010-07-01

    UPVapor is a software developed for the Cofrentes Nuclear Power Plant Group of Results. This application presents a graphical environment for analysis in which the user has available many variables registered to configure the graphics. This application saves a lot of time at work because it allows other users to do their own analysis without resorting to analysts.

  16. Environmental and security challenges of nuclear plants

    International Nuclear Information System (INIS)

    Omar, A.S.

    2014-01-01

    The world population increase, the acceleration of global requirement for development and the need to expand energy production, have led to the depletion of natural resources. The international efforts are increasing to get clean, safe and economical energy sources . The electricity generated from nuclear energy considers less polluting and high economic competitiveness as well as reliability and efficiency. The nuclear power plants projects face significant challenges, especially after two major accidents, in Chernobyl 1986 and Fukushima 2011 including the fears of radiation effects, nuclear waste management and nuclear proliferation issues, as well as the lack of public acceptance. So those bodies interested in operating nuclear power plants work to increase nuclear safety standards, review the nuclear facilities safety, know the strict application of laws, seek to prove the economic competitiveness, maintain environmental security, assist in the nonproliferation regime and gain public acceptance. This article discusses the most important environmental and security challenges of nuclear power plants. It highlights the importance of the peaceful uses of nuclear energy as a source of sustainable development and environmental security. It also offers a number of recommendations to support the Arab countries trend towards the inclusion of nuclear energy option within their national programs to generate electricity. (author)

  17. Liquid and solid rad waste treatment in advanced nuclear power plants. Application to the SBWR design

    International Nuclear Information System (INIS)

    Tielas Reina, M.; Asuar Alonso, O.

    1994-01-01

    Rad waste treatment requirements for the new generation of American advanced passive and evolutionary power plants are listed in the URD (Utility Requirements Document) of the EPRI (Electrical Power Research Institute). These requirements focus on: - Minimization of shipped solid wastes - Minimization of liquid effluents - Simplification of design and operation, with emphasis not only on waste treatment system design but also on general plant design and operation These objectives are aimed at: - Reducing and segregating wastes at source - Minimizing chemical contamination of these wastes System design simplification is completed by providing free space in the building for the use of mobile plants, either for special services not considered in the basic design or to accommodate future technical advances. (Author)

  18. Joint application of AI techniques, PRA and disturbance analysis methodology to problems in the maintenance and design of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Okrent, D.

    1989-03-01

    This final report summarizes the accomplishments of a two year research project entitled Joint Application of Artificial Intelligence Techniques, Probabilistic Risk Analysis, and Disturbance Analysis Methodology to Problems in the Maintenance and Design of Nuclear Power Plants. The objective of this project is to develop and apply appropriate combinations of techniques from artificial intelligence, (AI), reliability and risk analysis and disturbance analysis to well-defined programmatic problems of nuclear power plants. Reactor operations issues were added to those of design and maintenance as the project progressed.

  19. Joint application of AI techniques, PRA and disturbance analysis methodology to problems in the maintenance and design of nuclear power plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Okrent, D.

    1989-03-01

    This final report summarizes the accomplishments of a two year research project entitled ``Joint Application of Artificial Intelligence Techniques, Probabilistic Risk Analysis, and Disturbance Analysis Methodology to Problems in the Maintenance and Design of Nuclear Power Plants. The objective of this project is to develop and apply appropriate combinations of techniques from artificial intelligence, (AI), reliability and risk analysis and disturbance analysis to well-defined programmatic problems of nuclear power plants. Reactor operations issues were added to those of design and maintenance as the project progressed.

  20. Joint application of AI techniques, PRA and disturbance analysis methodology to problems in the maintenance and design of nuclear power plants

    International Nuclear Information System (INIS)

    Okrent, D.

