WorldWideScience

Sample records for developing nuclear plant

  1. SWOT of nuclear power plant sustainable development

    International Nuclear Information System (INIS)

    Abbaspour, M.; Ghazi, S.

    2008-01-01

    SWOT Analysis is a Useful tool that can he applied to most projects or business ventures. In this article we are going to examine major strengths, weaknesses, opportunities and threats of nuclear power plants in view of sustainable development. Nuclear power plants have already attained widespread recognition for its benefits in fossil pollution abatement, near-zero green house gas emission, price stability and security of energy supply. The impressive new development is that these virtues are now a cost -free bonus, because, in long run, nuclear energy has become an inexpensive way to generate electricity. Nuclear energy's pre-eminence economically and environmentally has two implications for government policy. First, governments should ensure that nuclear licensing and safety oversight arc not only rigorous but also efficient in facilitating timely development of advanced power plants. Second, governments should be bold incentivizing the transformation to clean energy economics, recognizing that such short-term stimulus will, in the case of nuclear plants, simply accelerate desirable changes that now have their own long-term momentum. The increased competitiveness of nuclear power plant is the result of cost reductions in all aspects of nuclear economics: Construction, financing, operations, waste management and decommissioning. Among the cost-lowering factors are the evolution to standardized reactor designs, shorter construction periods, new financing techniques, more efficient generation technologies, higher rates of reactor utilization, and longer plant lifetimes. U.S World Nuclear Association report shows that total electricity costs for power plant construction and operation were calculated at two interest rates. At 10%, midrange generating costs per kilowatt-hour are nuclear at 4 cents, coal at 4.7 cents and natural gas at 5.1 cent. At a 5% interest rate, mid-range costs per KWh fall to nuclear at 2.6 cents, coal at 3.7 cents and natural gas at 4.3 cents

  2. Development of nuclear power plant Risk Monitor

    International Nuclear Information System (INIS)

    Yang Xiaoming; Sun Jinlong; Ma Chao; Wang Lin; Gu Xiaohui; Bao Zhenli; Qu Yong; Zheng Hao

    2014-01-01

    Risk Monitor is a tool to monitor the real-time risk of a nuclear power plant for risk management and comprehensive decision-making, which has been widely used all over the world. The nuclear power plant Risk Monitor applies the real-time risk model with low-complicacy that could reflect the plant's actual configuration, automatically reads the plant's configuration information from the engineering system through the developed interface, and efficiently analyzes the plant's risk Dy the intelligent parallel-computing method in order to provide the risk basement for the safety management of nuclear power plant. This paper generally introduces the background, architecture, functions and key technical features of a nuclear power plant Risk Monitor, and validates the risk result, which could well reflect the plant's risk information and has a significant practical value. (authors)

  3. Nuclear plant analyzer development at INEL

    International Nuclear Information System (INIS)

    Laats, E.T.; Russell, K.D.; Stewart, H.D.

    1983-01-01

    The Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC) has sponsored development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes the status of the NPA project at the INEL after one year of development. When completed, the NPA will be an integrated network of analytical tools for performing reactor plant analyses. Development of the NPA in FY-1983 progressed along two parallel pathways; namely, conceptual planning and software development. Regarding NPA planning, and extensive effort was conducted to define the function requirements of the NPA, conceptual design, and hardware needs. Regarding software development conducted in FY-1983, all development was aimed toward demonstrating the basic concept and feasibility of the NPA. Nearly all software was developed and resides on the INEL twin Control Data Corporation 176 mainframe computers

  4. Appliance of software engineering in development of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Baek, Y. W.; Kim, H. C.; Yun, C. [Chungnam National Univ., Taejon (Korea, Republic of); Kim, B. R. [KINS, Taejon (Korea, Republic of)

    1999-10-01

    Application of computer technology in nuclear power plant is also a necessary transformation as in other industry fields. But until now, application of software technology was not wide-spread because of its potential effect to safety in nuclear field. It is an urgent theme to develop evaluation guide and regulation techniques to guarantee safety, reliability and quality assurance. To meet these changes, techniques for development and operation should be enhanced to ensure the quality of software systems. In this study, we show the difference between waterfall model and software life-cycle needed in development of nuclear power plant and propose the consistent framework needed in development of instrumentation and control system of nuclear power plant.

  5. Appliance of software engineering in development of nuclear power plant

    International Nuclear Information System (INIS)

    Baek, Y. W.; Kim, H. C.; Yun, C.; Kim, B. R.

    1999-01-01

    Application of computer technology in nuclear power plant is also a necessary transformation as in other industry fields. But until now, application of software technology was not wide-spread because of its potential effect to safety in nuclear field. It is an urgent theme to develop evaluation guide and regulation techniques to guarantee safety, reliability and quality assurance. To meet these changes, techniques for development and operation should be enhanced to ensure the quality of software systems. In this study, we show the difference between waterfall model and software life-cycle needed in development of nuclear power plant and propose the consistent framework needed in development of instrumentation and control system of nuclear power plant

  6. Engineering development in nuclear power plant construction

    International Nuclear Information System (INIS)

    Guenther, P.

    1979-01-01

    Proceeding from the up-to-now experience in the erection of nuclear power stations, especially of the first and second unit of the Greifswald nuclear power plant, the following essential aspects of the development of constructional engineering are discussed: (1) constructional features and criteria, (2) organizational management, (3) current status and problems in prelimary operations, and (4) possibilities of further expenditure reductions in constructing nuclear power stations

  7. 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

  8. Development of nuclear power plants database system, (2)

    International Nuclear Information System (INIS)

    Izumi, Fumio; Ichikawa, Michio

    1984-06-01

    A nuclear power plant data base system has been developed. The data base involves a large amount of safety design informations for nuclear power plants on operating and planning stage in Japan. The informations, if necessary, can be searched for at high speed by use of this system. The present report is an user's guide for access to the informations utilizing display unit of the JAERI computer network system. (author)

  9. Nuclear Power Plants and Sustainable Development on a Liberalized Market

    International Nuclear Information System (INIS)

    Androcec, I.; Stanic, Z.; Tomsic, Z.

    2002-01-01

    Finding a way to generate electricity so as to satisfy the terms of sustainable development of the entire society is the only way which will secure safe energy future. If we talk about energy in the context of sustainable development, one of the most important element is environmental protection. Since CO 2 emissions stemming from electricity generation have predominant impact on climate change, one of the options for reducing emissions is the use of fuels without carbon, such as e.g. nuclear fuel. The future of nuclear power plants was considered in view of: nuclear fuel supply; potential impact of fuel cycle on environment, power plant operation, decommissioning and secondary products from electricity generation; and the entire nuclear power plant economy. Nuclear power plants were also examined in the context of the Kyoto Protocol stipulating reduction of greenhouse gases emissions. Nuclear power plants can not reduce CO 2 emissions in a short-term because they already operate with maximum output, but in a long-run they can play a significant role. This paper is aiming to analyse the role of nuclear power plants in long term environmental sustainability in electricity sector reform (liberalisation, deregulation, privatisation) in small or medium sized power supply systems. Nuclear power plants are associated with certain environmental aspects which will be taken into account. A comparison will be made through externalities with other energy resources, especially fossil fuels, which are prevailing energy resources, considering possible use of nuclear power plants in the countries with small and medium-size grids. It will be given an example of the role of NPP Krsko on air emissions reduction in Croatia. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-12-15

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

  11. The Role of Nuclear Power Plants in the Development of a Country

    International Nuclear Information System (INIS)

    Cintra do Prado, L.

    1966-01-01

    Nuclear power plants oan contribute to the economic development of a country in two ways - as generators of power and as stimuli for the growth of new national industries. Some countries build nuclear power plants because other sources of cheap power are lacking. Other countries engage in nuclear activities such as the production of nuclear components and the purification of reactor materials before there is an immediate need for nuclear power in an attempt to plan for future national requirements and to create a nuclear export industry. A country can also import all or nearly all the components needed for the construction of nuclear power plants. In this case the importing country enjoys the benefits of facilities generating power without the advantages of a national nuclear industry. Industrialised countries generally find this solution undesirable save in exceptional circumstances, for example in the initial stages of a nuclear programme or in the case of specific nuclear components. Developing countries can also aim at a phased introduction of nuclear energy and try to combine the advantages of nuclear power production and the development of a national nuclear industry. Thus, in addition to the inherent advantages of nuclear plants as sources of electricity there are various ways in which the establishment of such plants can stimulate industry, namely through the use of nuclear and other ores utilizable in reactors, the promotion of ore-exploration activities, and the development of transformation industries

  12. The Role of Nuclear Power Plants in the Development of a Country

    Energy Technology Data Exchange (ETDEWEB)

    Cintra do Prado, L. [Brazilian Nuclear Energy Commission (Brazil)

    1966-07-01

    Nuclear power plants oan contribute to the economic development of a country in two ways - as generators of power and as stimuli for the growth of new national industries. Some countries build nuclear power plants because other sources of cheap power are lacking. Other countries engage in nuclear activities such as the production of nuclear components and the purification of reactor materials before there is an immediate need for nuclear power in an attempt to plan for future national requirements and to create a nuclear export industry. A country can also import all or nearly all the components needed for the construction of nuclear power plants. In this case the importing country enjoys the benefits of facilities generating power without the advantages of a national nuclear industry. Industrialised countries generally find this solution undesirable save in exceptional circumstances, for example in the initial stages of a nuclear programme or in the case of specific nuclear components. Developing countries can also aim at a phased introduction of nuclear energy and try to combine the advantages of nuclear power production and the development of a national nuclear industry. Thus, in addition to the inherent advantages of nuclear plants as sources of electricity there are various ways in which the establishment of such plants can stimulate industry, namely through the use of nuclear and other ores utilizable in reactors, the promotion of ore-exploration activities, and the development of transformation industries.

  13. Development of a nuclear plant analyzer (NPA)

    International Nuclear Information System (INIS)

    De Vlaminck, M.; Mampaey, L.; Vanhoenacker, L.; Bastenaire, F.

    1990-01-01

    A Nuclear Plant Analyzer has been developed by TRACTABEL. Three distinct functional units make up the Nuclear Plant Analyser, a model builder, a run time unit and an analysis unit. The model builder is intended to build simulation models which describe on the one hand the geometric structure and initial conditions of a given plant and on the other hand command control logics and reactor protection systems. The run time unit carries out dialog between the user and the thermal-hydraulic code. The analysis unit is aimed at deep analyzing of the transient results. The model builder is being tested in the framework of the International Standard Problem ISP-26, which is the simulation of a LOCA on the Japanese ROSA facility

  14. Development of a decommissioning plan for nuclear power plant 'Krsko'

    International Nuclear Information System (INIS)

    Tankosic, Djurica; Fink, Kresimir

    1991-01-01

    Nuclear Power Plant 'Krsko' (NEK), is the only nuclear power plant in Yugoslavia, is a two-loop, Westinghouse-design, pressurized water reactor rated at 632 MWe. When NEK applied for an operating license in 1981, it did not have to explain how the plant would be decommissioned and decommissioning provisions were not part of the licensing process. Faced with mounting opposition to nuclear power and a real threat that the plant would be shut down, the plant management developed a Mission Plan for resolving the decommissioning problem. The Mission Plan calls for a preliminary decommissioning plan to be prepared and submitted to the local regulatory body before the end of 1992

  15. 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.

  16. 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.

  17. Human resource development for the new nuclear power plant unit in Armenia

    International Nuclear Information System (INIS)

    Gevorgyan, A.; Galstyan, A.; Donovan, M.

    2008-01-01

    This paper presents a discussion of a study to define the programs for development of the human resource infrastructure needed for a new nuclear power plant unit in the Republic of Armenia. While Armenia has a workforce experienced in operation and regulation of a nuclear power plant (NPP), a significant portion of the current Armenia Nuclear Power Plant (ANPP) workforce is approaching retirement age and will not be available for the new plant. The Government of Armenia is performing a human resource infrastructure study in cooperation with the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), sponsored by the JAEA. The study of Human Resource Development for Armenia uses the INPRO methodology for assessment of human resources. The results of this study will provide the basis for decisions on human resource development programs for nuclear power in Armenia and provide a model for countries with the limited resources that are working to develop nuclear energy in the future. (authors)

  18. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim, Yun Jae; Choi, Jae Boong [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2002-03-15

    This project focuses on developing reliable life evaluation technology for nuclear power plant components, and is divided into two parts, development of a life evaluation system for nuclear pressure vessels and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered in this project: defect assessment method for steam generator tubes, development of fatigue monitoring system, assessment of corroded pipes, domestic round robin analysis for constructing P-T limit curve for RPV, development of probabilistic integrity assessment technique, effect of aging on strength of dissimilar welds, applicability of LBB to cast stainless steel, and development of probabilistic piping fracture mechanics.