    1989-01-01

    This final report summarizes the accomplishments of a two year research project entitled ''Joint Application of Artificial Intelligence Techniques, Probabilistic Risk Analysis, and Disturbance Analysis Methodology to Problems in the Maintenance and Design of Nuclear Power Plants. The objective of this project is to develop and apply appropriate combinations of techniques from artificial intelligence, (AI), reliability and risk analysis and disturbance analysis to well-defined programmatic problems of nuclear power plants. Reactor operations issues were added to those of design and maintenance as the project progressed

  1. Man and nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    According to the Inst. fuer Unfallforschung/TUeV Rheinland, Koeln, the interpretation of empirical data gained from the operation of nuclear power plants at home and abroad during the period 1967-1975 has shown that about 38% of all reactor accidents were caused by human failures. These occured either during the design and construction, the commissioning, the reconditioning or the operation of the plants. This very fact stresses human responsibility for the safety of nuclear power plants, in spite of those plants being automated to a high degree and devices. (orig.) [de

  2. The application of artificial intelligence chemistry diagnostic system to nuclear power plants

    International Nuclear Information System (INIS)

    Chen Meizhen

    1996-01-01

    By processing water chemistry data to diagnose sensor and equipment malfunctions in realtime, artificial intelligence chemistry diagnostic system helps to reduce the plant downtime due to steam generator tubing failures and other accidents. A typical processing system of water chemistry data is presented

  3. Development of the safety analysis system - SAIS - application to the Kola nuclear power plant

    International Nuclear Information System (INIS)

    Balfanz, H.P.; Fuhrmann, C.; Neumann, L.; Rumpf, J.; Kubintsev, B.; Marakulin, I.; Shevelev, V.; Terekhov, I.

    1995-01-01

    The project was started in July 1991 and finished by the end of 1993. It was aimed at adapting SAIS to WWER-440/W213 plant design and operational procedures, demonstrating the possibilities of SAIS for safety evaluation and examining the system by plant personnel and a PSA team. The project covered -the use of data form as well as fault and event tree methods of SAIS, - a probabilistic assessment of the high pressure injection system in case of a small break loss-of-coolant accident, - a quantification of human error probabilities for operator actions to cool down the primary circuit in case of a small break loss-of-coolant accident when the high pressure injection system has failed and - a comparison of Russian and German operational procedures and safety documents used in the probabilistic analyses of the SAIS-Kola project. As a main result SAIS was found to be an appropriate tool to give assistance to the plant personnel on safety evaluation of the plant within the frame of reconstruction measures and on the establishment of a qualified reliability data collection system at Kola NPP. (orig./HP) [de

  4. Computer based virtual reality approach towards its application in an accidental emergency at nuclear power plant

    International Nuclear Information System (INIS)

    Yan Jun; Yao Qingshan

    1999-01-01

    Virtual reality is a computer based system for creating and receiving virtual world. As an emerging branch of computer discipline, this approach is extensively expanding and widely used in variety of industries such as national defence, research, engineering, medicine and air navigation. The author intends to present the fundamentals of virtual reality, in attempt to study some interested aspects for use in nuclear power emergency planning

  5. Evolution of seismic monitoring systems of nuclear power plants. Improvements and practical applications

    International Nuclear Information System (INIS)

    Sanchez Cabanero, J. G.; Jimenez Juan, A.

    2010-01-01

    The II. NN. Spanish have a seismic monitoring system (SVS) covering two objectives relevant to nuclear security: determining earthquake leave operation, and specific data that serve to limit or reduce the uncertainties associated with the seismic source, the site and design. Since its construction, the major SVS II. NN. have been equipped with the best time of seismic instrumentation to record earthquakes strong, but with limited resolution for recording in the free field and appropriately moderate earthquakes.

  6. Radiochemistry in nuclear power plants

    International Nuclear Information System (INIS)

    Schwarz, W.

    2007-01-01

    Radiochemistry is employed in nuclear power plants not as an end in itself but, among other things, as a main prerequisite of optimum radiation protection. Radiochemical monitoring of various loops provides important information about sources of radioactivity, activity distribution in the plant and its changes. In the light of these analytical findings, plant crews are able to take measures having a positive effect on radiation levels in the plant. The example of a BWR plant is used to show, among other things, how radiochemical analyses helped to reduce radiation levels in a plant and, as a consequence, to decrease clearly radiation exposure of the personnel despite higher workloads. (orig.)