  19. Development on database for foreign nuclear power plants

    International Nuclear Information System (INIS)

    Okuda, Yasunori; Yanagi, Chihiro

    1999-01-01

    The Nuclear Information Project in Institute of Nuclear Technology, Institute of Nuclear Safety Systems, Inc. (INSS) has been carrying out two activities related to technical information about nuclear power plants. The first is collection and analysis of accidents and incidents (troubles) of nuclear power plants in U.S.A. and West Europe and making draft of action proposals. The second is collection of main laws, government ordinances, regulatory guides, standard and domestic and international technical news connected with nuclear power plants. This report describes these two data bases about nuclear power plants details. (author)

  20. Support system development for evacuation plan decision in nuclear plant disaster

    International Nuclear Information System (INIS)

    Fujita, Masahiko; Takayama, Jun-ichi; Nakayama, Sho-ichiro; Ushiba, Takashi

    2011-01-01

    These days, our interest in nuclear plant accidents has increased, and civic actions for them have also been activated. Therefore, improvement of the disaster prevention planning to nuclear plant accidents is requested. In this study, we developed a microscopic traffic simulation system for evacuation plan near the nuclear plant as a system which supports to examine the disaster prevention planning, and applied the system to Kashiwazaki-Kariwa nuclear plant area. Furthermore, the risk of each region near the nuclear plant disaster from the viewpoint of wind direction and the population was considered, the importance of each evacuation simulation was examined. As a result, we found that the present plan Kashiwazaki-Kariwa made has the problem on evacuation routes and others. (author)

  1. 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)

  2. 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)

  3. Development of web based performance analysis program for nuclear power plant turbine cycle

    International Nuclear Information System (INIS)

    Park, Hoon; Yu, Seung Kyu; Kim, Seong Kun; Ji, Moon Hak; Choi, Kwang Hee; Hong, Seong Ryeol

    2002-01-01

    Performance improvement of turbine cycle affects economic operation of nuclear power plant. We developed performance analysis system for nuclear power plant turbine cycle. The system is based on PTC (Performance Test Code), that is estimation standard of nuclear power plant performance. The system is developed using Java Web-Start and JSP(Java Server Page)

  4. Development of instructors for nuclear power plant personnel training

    International Nuclear Information System (INIS)

    2004-06-01

    In 1996 the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation, A Guidebook, which provides guidance with respect to development, implementation and evaluation of training programmes. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further details concerning the development of instructors for NPP personnel training. The quality of nuclear power plant personnel training is strongly dependent on the availability of competent instructors. Instructors must have a comprehensive practical as well as theoretical understanding of all aspects of the subjects being taught and the relationship of the subject to nuclear plant operation. Instructors should have the appropriate knowledge, skills and attitudes (KSAs) in their assigned areas of responsibility. They should thoroughly understand all aspects of the contents of the training programmes and the relationship between these contents and overall plant operation. This means that they should be technically competent and show credibility with the trainees and other plant personnel. In addition, the instructors should be familiar with the basics of adult learning and a systematic approach to training, and should have adequate instructional and assessment skills. This TECDOC provides practical guidance on various aspects of instructor selection, development and deployment, by quoting actual examples from different countries. It highlights the importance of having an appropriate training policy, especially considering the various organisational arrangements that exist in different utilities/countries. This should result in: plant performance improvement, improved human performance, meeting goals and objectives of the business (quality, safety, productivity), and improving training programs. This publication is available in two formats - as a conventional printed

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

    International Nuclear Information System (INIS)

    Tsukune, Hideo; Hirukawa, Hirohisa; Kitagaki, Kosei; Liu, Yunhui; Onda, Hiromu; Nakamura, Akira

    1994-01-01

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

  6. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

    2001-03-15

    This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

  7. Development of robots for nuclear power plants

    International Nuclear Information System (INIS)

    Sasaki, Masayoshi

    1982-01-01

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

  8. Infrastructure development assistance modeling for nuclear power plant

    International Nuclear Information System (INIS)

    Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M.

    2012-01-01

    The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task would be to

  9. Infrastructure development assistance modeling for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M. [Korea Hydro and Nuclear Power Co., LTD, 23, 106 gil, Yeongdong-daero, Gangnam-gu, 153-791 (Korea, Republic of)

    2012-07-01

    The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task

  10. Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Laats, E.T.

    1986-10-01

    The Nuclear Plant Analyzer (NPA) is a state-of-the-art safety analysis and engineering tool being used to address key nuclear power plant safety issues. Under the sponsorship of the US Nuclear Regulatory Commission (NRC), the NPA has been developed to integrate the NRC's computerized reactor behavior simulation codes such as RELAP5, TRAC-BWR and TRAC-PWR, with well-developed computer color graphics programs and large repositories of reactor design and experimental data. An important feature of the NPA is the capability to allow an analyst to redirect a RELAP5 or TRAC calculation as it progresses through its simulated scenario. The analyst can have the same power plant control capabilities as the operator of an actual plant. The NPA resides on the dual Control Data Corporation Cyber 176 mainframe computers at the Idaho National Engineering Laboratory and Cray-1S computers at the Los Alamos National Laboratory (LANL) and Kirtland Air Force Weapons Laboratory (KAFWL)

  11. Objectives for the development of advanced nuclear plants

    International Nuclear Information System (INIS)

    1993-01-01

    The scope of this report is to reiterate the broad objectives for the development of advanced nuclear plants, to set forth some related subobjectives and to propose some universal goals for the development programmes. The majority of these can be categorized under the headings of enhancing safety, improving reliability and gaining better economics. These categories are used in the report followed by additional categories considered to be important within the global framework intended. Additional broad objectives appear unlikely but more subobjectives may become evident as time progresses and the need arises to express them in the intended more global framework. The goals also may change. The scope is therefore a set of objectives for development of advanced nuclear plants. The objectives are believed to be universally acceptable; they have been reviewed on that basis. 13 refs

  12. Development of support system for nuclear power plant piping

    International Nuclear Information System (INIS)

    Horino, Satoshi

    1987-01-01

    Ishikawajima-Harima Heavy Industries Co., Ltd. has advanced the development of Integrated Nuclear Plant Piping System (INUPPS) for nuclear power plants since 1980, and continued its improvement up to now. This time as its component, a piping support system (PISUP) has been developed. The piping support system deals with the structures such as piping supports and the stands for maintenance and inspection, and as for standard supporting structures, it builds up automatically the structures including the selection of optimum members by utilizing the standard patterns in cooperation with the piping design system including piping stress analysis. As for the supporting structures deviating from the standard, by amending a part of the standard patterns in dialogue from, structures can be built up. By using the data produced in this way, this system draws up consistently a design book, production management data and so on. From the viewpoint of safety, particular consideration is given to the aseismatic capability of nuclear power plants, and piping is fundamentally designed regidly to avoid resonance. It is necessary to make piping supports so as to have sufficient strength and rigidity. The features of the design of piping supports for nuclear power plant, the basic concept of piping support system, the constitution of the software and hardware, the standard patterns and the structural patterns of piping support system and so on are described. (Kako, I.)

  13. 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

  14. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    Science.gov (United States)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  15. Toshiba's developments on construction techniques of nuclear power plants

    International Nuclear Information System (INIS)

    Hayashi, Y.; Itoh, N.

    1987-01-01

    Reliable and economic energy supplies are fundamental requirements of energy policies in Japan. To accomplish these needs, nuclear power plants are being increased in Japan. In recent years, construction cost increases and schedule extensions have affected the capital cost of nuclear energy, compared with fossil power plants, due to lower costs of oil and coal. On the other hand, several severe regulations have been applied to nuclear power plant designs. High-quality and cooperative engineering and harmonized design of equipment and parts are strongly required. Therefore, reduced construction costs and scheduling, as well as higher quality and reliability, are the most important items for nuclear industry. Toshiba has developed new construction techniques, as well as design and engineering tools for control and management, that demonstrate the positive results achieved in the shorter construction period of 1100-MW(electric) nuclear power plants. The normal construction period so far is 64 months, whereas the current construction period is 52 months. (New construction techniques are partially applied). In future years, the construction period will be lowered to 48 months. (New construction techniques are fully applied). A construction period is defined as time from the start of rock inspection to the start of commercial operation

  16. Development of new nuclear power plants in the Republic of Korea. Annex 4

    International Nuclear Information System (INIS)

    Kim, Jung-Cha; Park, Kee-Cheol

    2002-01-01

    Nuclear power in Korea is one of our major energy sources, which accounting for approximately 50 % of the total share of electric generation using the safest and most stable methods. Based on the outstanding performance of nuclear power generation, Korea plans to construct eight (8) new nuclear power plants to maintain nuclear power as a major contributor to the national energy mix by 2014. In order to ensure that nuclear power plants are safer and more economical than any conventional electric power sources, KEPCO has developed the improved Korea Standard Nuclear Power Plant (KSNP + ) and the Korea Next Generation Reactor (KNGR) by utilizing over 30 years of expertise and learned technologies gained from construction, design, operation of sixteen nuclear units. Recently, KEPCO has developed its own project management tool, the Nuclear Project Control System (NPCS), which integrates schedule, material, cost, drawing and documentation into a computerized system, to be utilized for construction of the nuclear power plants. This paper summarizes KEPCO's various efforts for design improvement of KSNP + and KNGR in terms of performance and economic viability for construction of new nuclear power plants in Korea. (author)

  17. 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

  18. 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)

  19. Technology development on the assessment of structural integrity of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jeong Moon; Choun, Y. S.; Choi, I. K. and others

    1999-04-01

    Nuclear power plants in Korea show drop off in their performance and safety margin as the age of plants increase. The reevaluation of Kori-1 Unit on its performance and safety for life extension is expected in the near future. However, technologies and information related are insufficient to quantitatively estimate them. The final goal of this study is to develop the basic testing and evaluation techniques related with structural integrity of important nuclear equipment and structures. A part of the study includes development of equipment qualification technique. To ensure the structural integrity of structures, systems, and equipment in nuclear power plants, the following 5 research tasks were performed in the first year. - Analysis of dynamic characteristics of reactor internals - Analysis of engineering characteristics of instrumental earthquakes recorded in Korea - Analysis of ultimate pressure capacity and failure mode of containments building - Development of advanced NDE techniques using ultrasonic resonance scattering - Development of equipment qualification technique against vibration aging. These technologies developed in this study can be used to ensure the structural safety of operational nuclear power plants, and for the long-term life management. (author)

  20. Development of halogen-free flame-retardant cable for nuclear power plant

    International Nuclear Information System (INIS)

    Ishii, Nobuhisa; Morii, Akira; Fujimura, Shunichi

    1991-01-01

    Conventional flame-retardant cables release a large amount of corrosive and toxic gases and also smoke during combustion on fire. Cables covered with halogen-free flame-retardant material, containing no halogen in it, have been developed to reduce generation of such gases and smoke, and already used in telecommunication plant, subway and shipboard applications. In the case of nuclear power plant application, cable covering materials should also have radiation resistance and other properties including long-term physical stability. We have developed halogen-free flame-retardant cables for nuclear power plant with sufficient flame retardancy, radiation resistance, and environmental resistance including steam-exposure resistance, all of which are in accordance with Japanese specifications for nuclear cables, and with characteristics as low corrosiveness, low toxicity, and low smoke evolution. (author)

  1. Research and development towards decommissioning of Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Minato, Kazuo

    2013-01-01

    Towards the decommissioning of Fukushima Daiichi Nuclear Power Plants, science-based research and development is important and useful, as well as technology and engineering development. Research and development activities based on radiation chemistry, radiochemistry, thermodynamics, etc., have contributed to safe and efficient decommissioning of the plants. (author)

  2. Development of bus duct inspection robot at nuclear power plant

    International Nuclear Information System (INIS)

    Hamada, Mamoru; Hoshi, Teruaki; Komura, Yoshinari

    2017-01-01

    Under the present situation, nuclear power plant has some places which are inspected with difficulty or not inspected due to narrowness or physical restriction, when carrying out periodical inspection. The subject of our research and development is to improve the accuracy of inspection and also to save labor (liberation from distress work of the worker) by applying a robot technology to the periodical inspection of the nuclear power plant. As a specific example, we report that developed robot can inspect inside the narrow space of Isolated Phase Bus ducts, which connect between a turbine generator and the main transformer. (author)

  3. Developing new methodology for nuclear power plants vulnerability assessment

    International Nuclear Information System (INIS)

    Kostadinov, Venceslav

    2011-01-01

    new methodology and solution methods for vulnerability assessment can help the overall national energy sector to identify and understand the terrorist threats to and vulnerabilities of its critical infrastructure. Moreover, adopted methodology could help national regulators and agencies to develop and implement a vulnerability awareness and education programs for their critical assets to enhance the security and a safe operation of the entire energy infrastructure. New methods can also assist nuclear power plants to develop, validate, and disseminate assessment and surveys of new efficient countermeasures. Consequently, concise description of developed new quantitative method and adapted new methodology for nuclear regulatory vulnerability assessment of nuclear power plants are presented.

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

    International Nuclear Information System (INIS)

    Salo, I.; Svensson, Ola

    2001-11-01

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

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

    International Nuclear Information System (INIS)

    Salo, I.; Svenson, O.

    2001-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-11-01

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

  7. New nuclear plant development - balancing localization with competitiveness

    International Nuclear Information System (INIS)

    Caplan, M.; Thompson, T.S.

    2014-01-01

    Nuclear power plants are large infrastructure projects that require government support and approval. This paper will highlight and contrast the larger, mostly government-desired, nuclear program localization objectives with the more utility-specific requirements for successful project implementation. Governments are concerned about sustainable industrial development, particularly manufacturing, and job creation while utilities are focused on delivering reliable electricity to consumers at the lowest cost. Numerous countries emphasize local content as a key requirement when procuring a station. For countries like China and Korea that have large programs, their strategy has been to localize to the point of having their own indigenous design. However, developing a workable localization strategy that truly benefits the local economy for others including existing nuclear markets like Canada, the UK, South Africa and Brazil as well as in newly developing markets such as Vietnam and Malaysia is more challenging. These countries may not look to indigenize a new design, rather they would localize elements of the nuclear program that best fit their strengths. The paper will discuss the issues related to developing successful localization and industrialization strategies in a changing nuclear world. (author)

  8. New nuclear plant development - balancing localization with competitiveness

    Energy Technology Data Exchange (ETDEWEB)

    Caplan, M.; Thompson, T.S. [MZ Consulting Inc., ON (Canada)

    2014-07-01

    Nuclear power plants are large infrastructure projects that require government support and approval. This paper will highlight and contrast the larger, mostly government-desired, nuclear program localization objectives with the more utility-specific requirements for successful project implementation. Governments are concerned about sustainable industrial development, particularly manufacturing, and job creation while utilities are focused on delivering reliable electricity to consumers at the lowest cost. Numerous countries emphasize local content as a key requirement when procuring a station. For countries like China and Korea that have large programs, their strategy has been to localize to the point of having their own indigenous design. However, developing a workable localization strategy that truly benefits the local economy for others including existing nuclear markets like Canada, the UK, South Africa and Brazil as well as in newly developing markets such as Vietnam and Malaysia is more challenging. These countries may not look to indigenize a new design, rather they would localize elements of the nuclear program that best fit their strengths. The paper will discuss the issues related to developing successful localization and industrialization strategies in a changing nuclear world. (author)

  9. Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Laats, E.T.; Beelman, R.J.; Charlton, T.R.; Hampton, N.L.; Burtt, J.D.

    1985-01-01

    The Nuclear Plant Analyzer (NPA) is a state-of-the-art safety analysis and engineering tool being used to address key nuclear power plant safety issues. The NPA has been developed to integrate the NRC's computerized reactor behavior simulation codes such as RELAP5, TRAC-BWR, and TRAC-PWR, with well-developed computer graphics programs and large repositories of reactor design and experimental data. An important feature of the NAP is the capability to allow an analyst to redirect a RELAP5 or TRAC calculation as it progresses through its simulated scenario. The analyst can have the same power plant control capabilities as the operator of an actual plant. The NPA resides on the dual CDS Cyber-176 mainframe computers at the INEL and is being converted to operate on a Cray-1S computer at the LANL. The subject of this paper is the program conducted at the INEL

  10. Development trends for diagnostic systems in nuclear power plants

    International Nuclear Information System (INIS)

    Kunze, U.; Pohl, U.

    1998-01-01

    Monitoring systems used in nuclear power plants have made remarkable progress over the past four or five years. Development has followed the trends and changes in philosophy for the purpose of monitoring systems in nuclear power plants: They are no longer expected to fulfill only safety tasks, the plant personnel require information on which to base condition-oriented maintenance. A new generation of monitoring and diagnostic systems has been developed by Siemens recently. This new generation, called Series '95, is PC-based. An overview is given for the KUeS '95 loose parts diagnostic system, the SUeS '95 vibration monitoring system, the FLUeS leak detection system and the SIPLUG valve diagnostics system. The objectives behind the development of these new systems are both safety-related and economic. The new systems improve the reliability and quality of monitoring techniques and incorporate better detection and diagnostic capabilities. Progress has also been made in automation of the systems so as to reduce routine work, give higher sensitivity for the monitoring task and reduce the scope of maintenance. (author)

  11. The Communities' research and development programme on decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    This is the first progress report of the European Community's programme (1979-1983) of research on the decommissioning of nuclear power plants. It shows the status of the programme on 31 December 1980. The programme seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific waste materials: steel, concrete and graphite; large transport containers for radioactive was produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive wastes arising from decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

  12. Developing an economic performance system to enhance nuclear power plant competitiveness

    International Nuclear Information System (INIS)

    2002-01-01

    In 1999 about 16% of the world's electricity was produced by nuclear power, and the total worldwide operating experience of nuclear power plants was over 9200 reactor-years. Some 16 countries are dependent on nuclear power for more than 25% of their electricity generation. In some countries deregulation of the electricity market has either happened or is currently ongoing, while in others it is planned for the future. Nevertheless, many countries are already facing open electricity markets and operating costs are under unprecedented pressure, with competition expected to come soon to the nuclear industry worldwide. To a certain extent, however, the industry has already prepared or is currently preparing to face competition. This report is primarily intended for nuclear power plant and utility managers. It discusses the means and principal issues for the development of the nuclear economic performance international system (NEPIS), which should enhance nuclear power plant competitiveness. The following issues are addressed: The major transformations occurring in the electricity generation industry that require reductions in operations and maintenance costs at nuclear utilities; The methods that nuclear plant management use to identify and justify the economic optimum level of a plant and its use of resources; The value of collecting cost and performance data and the analysis techniques that use that data; The cost data required to be collected; The difficulty of collecting data with existing cost accounting systems; The new cost accounting and collection systems that will be required, The cost effectiveness of the overall process. This report also presents the preliminary results of a pilot project that was established to collect cost data on a few nuclear power plants and was used to verify the adequacy of the definitions and terminology set for NEPIS

  13. Current developments in mechanized non-destructive testing in nuclear power plants

    International Nuclear Information System (INIS)

    Zeilinger, R.

    2008-01-01

    Nuclear power plants require frequent in-service activities to be carried out conscientiously in areas potentially hazardous to human operators (because of the associated radiation exposure), such as non-destructive testing of pressurized components of the steam system. Locations to be inspected in this way include the reactor pressure vessel, core internals, steam generators, pressurizers, and pipes. The codes to be used as a basis of these inspections demand high absolute positioning and repeating accuracy. These requirements can be met by mechanized test procedures. Accordingly, many new applications of, mostly mobile, robots have been developed over the past few years. The innovative control and sensor systems for stationary and mobile robots now on the market offer a potential for economic application in a large number of new areas in inspection, maintenance and service in nuclear power plants. More progress in this area is expected for the near future. Areva NP founded the new NDT Center, NETEC (Non-destructive Examination Technical Center), as a global technical center for non-destructive materials testing. NETEC is to advance research and development of all basic NDT technologies, robotics included. For many years, intelligeNDT has offered solutions and products for a variety of inspection and testing purposes and locations in nuclear power plants and is involved in continuous further development of the experience collected in nuclear power plants on the spot. (orig.)

  14. Development of automatic inspection robot for nuclear power plants

    International Nuclear Information System (INIS)

    Yamada, K.; Suzuki, K.; Saitoh, K.; Sakaki, T.; Ohe, Y.; Mizutani, T.; Segawa, M.; Kubo, K.

    1987-01-01

    This robot system has been developed for automatic inspection of nuclear power plants. The system configuration is composed of vehicle that runs on monorail, the sensors on the vehicle, an image processer that processes the image information from the sensors, a computer that creates the inspection planning of the robot and an operation panel. This system has two main features, the first is the robot control system. The vehicle and the sensors are controlled by the output data calculated in the computer with the three dimensional plant data. The malfunction is recognized by the combination of the results of image processing, information from the microphone and infrared camera. Tests for a prototype automatic inspection robot system have been performed in the simulated main steam piping room of a nuclear power plant

  15. IAEA activities in technology development for advanced water-cooled nuclear power plants

    International Nuclear Information System (INIS)

    Juhn, Poong Eil; Kupitz, Juergen; Cleveland, John; Lyon, Robert; Park, Je Won

    2003-01-01

    As part of its Nuclear Power Programme, the IAEA conducts activities that support international information exchange, co-operative research and technology assessments and advancements with the goal of improving the reliability, safety and economics of advanced water-cooled nuclear power plants. These activities are conducted based on the advice, and with the support, of the IAEA Department of Nuclear Energy's Technical Working Groups on Advanced Technologies for Light Water Reactors (LWRs) and Heavy Water Reactors (HWRs). Assessments of projected electricity generation costs for new nuclear plants have shown that design organizations are challenged to develop advanced designs with lower capital costs and short construction times, and sizes, including not only large evolutionary plants but also small and medium size plants, appropriate to grid capacity and owner financial investment capability. To achieve competitive costs, both proven means and new approaches should be implemented. The IAEA conducts activities in technology development that support achievement of improved economics of water-cooled nuclear power plants (NPPs). These include fostering information sharing and cooperative research in thermo-hydraulics code validation; examination of natural circulation phenomena, modelling and the reliability of passive systems that utilize natural circulation; establishment of a thermo-physical properties data base; improved inspection and diagnostic techniques for pressure tubes of HWRs; and collection and balanced reporting from recent construction and commissioning experiences with evolutionary water-cooled NPPs. The IAEA also periodically publishes Status Reports on global development of advanced designs. (author)

  16. Development of knowledge acquisition methods for knowledge base construction for autonomous nuclear plant

    Energy Technology Data Exchange (ETDEWEB)

    Sasajima, M.; Kitamura, Y.; Mizoguchi, R. [Osaka Univ., Ibaraki (Japan). Inst. of Scientific and Industrial Research; Yoshikawa, S.

    1994-03-01

    This report describes a development of an ontology for computerized representation of behaviors and functions of number power plants. This ontology also enables computers to predict plant behaviors under assumed changes of boundary conditions and to derive cause identification suggestions of observed anomalies, as well as to represent functions and behaviors. Technical requirements in this development were recognized as clarified distinguishment of functions from behaviors and efficient plant behavior reasoning, and these have been successfully attained. The purpose of this development is to achieve knowledge sharing between human and automized instrumentation and control system about nuclear plant functions and behaviors, to realize cooperation of human and automized system for safe and cost acceptable nuclear plant operation. (author)

  17. The critical issue of nuclear power plant safety in developing countries

    International Nuclear Information System (INIS)

    Rosen, M.

    1977-01-01

    A little more than a decade from now, large commercial nuclear power facilities will be in operation in almost 40 countries, of which approximately one-half are presently considered industrially less developed. Ambitious nuclear programmes coupled with minimal and frequently under-staffed regulatory and utility organizations are only one aspect of the difficulties related to the safety of nuclear plants that face these developing countries. Inherent problems of meeting current safety standards and requirements for the significantly non-standard nuclear power plant exports can be compounded by financial considerations that may lead to purchases of reactors of various types, from more than one supplier country and with different safety standards and requirements. An examination of these issues points to the necessity and opportunity for effective action which could include provision for adequate funding for safety considerations in the purchase contract, and for sufficient regulatory assistance and training from the developed countries. The article will introduce the topic, discuss specific examples, and offer some suggestions. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  20. Development of EDG Engine Condition Diagnosis Logic in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Byoung Oh; Choi, Kwang Hee; Lee, Sang Guk

    2012-01-01

    Through benchmarking using the excellent record of the nuclear power plants under operation in the United States and Europe and with the continuous development of nuclear-related technology, the Korea Hydro and Nuclear Power Co., LTD (KHNP) reached an average planned preventive maintenance period of 29.6 days in 2009. In addition, KHNP plans to reduce the planned preventive maintenance period at Korea standard nuclear plants (KSNPs) from 29.6 days to less than 21 days by 2014 through a combination of domestic research and development (R and D) and the introduction of the technical know-how applied in the very best overseas nuclear power plants (NPPs). Accordingly, it is necessary to reduce the inspection and maintenance periods of an emergency diesel generator (EDG), which are currently set in the planned preventive maintenance period. If the condition-based predictive maintenance (CBM) technology is applied to EDG engines, the maintenance period of an EDG will be shortened because engine maintenance is accomplished according to the engine condition under this plan. In this study, in the series of CBM program developments which will be applied to EDG engines, the development results of condition diagnosis logic to be applied to EDG engines for exiting domestic NPPs are introduced

  1. Development of halogen-free cables for nuclear power plants

    International Nuclear Information System (INIS)

    Yamamoto, Mitsuo; Ito, Kazumi; Yaji, Takeo; Yoshida, Shin; Sakurai, Takako; Matsushita, Shigetoshi.