  7. Nuclear Power Plant Simulation Game.

    Science.gov (United States)

    Weiss, Fran

    1979-01-01

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

  8. The safety of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    Do nuclear power plants present an unjustifiable risk Can there be confidence in their safety The Uranium Institute invited a group of senior safety experts from eight different Western countries operating different types of reactors to provide an authoritative explanation for non-specialists of the basic principles of reactor safety, their application and their implications. The report presents the group's opinion on the level of safety achieved in the Western nuclear power plants with which the authors are directly familiar. Although many of the points made may well also be true for non-Western reactors, the report does not cover them except where specifically stated. It does describe and discuss the causes of the Chernobyl disaster. It does not compare nuclear power with other fuels, nor does it deal with its benefits, since however great the benefits from the peaceful use of nuclear power, and its own advantages over other fuels, they could not compensate for lack of safety. The conclusion reached is that the risk associated with electricity production at nuclear power plants can be kept very low. Proper use of the extensive knowledge available today can guarantee operation of nuclear power plants at very high safety levels, carrying very low risks, both to health and of contamination of the environment: risks that are continually lowered by upgrading existing plants and their operation, and by the design of future power plants. (author).

  9. High temperature, radiation hardened electronics for application to nuclear power plants

    International Nuclear Information System (INIS)

    Gover, J.E.

    1980-01-01

    Electronic circuits were developed and built at Sandia for many aerospace and energy systems applications. Among recent developments were high temperature electronics for geothermal well logging and radiation hardened electronics for a variety of aerospace applications. Sandia has also been active in technology transfer to commercial industry in both of these areas

  10. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

    1984-01-01

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

  11. Robotics for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

    1984-10-01

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

  12. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Vollradt, J.

    1977-01-01

    A survey of the main questions of decommissioning of nuclear power plants will be given in the sight of German utilities (VDEW-Working group 'Stillegung'). The main topics are: 1) Definitions of decommissioning, entombment, removal and combinations of such alternatives; 2) Radioactive inventory (build up and decay); 3) Experience up to now; 4) Possibilities to dismantle are given by possibility to repair nuclear power plants; 5) Estimated costs, waste, occupational radiation dose; 6) German concept of decommissioning. (orig./HK) [de

  13. Nuclear power plant component protection

    International Nuclear Information System (INIS)

    Michel, E.; Ruf, R.; Dorner, H.

    1976-01-01

    Described is a nuclear power plant installation which includes a concrete biological shield forming a pit in which a reactor pressure vessel is positioned. A steam generator on the outside of the shield is connected with the pressure vessel via coolant pipe lines which extend through the shield, the coolant circulation being provided by a coolant pump which is also on the outside of the shield. To protect these components on the outside of the shield and which are of mainly or substantially cylindrical shape, semicylindrical concrete segments are interfitted around them to form complete outer cylinders which are retained against outward separation radially from the components, by rings of high tensile steel which may be interspaced so closely that they provide, in effect, an outer steel cylinder. The invention is particularly applicable to pressurized-water coolant reactor installations

  14. Application of the Commercial Grade Item (CGI) Dedication Process for Procurement of Nuclear Safety Related Items at Nuclear Power Plant Krsko (NEK)

    International Nuclear Information System (INIS)

    Heruc, Z.; Pozar, J.

    1998-01-01

    CGI procurement is a process whereby parts are brought without imposing Appendix B Quality Assurance requirements on the supplier, and than dedicated for use in safety-related applications. The dedication process involves 1) based upon required safety function, an engineering evaluation to identify critical characteristic of the item and specification of acceptance criteria; and 2) quality control activities to ensure the item(s) supplied meets the acceptance criteria specified. CGI Dedication supports the supply of certified components/parts for the plant operation in an environment where the number of nuclear qualified suppliers diminishes. It requires a more active role of the plant personnel, therefore presenting an additional burden on human resources, but at the same time increases the technical KNOW-HOW and improves the confidence of test and inspection data presented in the certificates. Very often it is also cost beneficial. This paper is a continuation to last year presentation of the introduction of this method into NEK's procurement process and presents the current approach and some practical examples. (author)

  15. Nuclear cratering applications

    International Nuclear Information System (INIS)

    Williamson, M.M.

    1969-01-01

    The development of nuclear excavation technology is based on the promise that the relatively inexpensive energy available from thermonuclear explosives can be used to simultaneously break and move age quantities of rock and earth economically and safety. This paper discusses the economic and other advantages of using nuclear excavation for large engineering projects. A brief description of the phenomenology of nuclear excavation is given. Each of the several proposed general applications of nuclear excavation is discussed to include a few specific example of possible nuclear excavation projects. The discussion includes nuclear excavation for harbors, canals, terrain transits, aggregate production, mining and water resource development and conservation. (author)

  16. Nuclear cratering applications

    Energy Technology Data Exchange (ETDEWEB)

    Williamson, M M [U.S. Atomic Energy Commission, Germantown, MD (United States)

    1969-07-01

    The development of nuclear excavation technology is based on the promise that the relatively inexpensive energy available from thermonuclear explosives can be used to simultaneously break and move age quantities of rock and earth economically and safety. This paper discusses the economic and other advantages of using nuclear excavation for large engineering projects. A brief description of the phenomenology of nuclear excavation is given. Each of the several proposed general applications of nuclear excavation is discussed to include a few specific example of possible nuclear excavation projects. The discussion includes nuclear excavation for harbors, canals, terrain transits, aggregate production, mining and water resource development and conservation. (author)

  17. Development of methodology to assess application of practical elimination for nuclear power plants

    International Nuclear Information System (INIS)

    Jung, J.; Sivekumar, D.; Thambirasa, S.

    2015-01-01

    The Fukushima Daiichi nuclear accident is presented as the primary case study for the topic of practical elimination. A decision matrix was created to assess whether practical elimination has been achieved or not. Public acceptance is included as a factor in practical elimination. An evaluation of an underground High-Temperature Gas Cooled Reactor was performed, where it was determined that a greater than 10 earthquake on the Richter scale is practically eliminated, but can easily be overturned based on public acceptance. A plane crash scenario was also practically eliminated. The gap analysis performed concluded that the developed decision matrix requires reworking. (author)

  18. Quality assurance during operation of nuclear power plants

    International Nuclear Information System (INIS)

    1994-01-01

    The general requirements applicable to the quality assurance of the Finnish nuclear power plants are presented in the Council of State Decision (395/91) and in the guide YVL 1.4. This guide specifies the quality assurance requirements to be applied during the operation of the nuclear power plants as well as of the other nuclear facilities. Quality assurance applies to all the activities and organizations with a bearing on the safe operation of the nuclear power plants. (5 refs.)

  19. Robotic devices for nuclear plant

    Energy Technology Data Exchange (ETDEWEB)

    Abel, E

    1986-05-01

    The article surveys the background of nuclear remote handling and its associated technology, robotics. Manipulators, robots, robot applications, extending the range of applications, and future developments, are all discussed.

  20. A nuclear power plant system engineering workstation

    International Nuclear Information System (INIS)

    Mason, J.H.; Crosby, J.W.

    1989-01-01

    System engineers offer an approach for effective technical support for operation and maintenance of nuclear power plants. System engineer groups are being set up by most utilities in the United States. Institute of Nuclear Power operations (INPO) and U.S. Nuclear Regulatory Commission (NRC) have endorsed the concept. The INPO Good Practice and a survey of system engineer programs in the southeastern United States provide descriptions of system engineering programs. The purpose of this paper is to describe a process for developing a design for a department-level information network of workstations for system engineering groups. The process includes the following: (1) application of a formal information engineering methodology, (2) analysis of system engineer functions and activities; (3) use of Electric Power Research Institute (EPRI) Plant Information Network (PIN) data; (4) application of the Information Engineering Workbench. The resulting design for this system engineer workstation can provide a reference for design of plant-specific systems

  1. Organizing nuclear power plant operation

    International Nuclear Information System (INIS)

    Adams, H.W.; Rekittke, K.

    1987-01-01

    With the preliminary culmination in the convoy plants of the high standard of engineered safeguards in German nuclear power plants developed over the past twenty years, the interest of operators has now increasingly turned to problems which had not been in the focus of attention before. One of these problems is the organization of nuclear power plant operation. In order to enlarge the basis of knowledge, which is documented also in the rules published by the Kerntechnischer Ausschuss (Nuclear Technology Committee), the German Federal Minister of the Interior has commissioned a study of the organizational structures of nuclear power plants. The findings of that study are covered in the article. Two representative nuclear power plants in the Federal Republic of Germany were selected for the study, one of them a single-unit plant run by an independent operating company in the form of a private company under German law (GmbH), the other a dual-unit plant operated as a dependent unit of a utility. The two enterprises have different structures of organization. (orig.) [de

  2. Nuclear power plant transients: where are we

    International Nuclear Information System (INIS)

    Majumdar, D.