    1990-01-01

    On the occasion where serious fire accidents were experienced in the past, the need for making flame-retardant wire and cable incombustible took place and has since been generalizing. Various sorts of flame-retardant cables have already been developed and been actually used. From the viewpoint of avoiding the interference with the evacuation and fire-fighting activity in case of fire or the secondary accidents such as corrosion of the distributing panel, etc., the demand for non-halogen flame-retardant cable has rapidly been increasing in recent years in some fields of general industries, because this specific cable would generate the least amount of toxic smoke or corrosive gas even when it should burn. Similar demand has been increasing also for the cable used for nuclear power plants. In this field, earnest desire has been made for the development of non-halogen flame-retardant cable having specific environmental resistance specially required at nuclear power plants in addition to the properties and capacities required in general industries. The authors have continued examinations on the anti-environmental properties of the materials for cable such as long heat resistance, radiation resistance, steam resistance and succeeded in completing various sorts of non-halogen flame-retardant cable for nuclear power plants. In this report, we will introduce various features of the cable we have developed this time as well as the long-term reliability of non-halogen flame-retardant materials. (author)

  2. Development of reliability-based safety enhancement technology; development of organization concept model in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Hyun; Kim, Ju Youl; Kim, Yoon Ik; Yang, Hui Chang; Lee, Yong Sik; Kim, Se Hyung [Seoul National University, Seoul (Korea)

    2002-03-01

    The influences of organizational factors on safety of nuclear power plants are mentioned in the early 1970s and noticed after being focused on in the accident report of TMI in 1979. These needs let us implement this research and the purposes of this research are to assess the organizational influences and to develop the organizational conceptual model to establish the basis of identifying the organizational factors, using this model to contribute to enhance safety and economics in nuclear power plants. Eventually research on the organizational influences is expected to have two effects, which are to improve safety through identifying potential causes of accidents and to elevate economics as a new approach to more efficient operation of nuclear power plants. In this study, recent studies were surveyed on the organizational conceptual model, the identification of organizational factors, assessment of organizational influences and evaluation methods of organizational factors and organizational influences among the overseas and domestic researches. In addition specific characteristics of domestic nuclear power plants were tried to identify through plant visit and an evaluation method of organizational influences on component maintenance and human performance were developed and presented. 71 refs., 40 figs., 18 tabs. (Author)

  3. 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

  4. Development of a dynamical systems model of plant programmatic performance on nuclear power plant safety risk

    International Nuclear Information System (INIS)

    Hess, Stephen M.; Albano, Alfonso M.; Gaertner, John P.

    2005-01-01

    Application of probabilistic risk assessment (PRA) techniques to model nuclear power plant accident sequences has provided a significant contribution to understanding the potential initiating events, equipment failures and operator errors that can lead to core damage accidents. Application of the lessons learned from these analyses has resulted in significant improvements in plant operation and safety. However, this approach has not been nearly as successful in addressing the impact of plant processes and management effectiveness on the risks of plant operation. The research described in this paper presents an alternative approach to addressing this issue. In this paper we propose a dynamical systems model that describes the interaction of important plant processes on nuclear safety risk. We discuss development of the mathematical model including the identification and interpretation of significant inter-process interactions. Next, we review the techniques applicable to analysis of nonlinear dynamical systems that are utilized in the characterization of the model. This is followed by a preliminary analysis of the model that demonstrates that its dynamical evolution displays features that have been observed at commercially operating plants. From this analysis, several significant insights are presented with respect to the effective control of nuclear safety risk. As an important example, analysis of the model dynamics indicates that significant benefits in effectively managing risk are obtained by integrating the plant operation and work management processes such that decisions are made utilizing a multidisciplinary and collaborative approach. We note that although the model was developed specifically to be applicable to nuclear power plants, many of the insights and conclusions obtained are likely applicable to other process industries

  5. Quality assurance requirements for the reliability of nuclear power plants in developing countries

    International Nuclear Information System (INIS)

    Bhutta, S.M.

    1978-01-01

    Quality Assurance (QA) has not been taken very seriously in developing countries despite their having significant nuclear power programmes. This may affect plant reliability and demands that urgent and serious attention be given to the development and implementation of Quality Assurance programmes according to local conditions. Confusion has been created by the differences in definitions and interpretations of terminologies of Quality Assurance and Control. Problems have been aggravated by the lack of clearly defined responsibilities and accountabilities during the projects execution phases of site selection, data collection, design, equipment fabrication and construction, etc. Therefore, reliability of nuclear power plants in developing countries is relatively low. But whenever some programme of QA has been implemented it has helped to improve the plant performance. This is highlighted in this paper by the practical examples for the experience of Karachi Nuclear Power Plant whose forced outages have been reduced by over a half within a period of 3 years. In view of the benefits, a QA programme for Chashma Nuclear Power Project has also been initiated. In this paper urgency is emphasized for the establishment and implementation of a formal QA programme in the developing countries if the reactor suppliers and purchasers both want to ensure higher reliability of their plants. The best way that management can play its role effectively is by setting up a strong QA organization with local personnel, thus helping to attain self-reliance and higher reliability during plant operation. (author)

  6. Development of Halogen-free flame-retardant cable for nuclear power plant

    International Nuclear Information System (INIS)

    Ishii, Nobuhisa; Morii, Akira; Fujimura, Shunichi

    1992-01-01

    Conventional flame-retardant cables release a large volume of corrosive and toxic gases as well as smoke while combusted. Cables covered with halogen-free flame-retardant material, containing no halogen in it, have been developed to reduce generation of such gases and smoke, and have already been used in telecommunication service, subway and shipboard applications. However, for cables for nuclear power plant, covering materials should also have radiation resistance and other properties, including long-term physical stability. We have developed halogen-free flame-retardant cables for BWR nuclear power plant with sufficient flame retardancy radiation resistance and environmental resistance including steam-exposure resistance all of which are in accordance with Japanese specifications for BWR nuclear cables and have such characteristics as low corrosiveness, low toxicity and low smoke emission. (author)

  7. Development of Inventory Optimization System for Operation Nuclear Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Se-Jin; Park, Jong-Hyuk; Yoo, Sung-Soo; Lee, Sang-Guk [Korea Electric Power Research Institutes, Taejon (Korea, Republic of)

    2006-07-01

    Inventory control of spare parts plays an increasingly important role in operation management. This is why inventory management systems such as manufacturing resources planning(MRP) and enterprise resource planning(ERP) have been added. However, most of these contributions have similar theoretical background. This means the concepts and techniques are mainly based on mathematical assumptions and modeling inventory of spare parts situations. Nuclear utilities in Korea have several problems to manage the optimum level of spare parts though they used MRP System. Because most of items have long lead time and they are imported from United States, Canada, France and so on. We developed the inventory optimization system for Operation Nuclear Plants to resolve these problems. In this paper, we report a data flow process, data load and inventory calculation process. The main contribution of this paper is development of inventory optimization system which can be used in domestic power plants.

  8. Development of Inventory Optimization System for Operation Nuclear Plants

    International Nuclear Information System (INIS)

    Jang, Se-Jin; Park, Jong-Hyuk; Yoo, Sung-Soo; Lee, Sang-Guk

    2006-01-01

    Inventory control of spare parts plays an increasingly important role in operation management. This is why inventory management systems such as manufacturing resources planning(MRP) and enterprise resource planning(ERP) have been added. However, most of these contributions have similar theoretical background. This means the concepts and techniques are mainly based on mathematical assumptions and modeling inventory of spare parts situations. Nuclear utilities in Korea have several problems to manage the optimum level of spare parts though they used MRP System. Because most of items have long lead time and they are imported from United States, Canada, France and so on. We developed the inventory optimization system for Operation Nuclear Plants to resolve these problems. In this paper, we report a data flow process, data load and inventory calculation process. The main contribution of this paper is development of inventory optimization system which can be used in domestic power plants

  9. Some issues related to the development of nuclear power plant in Indonesia

    International Nuclear Information System (INIS)

    Panggabean, L.M.

    1987-01-01

    Indonesia being a member of ASEAN belongs to the group of developing country. If Indonesia decides to embark on the establishment of nuclear power plan then the country will have no choice but to discuss the following issues: Safe operation of the plant and management of the nuclear waste. Safe operation of the power plant is important not only from the point of view of hazards to human being, or economic loss, or even death, but equally important it is also from the psychological point of view in that not to loose the society's confidence in the overall nuclear power plant programme in the future. The issue of safe operation involves both a safely designed system as well as skilled personnels to execute a well designed operation procedure. The issue of nuclear safety is getting more and more attention lately for various, some due to a deep concern about the quality of the inherent safety of the nuclear power plant to be built, others may just use their emotion to ask question like ''what its''. The issue of nuclear waste is as fundamental as the plant safety. Common people make very little difference between an atomic bomb and waste from a nuclear power plant. Another issue is one of transfer of technology which needs to be tied up with the overall industrialization process, meaning that embarking on nuclear power programme needs to contribute to local industrial activities, at least for some parts or components which can be manufactured locally. (author)

  10. Nuclear security - New challenge to the safety of nuclear power plants

    International Nuclear Information System (INIS)

    Li Ganjie

    2008-01-01

    The safety of nuclear power plants involves two aspects: one is to prevent nuclear accidents resulted from systems and equipments failure or human errors; the other is to refrain nuclear accidents from external intended attack. From this point of view, nuclear security is an organic part of the nuclear safety of power plants since they have basically the same goals and concrete measures with each other. In order to prevent malicious attacks; the concept of physical protection of nuclear facilities has been put forward. In many years, a series of codes and regulations as well as technical standard systems on physical protection had been developed at international level. The United Nations passed No. 1540 resolution as well as 'Convention on the Suppression of Acts of Nuclear terrorism', and revised 'Convention on Physical Protection of Nuclear Materials', which has enhanced a higher level capacity of preparedness by international community to deal with security issues of nuclear facilities. In China, in order to improve the capability of nuclear power plants on preventing and suppressing the external attacks, the Chinese government consecutively developed the related codes and standards as well as technical documents based on the existing laws and regulations, including 'Guide for the Nuclear Security of Nuclear Power Plants' and 'Guide for the Physical Protection of Nuclear Materials', so as to upgrade the legislative requirements for nuclear security in power plants. The government also made greater efforts to support the scientific research and staff training on physical protection, and satisfying the physical protection standards for newly-built nuclear facilities such as large scale nuclear power plants to meet requirement at international level. At the same time old facilities were renovated and the Chinese government established a nuclear emergency preparedness coordination mechanism, developed corresponding emergency preparedness plans, intensified the

  11. Use of Pilot Plants for Developing Used Nuclear Fuel Recycling Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Chris; Arm, Stuart [EnergySolutions LLC (United States); Banfield, Zara; Jeapes, Andrew; Taylor, Richard [National Nuclear Laboratory (United Kingdom)

    2009-06-15

    EnergySolutions and its teaming partners are working with the US Department of Energy (DOE) to develop processes, equipment and facilities for recycling used nuclear fuel (UNF). Recycling significantly reduces the volume of wastes that ultimately will be consigned to the National Geologic Repository, enables the re-use in new fuel of the valuable uranium and plutonium in the UNF, and allows the long-lived minor actinides to be treated separately so they do not become long term heat emitters in the Repository. A major requirement of any new UNF recycling facility is that pure plutonium is not separated anywhere in the process, so as to reduce the nuclear proliferation attractiveness of the facility. EnergySolutions and its team partner the UK National Nuclear Laboratory (NNL) have developed the NUEX process to achieve this and to handle appropriately the treatment of other species such as krypton, tritium, neptunium and technetium. NUEX is based on existing successful commercial UNF recycling processes deployed in the UK, France and imminently in Japan, but with a range of modifications to the flowsheet to keep some uranium with the plutonium at all times and to minimize aerial and liquid radioactive discharges. NNL's long-term experience in developing the recycling and associated facilities at the Sellafield site in the UK, and its current duties to support technically the operation of the Thermal Oxide Reprocessing Plant (THORP) at Sellafield provides essential input to the design of the US NUEX-based facility. Development work for THORP and other first-of-kind nuclear plants employed miniature scale fully radioactive through large scale inactive pilot plants. The sequence of development work that we have found most successful is to (i) perform initial process development at small (typically 1/5000) scale in gloveboxes using trace active materials, (ii) demonstrate the processes at the same small scale with actual irradiated fuel in hot cells and (iii

  12. Development of a smart type motor operated valve for nuclear power plants

    Science.gov (United States)

    Kim, Chang-Hwoi; Park, Joo-Hyun; Lee, Dong-young; Koo, In-Soo

    2005-12-01

    In this paper, the design concept of the smart type motor operator valve for nuclear power plant was described. The development objective of the smart valve is to achieve superior accuracy, long-term reliability, and ease of use. In this reasons, developed smart valve has fieldbus communication such as deviceNet and Profibus-DP, auto-tuning PID controller, self-diagnostics, and on-line calibration capabilities. And also, to achieve pressure, temperature, and flow control with internal PID controller, the pressure sensor and transmitter were included in this valve. And, temperature and flow signal acquisition port was prepared. The developed smart valve will be performed equipment qualification test such as environment, EMI/EMC, and vibration in Korea Test Lab. And, the valve performance is tested in a test loop which is located in Seoul National University Lab. To apply nuclear power plant, the software is being developed according to software life cycle. The developed software is verified by independent software V and V team. It is expected that the smart valve can be applied to an existing NPPs for replacing or to a new nuclear power plants. The design and fabrication of smart valve is now being processed.

  13. Development of remote repair robots for dissolvers in nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Sugiyama, Sen; Kunikata, Michio; Kawamura, Hironobu.

    1985-01-01

    For nuclear facilities, various types of remote maintenance and inspection devices have been developed to reduce radiation exposure to workers, save labor, and improve the operating rate of the plant. Existing robot technology, however, could not be employed when we were recently called upon to inspect and repair pinhole defects which had occurred in the spent fuel dissolvers of the Power Reactor and Nuclear Fuel Development Corporation's Tokai Reprocessing Plant, because the work had to be done in an extremely radioactive environment, conditions too extreme for conventional robots. For this reason, we developed highly radiation-resistant repair robots capable of fully remote-controlled operation inside the barrels of the dissolvers, which have the inconvenient shape of 270 mm inside diameter and 6 m length. The process for developing the six different repair robots and the their functions are described in this paper. This development was sponsored by the Power Reactor and Nuclear Fuel Development Corporation (PNC) under contract with Hitachi, Ltd. (author)

  14. Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

    International Nuclear Information System (INIS)

    Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

    2005-04-01

    Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

  15. 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.)

  16. Development of Dukovany nuclear power plant

    International Nuclear Information System (INIS)

    Kouklik, I.

    2000-01-01

    The presentation evaluates the present situation of the Dukovany nuclear power plant operation. It analyses the present at the plant, and also in both the near and distant localities. Based on these analyses the conclusions and targets that are necessary for keeping the plant's safe operation are made. From the current situation the report about the results of the year 1999 in the operation and financial field, stress on the safety index, is presented. Further, there is a list of finished and semi-finished activities that are taking place within the harmonization of the Dukovany NPP. At the same time the report presents the terms of licensing and the going of implementation of the 'KAPA' project - the complex application of the Atomic Energy Act. In the part, comparison to the environment, there is an example of a comparison with the results of a plant in the EU. Further the report compares the advantages and disadvantages of the WWER reactors with other light water reactors. In the last part of the presentation there is a brief opinion of the author on the steps that are awaiting us in the future. First, the 'Harmonization program' of Dukovany NPP is explained, its philosophy and principles. The basic idea is to take the right steps and strategic decisions, with the vision for the operation till the year 2025 at least. There is also a list of the most important events that are planned to increase the safety. Further the report goes briefly over the current situation in the filed of nuclear energy in the period of joining the European Union and also mentions the risks that result from this process. It concludes with the prognosis for the further position of the Dukovany nuclear power plant. (author)

  17. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

    1979-07-01

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system

  18. Developments in nuclear power plant water chemistry

    International Nuclear Information System (INIS)

    Fruzetti, K.; Wood, C.J.

    2007-01-01

    This paper illustrates the changing role of water chemistry in current operation of nuclear power plants. Water chemistry was sometimes perceived as the cause of materials problems, such as denting in PWR steam generators and intergranular stress corrosion cracking in BWRs. However, starting in the last decade, new chemistry options have been introduced to mitigate stress corrosion cracking and reduce fuel performance concerns. In BWRs and PWRs alike, water chemistry has evolved to successfully mitigate many problems as they have developed. The increasing complexity of the chemistry alternatives, coupled with the pressures to increase output and reduce costs, have demonstrated the need for new approaches to managing plant chemistry, which are addressed in the final part of this paper. (orig.)

  19. 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)

  20. Developing a computerized aging management system for concrete structures in finnish nuclear power plants

    International Nuclear Information System (INIS)

    Al-Neshawy, F.; Piironen, J.; Sistonen, E.; Vesikari, E.; Tuomisto, M.; Hradil, P.; Ferreira, M.

    2013-01-01

    Finland has four nuclear reactors units in two power plants. The first unit started operation in 1977 and in the early 1980's all four units were in use. During the last few years the aging management of the Nuclear Power Plant's (NPP) concrete structures has grown an important issue because the existing structures are reaching the end of their licensed operating lifetime (about 40 years). Therefore the nuclear power companies are developing aging management systems to avoid premature degradation of NPP facilities and to be able to extend their operating lifetime. This paper is about the development of a computerized ageing management system for the nuclear power plants concrete structures. The computerized ageing management system is built upon central database and implementation applications. It will assist the personnel of power companies to implement the aging management activities at different phases of the lifetime of a power plant. It will provide systematic methods for planning, surveillance, inspection, monitoring, condition assessment, maintenance and repair of structures. (authors)

  1. Development of management systems for nuclear power plant of Hokuriku Electric Power Company

    International Nuclear Information System (INIS)

    Nakamura, Tatsuaki; Hasunuma, Junichi; Suzuki, Shintaro

    2009-01-01

    Hokuriku Electric Power Company has been operating the Shika Nuclear Power Station that it constructed in Shika city, Ishikawa prefecture, for over 15 years since bringing Unit 1 of this plant online in July 1993. In addition to electricity generation, maintenance and inspection tasks constitute a big part of operating a large-scale nuclear power plant, and in recent years, problems at power stations in the nuclear power industry have led to several revisions of nationally regulated maintenance and inspection systems. This paper describes the background, objectives, development method, and features of the Maintenance Management System and Maintenance History Management System that make effective use of information technology to promote safer and more efficient maintenance work at large-scale nuclear power plants. (author)

  2. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

    1979-01-01

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system. 2 refs

  3. Development of advanced secondary chemistry monitoring system for Korea nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Sang Hak; Kim, Chung Tae

    1997-01-01

    Water chemistry control is one of the most important tasks in order to maintain the reliability of plant equipments and extend the operating life of the plant. KEPCO and KOPEC developed a computerized tool for this purpose -ASCMS (advanced secondary chemistry monitoring system) which is able to monitor and diagnose the secondary water chemistry. A prototype system had been installed at KORI 3 nuclear power plant since April 1993 in order to evaluate the system performance. After the implementation of enhancements identified during the testing of the prototype, we have developed the advanced secondary monitoring system, ASCMS which is installed at 5 nuclear power plants and has been under operations since April 1997. The ASCMS comprises PC subsystem designed for data acquisition, data analysis, and data diagnosis. The ASCMS will provide overall information related to steam generator secondary side water chemistry problems and improve plant availability, reduce radiation exposure to workers, and reduce operating and maintenance costs. 6 figs

  4. 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…

  5. Development of high-reliability control system for nuclear power plants

    International Nuclear Information System (INIS)

    Asami, K.; Yanai, K.; Hirose, H.; Ito, T.

    1983-01-01

    In Japan, many nuclear power generating plants are in operation and under construction. There is a general awareness of the problems in connection with nuclear power generation and strong emphasis is put on achieving highly reliable operation of nuclear power plants. Hitachi has developed a new high-reliability control system. NURECS-3000 (NUclear Power Plant High-REliability Control System), which is applied to the main control systems, such as the reactor feedwater control system, the reactor recirculation control system and the main turbine control system. The NURECS-3000 system was designed taking into account the fact that there will be failures, but the aim is for the system to continue to function correctly; it is therefore a fault-tolerant system. It has redundant components which can be completely isolated from each other in order to prevent fault propagation. The system has a hierarchical configuration, with a main controller, consisting of a triplex microcomputer system, and sub-loop controllers. Special care was taken to ensure the independence of these subsystems. Since most of the redundant system failures are caused by common-mode failures and the reliability of redundant systems depends on the reliability of the common-mode parts, the aim was to minimize these parts. (author)

  6. Development of an intelligent annunciation system for nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Chang-Gi; Che, Myoung-Eun

    1997-01-01

    Yonggwang Nuclear Units 1 and 2 have developed an intelligent annunciation system to replace the existing obsolete system and to enhance operator support. The new annunciation system, which is currently operating at both units, uses the distributed control technology to enhance reliability and to provide versatile function to operations and maintenance personnel. The hardware and software configuration is based on redundancy so that a component failure would not initiate system malfunction. The data base of the new system provides, through a touch screen, an automatic alarm response procedure for selected alarms, which increases availability of information for plant operation. Other KEPCO nuclear units and the fossil plants are considering installing the new system. (author). 6 figs, 2 tabs

  7. 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)

  8. Development of an intelligent annunciation system for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang-Gi; Che, Myoung-Eun [Instrumentation and Control, Yonggwang Nuclear Units 1 and 2, Korea Electric Power Corp. (Korea, Republic of)

    1997-09-01

    Yonggwang Nuclear Units 1 and 2 have developed an intelligent annunciation system to replace the existing obsolete system and to enhance operator support. The new annunciation system, which is currently operating at both units, uses the distributed control technology to enhance reliability and to provide versatile function to operations and maintenance personnel. The hardware and software configuration is based on redundancy so that a component failure would not initiate system malfunction. The data base of the new system provides, through a touch screen, an automatic alarm response procedure for selected alarms, which increases availability of information for plant operation. Other KEPCO nuclear units and the fossil plants are considering installing the new system. (author). 6 figs, 2 tabs.

  9. Fire scenarios in nuclear power plant

    International Nuclear Information System (INIS)

    Asp, I.B.; MacDougall, E.A.; Hall, R.E.

    1978-01-01

    This report defines a Design Base Fire and looks at 3 major areas of a hypothetical model for a Nuclear Power Plant. In each of these areas a Design Base Fire was developed and explained. In addition, guidance is given for comparing fire conditions of a given Nuclear Power Plant with the model plant described. Since there is such a wide variation in nuclear plant layouts, model areas were chosen for simplicity. The areas were not patterned after any existing plant area; rather several plant layouts were reviewed and a simplified model developed. The developed models considered several types of fires. The fire selected was considered to be the dominant one for the case in point. In general, the dominant fire selected is time dependent and starts at a specific location. After these models were developed, a comparison was drawn between the model and an operating plant for items such as area, cable numbers and weight, tray sizes and lengths. The heat loads of the model plant are summarized by area and compared with those of an actual operating plant. This document is intended to be used as a guide in the evaluation of fire hazards in nuclear power stations and a summarization of one acceptable analytical methodology to accomplish this

  10. Development of on-line operator aid system (OASYSTM) for nuclear power plants

    International Nuclear Information System (INIS)

    Kang, Ki Sig; Choi, Seong Soo; Kim, Han Gon; Chang, Soon Heung; Jeong, Hee Kyo; Yi, Chul Un

    1994-01-01

    In this paper, the development of On - line operator Aid SYStem (OASYS TM ) are discussed by focusing attention on the importance of the operator's role for nuclear power plants. The OASYS TM is under development to support the operator's decision making process and to enhance the safety of a nuclear power plant by providing the plant operators with timely and proper guideline during abnormal and emergency conditions. The OASYS TM has capabilities for the signal validation/management, the alarm processing, the failure diagnosis using abnormal operating procedures, and the dynamic tracking of emergency operating procedures using function restoration guidelines and optimal recovery guidelines with a series of complex logic steps covering a broad spectrum of event sequences. The proposed system is being implemented on a SUN-4/75 Workstation using C and Quintus TM prolog language. For verification studies a full-scope real-time simulator is being used. Test results show that the OASYS TM is capable of diagnosing a plant failure quickly and providing an operator guideline with fast response time. After verification the OASYS TM will be installed in the simulator II of Kori nuclear training center

  11. Reliability database development and plant performance improvement effort at Korea Hydro and Nuclear Power Co

    International Nuclear Information System (INIS)

    Oh, S. J.; Hwang, S. W.; Na, J. H.; Lim, H. S.