    1984-05-01

    This document is in part a postconference review and summary of the American Nuclear Society sponsored Anticipated and Abnormal Plant Transients in Light Water Reactors Conference held in Jackson, Wyoming, September 26-29, 1983, and in part a reflection upon the issues of plant transients and their impact on the viability of nuclear power. This document discusses state-of-the-art knowledge, deficiencies, and future directions in the plant transients area as seen through this conference. It describes briefly what was reported in this conference, emphasizes areas where it is felt there is confidence in the nuclear industry, and also discusses where the experts did not have a consensus. Areas covered in the document include major issues in operational transients, transient management, transient events experience base, the status of the analytical tools and their capabilities, probabilistic risk assessment applications in operational transients, and human factors impact on plant transients management

  3. International safety standards and regulatory practices and their application to Brazilian nuclear power plants - a realistic view

    International Nuclear Information System (INIS)

    Almeida, Claudio; Camargo, Claudio

    1999-01-01

    An international nuclear safety regime is being established through a series of binding safety conventions, voluntarily adopted international safety standards and an accompanying peer review process. The basis for the evaluation of each country performance within this international regime should be the international practices. However, local conditions should be taken into account to avoid undue stress of the limited resources available to countries with a limited nuclear power programme. This work reviews the current international nuclear safety and discusses the application of some international practices to the Brazilian situation, considering the peculiarities of the national nuclear power programme and the limitations of the available financial and human resources. (author)

  4. Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

    2002-02-01

    The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

  5. Expert system applications to nuclear plant for enhancement of productivity and performance

    International Nuclear Information System (INIS)

    Sun, B.; Cain, D.; Naser, J.; Colley, R.; Hirota, N.

    1988-01-01

    Expert systems, a major essence of the artificial intelligence (AI) technology, are referred to as computer software and hardware systems which are designed to capture and emulate the knowledge, reasoning, judgment, and to store the expertise of humans. Two parallel efforts are being performed at the Electric Power Research Institute (EPRI) to help the electric utility industry take advantage of the expert system technology. The first effort is the development of expert system building tools which are tailored to electric utility industry applications. The second effort is the development of expert system application prototypes. These two efforts complement each other. The application development tests the tools and identifies additional tool capabilities which are required. The tool development helps define the applications which can be successfully developed. This paper summarizes a number of research projects which are being performed at EPRI in both the areas of expert system building tool development and expert system applications to operations and maintenance. The AI technology as demonstrated by the development is being established as a credible technological tool for the electric utility industry. A challenge to transferring the expert systems technology to the utility industry is to gain utility users' acceptance of this modern information technology. To achieve successful technology transfer, the technology developers need to (1) understand the problems which can be addressed successfully using AI technology, (2) involve with users throughout the development and testing phases, and (3) demonstrate the benefits of the technology by the users

  6. Backfitting of the nuclear power plant Borssele. A practical application of the ALARA-principle

    International Nuclear Information System (INIS)

    Leurs, C.J.

    1998-01-01

    In two articles an overview is given of the adjustments for the title plant and how the radiation load of employees is kept as low as possible according to the newest insights of the ALARA-principle. In this article attention is paid to the results of the project 'Modifications' which comprises 16 system engineering modifications. The maximum attention for radiation protection resulted in a collective dose of circa 2500 millisievert, which is a factor 4 lower than the first estimation of the radiation load. 7 refs

  7. An interactive graphic simulator for garona nuclear power plant: development and applications

    International Nuclear Information System (INIS)

    Corcuera, P.; Garces, M.; Melara, J.; Gonzalez, J.; Lopez, J.V.