    2008-01-01

    Nuclear utilities in recent years have focused on improved plant performance and equipment reliability. In U.S., there is a movement toward process integration. Examples are INPO AP-913 equipment reliability program and the standard nuclear performance model developed by NEI. Synergistic effect from an integrated approach can be far greater than as compared to individual effects from each program. In Korea, PSA for all Korean NPPs (Nuclear Power Plants) has been completed. Plant performance monitoring and improvement is an important goal for KHNP (Korea Hydro and Nuclear Power Company) and a risk monitoring system called RIMS has been developed for all nuclear plants. KHNP is in the process of voluntarily implementing maintenance rule program similar to that in U.S. In the future, KHNP would like to expand the effort to equipment reliability program and to achieve highest equipment reliability and improved plant performance. For improving equipment reliability, the current trend is moving toward preventive/predictive maintenance from corrective maintenance. With the emphasis on preventive maintenance, the failure cause and operation history and environment are important. Hence, the development of accurate reliability database is necessary. Furthermore, the database should be updated regularly and maintained as a living program to reflect the current status of equipment reliability. This paper examines the development of reliability database system and its application of maintenance optimization or Risk Informed Application (RIA). (authors)

  12. Development of Air Dispersion Modeling for Future Nuclear Plant in Malaysia

    International Nuclear Information System (INIS)

    Mohd Nahar Othman

    2011-01-01

    The impact development of Nuclear power plant in Malaysia, can be very negative to the nearby population, causing public restlessness and consequently affecting the image of the authorities in the countries. The precise source of the pollution from the nuclear power plant must be determined, pollution emission level and the meteorological conditions are needed to predict and established the ambient air to the save level at the perimeter fence of the plant and address it with respect to the radiological ambient standards. Upon modeling using an established package as well as site measurements, the radiological level at the perimeter fence of the plant must deduced and lower than the normal ambient level. Based on this issue, a modeling study was made in vicinity of Malaysian Nuclear Agency TRIGA reactor in the area of Bangi, Selangor to evaluate the possibility of movement of air around the area and their impact. This paper will address and discuss the modeling base on the data getting from Meteorological Department such as measurement of wind speed, temperature, humidity, ambient air radiological concentration and ect. The purpose of Air Dispersion Modeling is to establish the critical ambient emission level, as well as radiological modeling. The focus will be made on exploring the use of Ausplume modeling to develop correlations between the radiological concentrations, chemical compositions and ambient model for emission controls. (author)

  13. The Community's research and development programme on decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

    The programme, adopted by the Council of the European Communities, seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontaminations for decommissioning purposes; dismantling techniques; treatment of specific waste materials (steel, concrete and graphite); large transport containers for radioactive waste arising from decommissioning of nuclear power plants in the Community; and influence of nuclear power plant design features on decommissioning

  14. Development of a Multi-Channel Ultrasonic Testing System for Automated Ultrasonic Pipe Inspection of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lee, Hee Jong; Cho, Chan Hee; Cho, Hyun Joon

    2009-01-01

    Currently almost all in-service-inspection techniques, applied in domestic nuclear power plants, are partial to field inspection technique. These kinds of techniques are related to managing nuclear power plants by the operation of foreign-produced inspection devices. There have been so many needs for development of native in-service-inspection device because there is no native diagnosis device for nuclear power plant inspection yet in Korea. In this research, we developed several core techniques to make an automated ultrasonic pipe inspection system for nuclear power plants. A high performance multi-channel ultrasonic pulser/receiver module, an A/D converter module and a digital main CPU module were developed and the performance of the developed modules was verified. The S/N ratio, noise level and signal acquisition performance of the developed modules showed proper level as we designed in the beginning.

  15. Summary of developments and future projects in nuclear power plant control and instrumentation in the Netherlands

    International Nuclear Information System (INIS)

    Plas, Y. van der

    1990-01-01

    A general view is given on the developments and trends due to instrumentation and control of the two nuclear power plants in the Netherlands around the year 1989. Several projects, under which for classification of systems and components and for emergency operating procedures, are executed in both plants. An OSART mission initiated a project to make possible the periodic test of safety commands during operation. An other large project concerned the replacement of the process presentation system in Nuclear Power Plant Borssele. In the article several other developments due to the application of I and C in existing plants are outlined generally. Since 1974, no new nuclear power plants have been constructed in the Netherlands. (author). 2 figs

  16. Development of small size wall decontamination robot systems in nuclear power plants

    International Nuclear Information System (INIS)

    Fujita, Tsuneaki; Takahashi, Tsuyosi

    2004-01-01

    This paper describes the development of wall decontamination robot systems for nuclear power plants. In nuclear power plants, it is required to reduce maintenance costs, including annual inspection, repairs and so on. Most of such maintenance activities are actually performed after decontamination processes are completed. In particular, the decontamination process of reactor wells is very important for reducing the radiation exposure of human workers. In the past, decontamination of reactor wells used to be done by extra large machine and tools, which caused long working hours and tiresome works. It was one of the reasons maintenance costs couldn't have been easily reduced. There are narrow spaces in the reactor wells that have to be decontaminated by human workers. In order to minimize the radiation exposure to humans, wall decontamination robot systems have been developed. The decontamination robots have rolled brushes and suction mechanisms and are capable of removing contaminants attached to the wall surface of the reactor wells. By making the robots smaller, it is possible to work in narrower spaces. In this paper, the effectiveness of decontamination by the developed robots is shown through experiments in the actual nuclear power plants. (author)

  17. Direction of Technology Development for Nuclear Power Plants at the O and M Phase

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Insu; Park, Hwanpyo; Kim, Younghyun [Korea Institute of Construction Technology, Goyang (Korea, Republic of)

    2014-05-15

    Recently, Korea has attempted to advance overseas markets by securing competitive power in nuclear power technology. In order to develop and operate overall construction management systems with Korea's own brand equipped with sufficient applicability and competitive power in the market abroad and to ensure equal competitive power with other foreign advanced companies of nuclear power plants, Korea has launched a project called 'Data Centric Integration/Automation Technology for NP Project Management System' since July 2011. This project is divided into two phases: the first phase from 2012 to 2016 realizes EPCS stage, and the second phase from 2017 to 2020 extends to O and M stage. Appropriate technology development planning must be established if 'Data Centric Integration/Automation Technology for NP Project Management System' conducted at the first phase would extend to O and M stage at the second phase. Therefore, this study aimed at drawing out the direction of technology development based on present analysis of process at the operational phase of nuclear power plants in Korea conducted as previous study. This study analyzed current operation and maintenance systems first, analyzing the results of differences between the operation process of nuclear plants in Korea which was suggested at the previous study and the process of the Korea Hydro and Nuclear Power Co., Ltd. (hereafter referred to as 'KHNP') and drawing out the direction of technology development for nuclear power plants at the operational phase from the viewpoint of life cycle.

  18. Direction of Technology Development for Nuclear Power Plants at the O and M Phase

    International Nuclear Information System (INIS)

    Jung, Insu; Park, Hwanpyo; Kim, Younghyun

    2014-01-01

    Recently, Korea has attempted to advance overseas markets by securing competitive power in nuclear power technology. In order to develop and operate overall construction management systems with Korea's own brand equipped with sufficient applicability and competitive power in the market abroad and to ensure equal competitive power with other foreign advanced companies of nuclear power plants, Korea has launched a project called 'Data Centric Integration/Automation Technology for NP Project Management System' since July 2011. This project is divided into two phases: the first phase from 2012 to 2016 realizes EPCS stage, and the second phase from 2017 to 2020 extends to O and M stage. Appropriate technology development planning must be established if 'Data Centric Integration/Automation Technology for NP Project Management System' conducted at the first phase would extend to O and M stage at the second phase. Therefore, this study aimed at drawing out the direction of technology development based on present analysis of process at the operational phase of nuclear power plants in Korea conducted as previous study. This study analyzed current operation and maintenance systems first, analyzing the results of differences between the operation process of nuclear plants in Korea which was suggested at the previous study and the process of the Korea Hydro and Nuclear Power Co., Ltd. (hereafter referred to as 'KHNP') and drawing out the direction of technology development for nuclear power plants at the operational phase from the viewpoint of life cycle

  19. Plant Design Nuclear Fuel Element Production Capacity Optimization to Support Nuclear Power Plant in Indonesia

    International Nuclear Information System (INIS)

    Bambang Galung Susanto

    2007-01-01

    The optimization production capacity for designing nuclear fuel element fabrication plant in Indonesia to support the nuclear power plant has been done. From calculation and by assuming that nuclear power plant to be built in Indonesia as much as 12 NPP and having capacity each 1000 MW, the optimum capacity for nuclear fuel element fabrication plant is 710 ton UO 2 /year. The optimum capacity production selected, has considered some aspects such as fraction batch (cycle, n = 3), length of cycle (18 months), discharge burn-up value (Bd) 35,000 up 50,000 MWD/ton U, enriched uranium to be used in the NPP (3.22 % to 4.51 %), future market development for fuel element, and the trend of capacity production selected by advances country to built nuclear fuel element fabrication plant type of PWR. (author)

  20. New developments in seismic surveillance of nuclear power plants

    International Nuclear Information System (INIS)

    Anesa, Franco; Vavassori, Maurizio; Casirati, Mario

    1988-01-01

    In the present article, new trends and development of ISMES techniques and methods relating to the seismic surveillance of nuclear power plants, are described. The experience gained in this field is described, and particular attention is paid to the new trend in surveys and instrumentation design criteria (from both the hardware and software point of view). (author)

  1. New developments in seismic surveillance of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Anesa, Franco; Vavassori, Maurizio [Instrumentation and Systems Department, ISMES, Bergamo (Italy); Casirati, Mario [Dynamic Department, ISMES, Bergamo (Italy)

    1988-07-01

    In the present article, new trends and development of ISMES techniques and methods relating to the seismic surveillance of nuclear power plants, are described. The experience gained in this field is described, and particular attention is paid to the new trend in surveys and instrumentation design criteria (from both the hardware and software point of view). (author)

  2. 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

  3. Development of regulatory requirements/guides for desalination unit coupled with nuclear plant

    International Nuclear Information System (INIS)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik

    2005-10-01

    The basic design of System-integrated Modular Advanced Reactor (SMART), a small-to-medium sized integral type pressurized water reactor (PWR) with the capacity of 330MWth, has been developed in Korea. In order to demonstrate the safety and performance of the SMART design, 'Development Project of SMART-P (SMART-Pilot Plant)' has been being performed as one of the 'National Mid and Long-term Atomic Energy R and D Programs', which includes design, construction, and start-up operation of the SMART-P with the capacity of 65MWth, a 1/5 scaled-down design of the SMART. At the same time, a study on the development of regulatory requirements/guides for the desalination unit coupled with nuclear plant has been carried out by KINS in order to prepare for the forthcoming SMART-P licensing. The results of this study performed from August of 2002 to October of 2005 can be summarized as follows: (1) The general status of desalination technologies has been survey. (2) The design of the desalination plant coupled with the SMART-P has been investigated. (3) The regulatory requirements/guides relevant to a desalination unit coupled with a nuclear plant have been surveyed. (4) A direction on the development of domestic regulatory requirements/guides for a desalination unit has been established. (5) A draft of regulatory requirements/guides for a desalination unit has been developed. (6) Expert technical reviews have been performed for the draft regulatory requirements/guides for a desalination unit. The draft regulatory requirements/guides developed in this study will be finalized and can be applied directly to the licensing of the SMART-P and SMART. Furthermore, it will be also applied to the licensing of the desalination unit coupled with the nuclear plant

  4. Development of construction technology for nuclear power plants

    International Nuclear Information System (INIS)

    Schnellenbach, G.

    1975-01-01

    Stringent safety requirements for nuclear power plants create new technological problems in their construction. The development is influenced by the mode of operation of the respective reactors which leads to different construction styles of the reactor buildings. Accomodation of extraordinary load cases such as earthquake, airplane crash, and blast due to chemical explosions, requires additional treatment. Significant new problems arise for the prestressed concrete reactor pressure vessels and concrete containments, prestressed or reinforced. (orig.) [de

  5. 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

  6. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

  7. Development of supplier evaluation model applying in nuclear power plants

    International Nuclear Information System (INIS)

    Wang Yonggang; Fang Chunfa

    2006-01-01

    It is essential for the safe and stable operations of Nuclear Power Plants that various resources in the supply chain are effectively managed. Supplier is a significant resource of nuclear entities serving as an extension of the operation process. Scientific and radiation evaluation of the performance of suppliers is of vital importance to an effective and high quality supply chain. This paper establishes an advance and practical supplier evaluation system that is applicable for the operational nuclear power plants, based on the analysis of the current operation status of Daya Bay Nuclear Power Station against its targeted objectives, the acquisition of relevant practices home and abroad and the benchmarking with advanced peers, in order to enhance the core competence of nuclear power plant. (authors)

  8. Results of research and development for nuclear power plants with WWER-1000 type light water reactors

    International Nuclear Information System (INIS)

    1984-01-01

    The conference met in three sessions: 1. Project designing and construction of nuclear power plants; 2. Materials, technologies and applied mechanics; 3. Physics, thermal physics and control. The proceedings contains 82 papers of which only two have not been inputted in INIS. The final resolutions of session 1 related to the reduction of capital costs for newly built units, processing of project documentation, the introduction of step motors manufactured in Czechoslovakia, in-service diagnostics of nuclear power plants, etc. The final recommendations of session 2 dealt with the centralization of the management of research into the reliability, safety and residual life of nuclear installations, with radiation stability of weld metals, repairs of nuclear power plants by patch welding, with welding in nuclear power plants and stress calculations using mathematical methods. Session 3 centred on questions of the safety, reliability and economy of nuclear power plant operation. It was recommended to make a comparison of the results of theoretical calculations with experiments, to concentrate on the automation of measurement, to extend international division of labour and cooperation of CMEA countries, to extend publishing activities in the field of thermal physics, etc. General recommendations were related to the conception of the construction of nuclear power plants in Czechoslovakia, the implementation of original scientific, research and development work, to the question of personnel for nuclear research, the experimental base of the Czechoslovak nuclear programme and to planning and management of technical development. (E.S.)

  9. Action research for the development of the organizational climate in nuclear power plants. Review of the 6-year research and development program

    International Nuclear Information System (INIS)

    Yoshida, Michio; Misumi, Jyuji; Misumi, Emiko; Kotani, Fumio; Fukui, Hirokazu; Sakurai, Yukihiro

    1998-01-01

    The Institute of Nuclear Safety System, Incorporated and the Japan Institute for Group Dynamics have conducted action research for the development of the organizational climate in nuclear power plants. First, two types of scales were completed. One is for measuring the leadership behavior of leaders working at nuclear power plants and the other is for measuring the safety consciousness of workers. After having diagnosed the reality of actual nuclear power plants using those scales developed, leadership training courses were developed and implemented successfully. Analyses of the commitment to organization and self-efficacy and the relationship between leadership and personality were conducted as well. (author)

  10. Action research for the development of the organizational climate in nuclear power plants. Review of the 6-year research and development program

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, Michio [Kumamoto Univ. (Japan). Faculty of Education; Misumi, Jyuji; Misumi, Emiko; Kotani, Fumio; Fukui, Hirokazu; Sakurai, Yukihiro

    1998-09-01

    The Institute of Nuclear Safety System, Incorporated and the Japan Institute for Group Dynamics have conducted action research for the development of the organizational climate in nuclear power plants. First, two types of scales were completed. One is for measuring the leadership behavior of leaders working at nuclear power plants and the other is for measuring the safety consciousness of workers. After having diagnosed the reality of actual nuclear power plants using those scales developed, leadership training courses were developed and implemented successfully. Analyses of the commitment to organization and self-efficacy and the relationship between leadership and personality were conducted as well. (author)

  11. Safety criteria for nuclear chemical plants

    International Nuclear Information System (INIS)

    Ball, P.W.; Curtis, L.M.

    1983-01-01

    Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

  12. Development of advanced I and C in nuclear power plants: ADIOS and ASICS

    International Nuclear Information System (INIS)

    Kim, Jung-Taek; Kwon, Kee-Choon; Hwang, In-Koo; Lee, Dong-Young; Park, Won-Man; Kim, Jung-Soo; Lee, Sang-Jeong

    2001-01-01

    In this paper Automatic Startup Intelligent Control System (ASICS) that automatically controls the PWR plant from cold shutdown to 5% of reactor power and Alarm and Diagnosis-Integrated Operator Support System (ADIOS) that is integrated with alarms, process values, and diagnostic information to an expert system focused on alarm processing are described. Nuclear Power Plant is manually controlled from cold shutdown to 5% according to the general operation procedures for startup operation of nuclear power plant. Alarm information is the primary sources to detect abnormalities in nuclear power plants or other process plants. The conventional hardwired alarm systems, characterized by one sensor-one indicator may lead the control room operators to be confused with avalanching alarms during plant transients. ASICS and ADIOS are designed to reduce the operator burden. The advances in computer software and hardware technology and also in information processing provide a good opportunity to improve the control systems and the annunciator systems of nuclear power plants or other similar process plants. It is very important to test and evaluate the performance and the function of the computer- or software-based systems like ASICS and ADIOS. The performance and the function of ASICS and ADIOS are evaluated with the real-time functional test facility and the results have shown that the developed systems are efficient and useful for operation and operator support

  13. Development of advanced I and C in nuclear power plants: ADIOS and ASICS

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung-Taek E-mail: jtkim@nanum.kaeri.re.kr; Kwon, Kee-Choon; Hwang, In-Koo; Lee, Dong-Young; Park, Won-Man; Kim, Jung-Soo; Lee, Sang-Jeong

    2001-07-01

    In this paper Automatic Startup Intelligent Control System (ASICS) that automatically controls the PWR plant from cold shutdown to 5% of reactor power and Alarm and Diagnosis-Integrated Operator Support System (ADIOS) that is integrated with alarms, process values, and diagnostic information to an expert system focused on alarm processing are described. Nuclear Power Plant is manually controlled from cold shutdown to 5% according to the general operation procedures for startup operation of nuclear power plant. Alarm information is the primary sources to detect abnormalities in nuclear power plants or other process plants. The conventional hardwired alarm systems, characterized by one sensor-one indicator may lead the control room operators to be confused with avalanching alarms during plant transients. ASICS and ADIOS are designed to reduce the operator burden. The advances in computer software and hardware technology and also in information processing provide a good opportunity to improve the control systems and the annunciator systems of nuclear power plants or other similar process plants. It is very important to test and evaluate the performance and the function of the computer- or software-based systems like ASICS and ADIOS. The performance and the function of ASICS and ADIOS are evaluated with the real-time functional test facility and the results have shown that the developed systems are efficient and useful for operation and operator support.

  14. Development of a general-purpose mobile robot for use in nuclear power plants

    International Nuclear Information System (INIS)

    Martinez, A.; Yague, M.A.; Linares, F.

    1993-01-01

    In recent years, the Space Division of CONSTRUCCIONES AERONAUTICAS (CASA) and EQUIPOS NUCLEARES (ENSA) have participated in several national and international robotics programs in the respective space and nuclear areas. In mid-1992, they decided to jointly undertake the development of a mobile inspection and maintenance robot for Nuclear Power Plants. The success of such a multidisciplinary project was ensured by the way both companies complement each other and by their previous development. Work was begun on the feasibility study and specifications, for which technical meetings were held with personnel from the Medical and Health Physics Association of the utilities (AMYS) and several Nuclear Power Plants. The result of these conversations was a preliminary system design along with the specifications with which the system must comply. With these results, a report and job plan were prepared for construction of two prototypes and submitted to the INI (National Institute of Industry Shareholder of both CASA and ENSA), which decided to finance this second Phase of Development by charging it to the Group's Research Development Fund

  15. Development of nuclear power plant simulators for Soviet-designed nuclear reactors

    International Nuclear Information System (INIS)

    Kohut, P.; Tutu, N.K.; Cleary, E.J.; Erickson, K.G.; Yoder, J.; Kroshilin, A.

    2001-01-01

    The US Department of Energy (US DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators, are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper

  16. Success and failure of nuclear power plant Quality Assurance when applied to research and development activities

    International Nuclear Information System (INIS)

    Michels, R.D.; Stark, W.A.; Eberhart, C.F.

    1986-01-01

    Quality Assurance in some form or fashion has been practiced at research and development laboratories and facilities for quite some time. This quality assurance effort has largely been that of the scientist taking good notes as the experiment or observation is conducted to provide adequate documentation of the research and development effort. With the advent of the national laboratories participating in such projects as the Waste Isolation Project Plant (WIPP), Three Mile Island, and the National Waste Storage Program, a need for planned, systematic quality assurance for research and development activities has come into being. Based on experience evolved from nuclear power plant and facility construction, the government has chosen to utilize for these new projects the criteria developed for use in construction of power plants. While these criteria have worked reasonably well in the construction, maintenance, and operation of those nuclear plants, their application to research and development activities has not been an unqualified success. This paper compares and contrasts four criteria; surveillance, inspection, procurement, and calibration for application in the research and development situation, and nuclear power plants

  17. Success and failure of nuclear power plant Quality Assurance when applied to research and development activities

    Energy Technology Data Exchange (ETDEWEB)

    Michels, R.D.; Stark, W.A.; Eberhart, C.F.

    1986-01-01

    Quality Assurance in some form or fashion has been practiced at research and development laboratories and facilities for quite some time. This quality assurance effort has largely been that of the scientist taking good notes as the experiment or observation is conducted to provide adequate documentation of the research and development effort. With the advent of the national laboratories participating in such projects as the Waste Isolation Project Plant (WIPP), Three Mile Island, and the National Waste Storage Program, a need for planned, systematic quality assurance for research and development activities has come into being. Based on experience evolved from nuclear power plant and facility construction, the government has chosen to utilize for these new projects the criteria developed for use in construction of power plants. While these criteria have worked reasonably well in the construction, maintenance, and operation of those nuclear plants, their application to research and development activities has not been an unqualified success. This paper compares and contrasts four criteria; surveillance, inspection, procurement, and calibration for application in the research and development situation, and nuclear power plants.

  18. 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

  19. Introduction of Integrity Evaluation Criteria Developing during and after fire for Nuclear Power Plant Buildings

    International Nuclear Information System (INIS)

    Lee, Jin Woo

    2016-01-01

    The first project for nuclear power plant built in Korea to taking account the engineering based approach was started on October 2015 including the whole process such as fire hazard analysis, standard fire modeling, cable tray fire with multi spurious operation, structural fire integrity evaluation, and large area fire induced air craft crash. This paper covers the brief developing scheme and roadmap focusing on structural fire evaluation criteria. The meaningful first step for developing the structural fire integrity in nuclear power plant building is started with the series of fire related sub sections mentioned in earlier section. The recognition and sufficient effort of fire research leads to set up the safe and reliable design of nuclear power plant

  20. Introduction of Integrity Evaluation Criteria Developing during and after fire for Nuclear Power Plant Buildings

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin Woo [KEPCo, Gimcheon (Korea, Republic of)

    2016-05-15

    The first project for nuclear power plant built in Korea to taking account the engineering based approach was started on October 2015 including the whole process such as fire hazard analysis, standard fire modeling, cable tray fire with multi spurious operation, structural fire integrity evaluation, and large area fire induced air craft crash. This paper covers the brief developing scheme and roadmap focusing on structural fire evaluation criteria. The meaningful first step for developing the structural fire integrity in nuclear power plant building is started with the series of fire related sub sections mentioned in earlier section. The recognition and sufficient effort of fire research leads to set up the safe and reliable design of nuclear power plant.

  1. 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.)

  2. Plant life extensions for German nuclear power plants? Controversial discussion profit taking of nuclear power plant operators

    International Nuclear Information System (INIS)

    Matthes, Felix C.

    2009-10-01

    The discussion on the plant life extensions for German nuclear power plants beyond the residual quantity of electricity particularly focus on three aspects: Effects for the emission of carbon dioxide as a greenhouse gas; Development of the electricity price for which a reduction or attenuation is postulated due to a plant life extension; Skimming of additional profits at operating companies and their use in the safeguarding of the future (development of renewable energies, support of energy efficiency, promotion of the research, consolidation of the public budget, and so on). Under this aspect, the author of the contribution under consideration reports on the profit taking of nuclear power plant operators. The presented analysis considers three aspects: (a) Specification of the quantity structures for the investigated model of plant life extension; (b) The decisive parameter is the revenue situation and thus the price development for electricity at wholesale markets; (c) Determination and evaluation of the course in time of the profit taking.

  3. Development of an integrated database management system to evaluate integrity of flawed components of nuclear power plant

    International Nuclear Information System (INIS)

    Mun, H. L.; Choi, S. N.; Jang, K. S.; Hong, S. Y.; Choi, J. B.; Kim, Y. J.