    1999-01-01

    As a result of a R and D project jointly undertaken by Nuclenor S.A. and the University of Cantabria, since the beginning of 1995 Santa Maria de Garona NPP holds its own plant transient and accident simulator for the training of its operators on Emergency Procedures Guides (EPG's). This paper describes the process followed in its development and the derived projects. This interactive graphic simulator is based on the MAAP computer code with an interface developed with DataViews software for X-Window terminals running under UNIX on a Hewlet Packard series 9000/712 workstation. The themarhydraulical code MAAP, with modifications to include all the controls and systems of the plant was chosen due to its capability to simulate primary system, containment and reactor building behavior during transients and accidents of any kind, including those beyond the design basis and also severe accidents. Besides, this code is currently being used for the PSA of the plant. The current configuration consists of several monitors that displays the systems and components situation and the safety parameters through the SPDS (Safety Parameter Display System) displays. With this design the simulator has fulfilled its initial main purpose of training operators on abnormal and emergency procedure guides, revealing as a very efficient and cost effective tool to accomplish this task. Furthermore it has been improved to visualize the real time plant data through the simulator displays. It is also possible to distribute the simulated data to any computer connected to the local area network (LAN). This feature has been applied successfully in the last emergency drills. Other benefits are derived from the fact that the same code is used for training and for the PSA. As an example of its flexibility, the simulator is now being used to validate the new SPDS displays designed to improve the man-machine interface and then it will serve to train the operators on them before their installation at the

  8. Overview on the different applications of probabilistic safety assessment for nuclear power plants

    International Nuclear Information System (INIS)

    Berg, Heinz-Peter

    2009-01-01

    Worldwide it can be recognised that the use of probabilistic safety assessment (PSA) in regulatory as well as operational decision-making is state of the art and seen as a successful development. Therefore, in most cases the regulator encourages the performance of PSAs to provide information to complement and support the defence in depth philosophy as well as operational configuration decisions. The main application of the PSA is still as part of integrated safety reviews, in particular in the frame of comprehensive (periodic) safety reviews. Other more specific applications areas of PSA are, among others, design evaluation, event analysis with aid of PSA, evaluation of technical specifications; risk-informed in-service inspection, risk monitoring and accident management. The extent of these applications vary from country to country but has been increasing during the last years. (orig.)

  9. Calcium aluminates for quick cesium trapping, application for nuclear power plants

    International Nuclear Information System (INIS)

    Capmas, A.; Dubourg, M.; Boch, P.

    1993-01-01

    It has recently been shown that cesium dissolved in water could be trapped in a solid structure by adding cementitious calcium aluminates and fume silica. Calcium aluminates are heat resistant and widely used as refractory products. Extensive studies on the rheological properties has been achieved. It is now possible to obtain flow properties to such an extent as to percolate a slurry through broken structures and give high mechanical strength in a short time. This along with the other properties of thermal shock resistance and cesium trapping makes a solution possible for nuclear building safety as a preventitive or a curative material. For example, at Chernobyl, this material could improve safety by remote casting techniques, construction of a structure which could serve as as ash tray under the coruim. Remotelly controlled equipment needed for this are in operation in more than 50 standardized PWR's. The equipment performs maintenance and inspection tasks with low radiation exposure

  10. Phytomonitoring of the genotoxicity of environment pollutants: An application to Armenian nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jin Kyu; Kim, Jin Hong [Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of); Aroutiounian, Rouben M.; Nebish, Anna A. [Yerevan State University, Yerevan (Armenia)

    2015-12-15

    Today the biosafety evaluation, a common problem of vital importance, is based on internationally proved test-systems, standards and techniques. The paradigm of biosafety includes multidisciplinary approach, a combination of physical, chemical and biological tests to monitor the environmental level of pollutants and needs to be improved by modern approaches. The genetic risk of environmental pollutions has long been studied by many researchers. In this study, used was the known sensitive plant test-system, clones of plant Tradescantia (spiderwort) able to detect gene mutations (frequency of mutational events and formation of micronuclei) in combination with chemical and, in some instances, with radiological measurements. In addition, male gametophyte generation of fruit trees was applied as bioindicators of genotoxicity. The obtained results did not show any significant increase along with wind direction. As for the male gametophyte assay, the fertility of the investigated fruit-trees near to NPP did not significantly differ from that of the control point. The influence of the NPP on the male generative system of the investigated taxa of fruit trees for the investigated year was not revealed. The system described needs to be expanded by species of interest (human) as there is a difficulty to transfer the revealed dose correlations to humans. The development of this idea includes various levels: population (epidemiological studies), individual, cellular, molecular (DNA), etc.

  11. Phytomonitoring of the genotoxicity of environment pollutants: An application to Armenian nuclear power plant

    International Nuclear Information System (INIS)

    Kim, Jin Kyu; Kim, Jin Hong; Aroutiounian, Rouben M.; Nebish, Anna A.

    2015-01-01

    Today the biosafety evaluation, a common problem of vital importance, is based on internationally proved test-systems, standards and techniques. The paradigm of biosafety includes multidisciplinary approach, a combination of physical, chemical and biological tests to monitor the environmental level of pollutants and needs to be improved by modern approaches. The genetic risk of environmental pollutions has long been studied by many researchers. In this study, used was the known sensitive plant test-system, clones of plant Tradescantia (spiderwort) able to detect gene mutations (frequency of mutational events and formation of micronuclei) in combination with chemical and, in some instances, with radiological measurements. In addition, male gametophyte generation of fruit trees was applied as bioindicators of genotoxicity. The obtained results did not show any significant increase along with wind direction. As for the male gametophyte assay, the fertility of the investigated fruit-trees near to NPP did not significantly differ from that of the control point. The influence of the NPP on the male generative system of the investigated taxa of fruit trees for the investigated year was not revealed. The system described needs to be expanded by species of interest (human) as there is a difficulty to transfer the revealed dose correlations to humans. The development of this idea includes various levels: population (epidemiological studies), individual, cellular, molecular (DNA), etc

  12. Development of nuclear plant Operation Management System

    Energy Technology Data Exchange (ETDEWEB)

    Koide, I.; Okada, T.; Ishida, K. [Chubu Electric Power Co. Inc., Nagoya (Japan)

    1998-09-01

    Recently it has become more important to detect a change in operational characteristics and to take appropriate corrective actions before it deteriorates to an incident in nuclear power plants. Therefore, aiming at earlier detection of a tendency change, swifter corrective actions and more effective application of operational data, we have developed Operation Management System which automatically acquires, accumulates and observes operational data of Hamaoka Nuclear Power Station through cycles. (author)

  13. Development of nuclear plant Operation Management System

    International Nuclear Information System (INIS)

    Koide, I.; Okada, T.; Ishida, K.

    1998-01-01

    Recently it has become more important to detect a change in operational characteristics and to take appropriate corrective actions before it deteriorates to an incident in nuclear power plants. Therefore, aiming at earlier detection of a tendency change, swifter corrective actions and more effective application of operational data, we have developed Operation Management System which automatically acquires, accumulates and observes operational data of Hamaoka Nuclear Power Station through cycles. (author)

  14. Safety targets for nuclear power plants

    International Nuclear Information System (INIS)

    Herttrich, P.M.

    1985-01-01

    By taking as an example the safety targets of the American nuclear energy authority US-NRC, this paper explains what is meant by global, quantitative safety targets for nuclear power plants and what expectations are associated with the selecton of such safety targets. It is shown how probabilistic methods can be an appropriate completion of proven deterministic methods and what are the sectors where their application may become important in future. (orig./HP) [de

  15. Partner of nuclear power plants

    International Nuclear Information System (INIS)

    Gribi, M.; Lauer, F.; Pauli, W.; Ruzek, W.

    1992-01-01

    Sulzer, the Swiss technology group, is a supplier of components and systems for nuclear power plants. Important parts of Swiss nuclear power stations, such as containments, reactor pressure vessels, primary pipings, are made in Winterthur. Sulzer Thermtec AG and some divisions of Sulzer Innotec focus their activities on servicing and backfitting nuclear power plants. The European market enjoys priority. New types of valves or systems are developed as economic solutions meeting more stringent criteria imposed by public authorities or arising from operating conditions. (orig.) [de

  16. AVISE, ageing anticipation methodology using expert judgement and stimulation. Application to a nuclear power plant component: the pressurizer

    International Nuclear Information System (INIS)

    Bouzaiene-Marle, L.

    2005-04-01

    This thesis deals with components ageing anticipation in the context of life cycle management. The proposed approach, called AVISE, allows the identification of potentials problems related to ageing, to measure the risks in terms of degradation probability and degradation consequences and gives the adequate solutions to stop or to postpone ageing. This research was undertaken in a particular industrial context, the nuclear industry. Equipments used in this context are specific and particularly reliable. These characteristics result in limited feedback (low number of failures). To compensate for this limited information, two solutions are proposed in this approach. The first solution that we can consider as a classical one consists in using expert judgement. The second one, more original, consists in using the operation feedback of 'similar' components. In order to apply these solutions and to obtain the anticipation results, a set of methodological tools was developed and tested in a real industrial application on a nuclear power plant component: the pressurizer. The first tool is a generic process for expert judgement, identified thanks to a comparison between eleven existing methods using expert judgement. Two methods based on expert stimulation and called STIMEX-IMDP and STIMEX-IPP were elaborated. A reference list of degradation mechanisms and a reference list of ageing effects were constructed and used in the method STIMEX-IMDP in order to help expert stimulation. Then, the developed approach proposes the use of belief networks to model and quantify the risks related to the potential degradations. Finally, the construction of a conceptual data model and specifications are given for the creation of an ageing database. The data to capitalize was identified on the basis of the research undertaken in this thesis. (author)

  17. Application perspectives of simulation techniques CFD in nuclear power plants; Perspectivas de aplicacion de tecnicas de modelado CFD en plantas nucleoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Galindo G, I. F., E-mail: igalindo@iie.org.mx [Instituto de Investigaciones Electricas, Reforma No. 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico)

    2013-10-15

    The scenarios simulation in nuclear power plants is usually carried out with system codes that are based on concentrated parameters networks. However situations exist in some components where the flow is predominantly 3-D, as they are the natural circulation, mixed and stratification phenomena. The simulation techniques of computational fluid dynamics (CFD) have the potential to simulate these flows numerically. The use of CFD simulations embraces many branches of the engineering and continues growing, however, in relation to its application with respect to the problems related with the safety in nuclear power plants, has a smaller development, although is accelerating quickly and is expected that in the future they play a more emphasized paper in the analyses. A main obstacle to be able to achieve a general acceptance of the CFD is that the simulations should have very complete validation studies, sometimes not available. In this article a general panorama of the state of the methods application CFD in nuclear power plants is presented and the problem associated to its routine application and acceptance, including the view point of the regulatory authorities. Application examples are revised in those that the CFD offers real benefits and are also presented two illustrative study cases of the application of CFD techniques. The case of a water recipient with a heat source in its interior, similar to spent fuel pool of a nuclear power plant is presented firstly; and later the case of the Boron dilution of a water volume that enters to a nuclear reactor is presented. We can conclude that the CFD technology represents a very important opportunity to improve the phenomena understanding with a strong component 3-D and to contribute in the uncertainty reduction. (Author)

  18. NEP Nuclear Power Plant, Units 1 and 2. License application, general and financial information

    International Nuclear Information System (INIS)

    1976-01-01

    A license application is presented for 2 pressurized water reactors at a proposed location in Charlestown RI. Each reactor will have a net capacity of 1150 MW. Cooling water will be supplied by the Atlantic Ocean. NEP-1 is scheduled for operation in 1983 and NEP-2 in 1985

  19. Video camera use at nuclear power plants

    International Nuclear Information System (INIS)

    Estabrook, M.L.; Langan, M.O.; Owen, D.E.

    1990-08-01

    A survey of US nuclear power plants was conducted to evaluate video camera use in plant operations, and determine equipment used and the benefits realized. Basic closed circuit television camera (CCTV) systems are described and video camera operation principles are reviewed. Plant approaches for implementing video camera use are discussed, as are equipment selection issues such as setting task objectives, radiation effects on cameras, and the use of disposal cameras. Specific plant applications are presented and the video equipment used is described. The benefits of video camera use --- mainly reduced radiation exposure and increased productivity --- are discussed and quantified. 15 refs., 6 figs

  20. Operation and maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Ackermann, G.

    1987-01-01

    This textbook gives a systematic introduction into the operational and maintenance activities in nuclear power plants with pressurized water reactors. Subjects: (1) Setup and operational behaviour of power reactors, (2) setup of nuclear power plants, (3) radiation protection and nuclear safety, (4) nuclear fuel, (5) constructional layout of nuclear power plants, (6) management, and (7) maintenance. 158 figs., 56 tabs