    2001-01-01

    The object of this paper is to develop an NPP-IDBMS(Integrated DataBase Management System for Nuclear Power Plants) for evaluating the integrity of components of nuclear power plant using relational data model. This paper describes the relational data model, structure and development strategy for the proposed NPP-IDBMS. The NPP-IDBMS consists of database, database management system and interface part. The database part consists of plant, shape, operating condition, material properties and stress database, which are required for the integrity evaluation of each component in nuclear power plants. For the development of stress database, an extensive finite element analysis was performed for various components considering operational transients. The developed NPP-IDBMS will provide efficient and accurate way to evaluate the integrity of flawed components

  4. Development and future perspective of nuclear power plants. Current status and future prospect of world nuclear power plants

    International Nuclear Information System (INIS)

    Kobayashi, Masaharu

    2013-01-01

    Fukushima Daiichi NPS accidents occurred on 11 March 2011 brought about great effects on nuclear development not only in Japan but also in the world. In Japan restart of operation of periodically inspected nuclear power plants (NPPs) could not be allowed except Oi NPPs two units and most parties except Liberal Democratic Party (LDP) pledged to possibly phasing out nuclear power at House of Councillors election in July and public opinion was mostly against nuclear power after the accident. LDP clearly stated that, with the inauguration of new government last December, Japan would not pursuing the policy of the prior government of possibly phasing out nuclear power by the 2030s, but would instead make a 'zero-base' review of energy policy. Germany decided to close eight reactors immediately and remaining nine by the end of 2022. For many countries, nuclear power would play an important role in achieving energy security and sustainable development goals. In 2011 NPPs 6 units started operation with 2 units under construction, and in 2012 NPPs 3 units started operation with 7 units under construction. At present there are now over 400 NPPs operating in 31 countries and world trend seemed nuclear development was continued and number of countries newly deploying NPPs was increasing as much as eighteen. This article presented current status and future prospect of world NPPs in details. Japan would like to share its experiences and information obtained from the accident with the world and also promote NPPs overseas to meet the world's expectations. (T. Tanaka)

  5. Development of nuclear power plant diagnosis technique using neural networks

    International Nuclear Information System (INIS)

    Horiguchi, Masahiro; Fukawa, Naohiro; Nishimura, Kazuo

    1991-01-01

    A nuclear power plant diagnosis technique has been developed, called transient phenomena analysis, which employs neural network. The neural networks identify malfunctioning equipment by recognizing the pattern of main plant parameters, making it possible to locate the cause of an abnormality when a plant is in a transient state. In a case where some piece of equipment shows abnormal behavior, many plant parameters either directly or indirectly related to that equipment change simultaneously. When an abrupt change in a plant parameter is detected, changes in the 49 main plant parameters are classified into three types and a characteristic change pattern consisting of 49 data is defined. The neural networks then judge the cause of the abnormality from this pattern. This neural-network-based technique can recognize 100 patterns that are characterized by the causes of plant abnormality. (author)

  6. Nuclear power plants in post-war thought

    International Nuclear Information System (INIS)

    Toya, Hiroshi

    2015-01-01

    This paper overviews how nuclear power plants have been talked about in the post-war thought. Science and technology sometimes significantly change the thinking way of humans, and nuclear power generation is an extreme technology. This paper overviews how nuclear power plants and humans are correlated. The following three points are discussed as the major issues of contemporary thought over nuclear power plants. First, on the danger of nuclear power plants, the risk of destructive power that nuclear energy has, and the danger of unreasoning development in science and technology civilization are discussed. Second, on the ethics issues surrounding nuclear power plants, the ethics that are based on unbalanced power relations, and democratic responsibility ethics based on discussion ethics are discussed. Third, on the issues of nuclear power plants and imagination, the limitations of democratic discussion surrounding nuclear power plants, the formation of imagination commensurate with the destructive power of nuclear power plants, and the formation of imagination that can represent the distant future are discussed. (A.O.)

  7. Manpower development for safe operation of nuclear power plant. China. Simulator software development. UNDP-Activity: 2.1.8-IAEA-Task-01. Technical report

    International Nuclear Information System (INIS)

    Feng, C.P.

    1994-01-01

    In the frameworks of the project ''manpower development for safe operation of nuclear power plant'' the development of reactor simulator software is described. Qinshan nuclear power plant was chosen as a reference one

  8. 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

  9. Atucha I nuclear power plant transients analysis

    International Nuclear Information System (INIS)

    Castano, J.; Schivo, M.

    1987-01-01

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

  10. Development of chemistry management for Onagawa Nuclear Power Plant

    International Nuclear Information System (INIS)

    Honda, Kazuaki; Sato, Junichi; Maeda, Katsuji; Nagasawa Katsumi; Hashiura, Sintaro

    2000-01-01

    Onagawa nuclear power plant developed a system for chemistry management of prevention and preservation of power plant. It is able to early detection of data change for prevention of plant. The system supports management of chemical custodian and consists of four parts such as management of water quality of plant , management of liquid waste, management of vapor waste and estimation of performance of chemical equipment. The system has three functions: management of operation, estimation of omen and examination of origin. The function of management of operation supports the routine inspection of chemical custodian by increasing efficiency of analytical and process data collection, practical use of data,, accuracy of data and rapid analysis. Estimation function of omen observes data fetched via online during 24 hr, indicates the small primary change and determines the origins. Examination function of origin supports their quick correspondences at accident and certificates the detailed origins. Histories of development of the system, business systemization, system construction, system functions are explained.The diagram of background of system development, system construction, management functions, verification of analytical data, automatic continuos monitoring diagram, screen of detection of abnormal phenomena, classified diagram of origins for change of water quality in reactor were developed. (S.Y.)

  11. The impact of team building and leadership development on nuclear plant performance

    International Nuclear Information System (INIS)

    Fiedler, P.B.; Long, R.L.; Childress, J.R.

    1988-01-01

    Within the nuclear utility industry, the pressures of complex technologies, increasing regulations, and critical public scrutiny create a working environment filled with numerous pressures. The difficult nature of the industry puts a premium on effective teamwork, interdepartmental cooperation, and communication skills. A well-conceived and implemented team building and leadership development program can substantially improve the operating performance of a nuclear plant. This paper describes one such implementation effort at GPU Nuclear Corporation and at the Oyster Creek nuclear generating station (OCNGS) over an 18-month period

  12. Economic aspects of the development of nuclear power and fuel-cycle plants in the USSR

    International Nuclear Information System (INIS)

    Dergachev, N.P.; Kruglov, A.K.; Sedov, V.M.; Shuklin, S.V.

    1977-01-01

    Different possible versions of the construction programme for nuclear power stations and fuel-cycle plants in the USSR are discussed in relation to the target level of installed electrical capacity for 1980 and the predictions for the year 2000. The likely structure of the nuclear power industry is considered and the role of nuclear power stations with fast reactors is discussed, including their effect on the natural uranium supply situation. The effect of the development of fuel-cycle plants and of the organization of the reprocessing of fuel from nuclear power stations on the rate of introduction of fast reactor stations is analysed, and the effect of the technical and economic characteristics of fuel-cycle plants on the economic indices of nuclear power is studied. (author)

  13. Development of real options model for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, Kenji

    2004-01-01

    As the Japanese electricity market is deregulated, it becomes more important for electric utilities to recognize their financial risks and to adopt strategic and scientific decision making methodology. We have developed two models for valuation of Japanese nuclear power plants to support utilities' decision making. One is a net present value (NPV) model using discounted cash flow analysis method. Another is a real options model. This model is based on strict financial technology theory and can calculate value of early retirement, life extension and new unit addition options of nuclear units under electricity price uncertainty. This can also derive an optimal period for retirement, life extension and new unit addition. (author)

  14. Development of remote maintenance technology for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Kawahara, Akira; Saito, Masayuki; Kawamura, Hironobu; Yamade, Atsushi; Sugiyama, Sen; Sugiyama, Sakae.

    1986-01-01

    In the plants for reprocessing spent nuclear fuel containing fission products, due to the facts that the facilities are in high radiations fields, and the surfaces of equipments are contaminated with radioactive substances, the troubles of process equipments are directly connected to the remarkable drop of the rate of operation of the facilities. Therefore, the development of various remote maintenance techniques has been carried out so far, but this time, Hitachi Ltd. got a chance to take part in the repair of spent fuel dissolving tanks in the Tokai Reprocessing Plant of Power Reactor and Nuclear Fuel Development Corp. and the development of several kinds of remote checkup equipment related to the repair work. Especially in the repair of the dissolving tanks, a radiation-withstanding checkup and repair apparatus which has high remote operability taking the conditions of radioactive environment and the restriction of the repaired objects in consideration was required, and a dissolving tank repairing robot composed of six kinds has been developed. The key points of the development were the selective use of high radiation-withstanding parts and materials, small size structure and the realization of full remote operability. The full remote maintenance apparatus of this kind is unique in the world, and applicable to wide fields. (Kako, I.)

  15. Impacts of nuclear power plant developments on community service capacity

    International Nuclear Information System (INIS)

    Krannich, R.S.

    1978-03-01

    With the passage of the National Environmental Policy Act in 1969 a legislative mandate was established to assess ''socioeconomic'' as well as environmental consequences of large-scale development projects. However, the developing literature base in the area of socioeconomics has exhibited a pronounced tendency to stress social and economic pathologies associated with the so-called ''boom town'' syndrome. While boom growth and associated problems do appear to provide relevant conceptualizations of the socioeconomic impacts of energy resource development projects in geographically isolated sectors of the western United States, the argument is presented that such a perspective is generally inappropriate when assessing the consequences of nuclear power plant developments. Survey data on 21 nuclear generating facilities are analyzed in order to provide a comparative perspective on socioeconomic consequences and factors which may influence their relative importance

  16. Strengthening of nuclear power plant construction safety management

    International Nuclear Information System (INIS)

    Yu Jun

    2012-01-01

    The article describes the warning of the Fukushima nuclear accident, and analyzes the major nuclear safety issues in nuclear power development in China, problems in nuclear power plants under construction, and how to strengthen supervision and management in nuclear power construction. It also points out that the development of nuclear power must attach great importance to the safety, and nuclear power plant construction should strictly implement the principle of 'safety first and quality first'. (author)

  17. Academic training for nuclear power plant operators

    International Nuclear Information System (INIS)

    Jones, D.W.

    1982-01-01

    In view of the increasing emphasis being placed upon academic training of nuclear power plant operators, it is important that institutions of higher education develop and implement programs which will meet the educational needs of operational personnel in the nuclear industry. Two primary objectives must be satisfied by these programs if they are to be effective in meeting the needs of the industry. One objective is for academic quality. The other primary objective is for programs to address the specialized needs of the nuclear plant operator and to be relevant to the operator's job. The Center for Nuclear Studies at Memphis State University, therefore, has developed a total program for these objectives, which delivers the programs, and/or appropriate parts thereto, at ten nuclear plant sites and with other plants in the planning stage. The Center for Nuclear Studies program leads to a Bachelor of Professional Studies degree in nuclear industrial operations, which is offered through the university college of Memphis State University

  18. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Nakayama, Ryoichi; Kimura, Motohiko; Abe, Akira

    1993-01-01

    A continuing need exists for automatic or remote-controlled machines or robots which can perform inspection and maintenance tasks in nuclear power plants. Toshiba has developed several types of monofunctional and multi- functional robots for such purposes over the past 20 years, some of which have already been used in actual plants. This paper describes new multifunctional robots for inspection and maintenance. An inspection robot has been applied in an actual plant for two years for performance testing. Maintenance robots for grinding tasks have also been developed, which can be easily teleoperated by the operator using automatic control. These new robots are expected to be applied to actual inspection and maintenance work in nuclear power plants. (author)

  19. Research and development on the human factors technologies for nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Sim, B.S.; Lee, J.W.; Cheon, S.W.

    1996-01-01

    This paper introduces our research project on the development of human factors technologies for nuclear power plants in Korea. The project is divided into two sub-projects. The first sub-project is the development of human factors experimental evaluation techniques, which aims to develop the techniques for experimental design, experimental measurement and data collection/analysis, and to construct an integrated test facility (ITF) suitable for the experimental evaluation of man-machine interfaces (MMIs) at an advanced control room. The second is the development of human behavior analysis techniques, which has two research areas: one is the development of a task simulation analyzer and the other is human error case studies for nuclear power plants. (author)

  20. 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

  1. Risk-informed technology developments for nuclear power plants within the ASME in 2000-2001

    International Nuclear Information System (INIS)

    Wesley Rowley, C.; Balkey, K.R.

    2001-01-01

    The purpose of this paper is to provide information on developments within the ASME to support risk-informing NRC regulations for nuclear power plants. This paper builds on a publication at ICONE-8 that discussed ASME risk-informed nuclear power plant initiatives, both in Research and in Codes and Standards, particularly those related to risk-informing Part 50 of the 10 CFR (Code of federal regulations). During the past year, the ASME BNCS formed a Task Force to focus the Society's efforts to support risk-informing 10 CFR Part 50. Key efforts underway that are guided by the task force include finalizing the ASME PRA (probability risk assessment) Standard, developing a Code Case to risk-inform the repair, replacement, and modification activities for ASME components, and developing a Code Case to risk-inform the safety classification of pressure boundary components. Several other initiatives are also under investigation such as introducing risk insights into other ASME nuclear codes and standards supported by appropriate research and technical basis information. Supplementary information will also be provided to update an initial high level plan of ASME risk-informed initiatives for nuclear power plants that was presented at ICONE-8, including plans to communicate these risk-informed technology developments to the public. The authors included and acknowledged contributions from several other cognizant members of the ASME BNCS (board on nuclear codes standards) Task Group on RIP50 in the paper. (authors)

  2. Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Park, Un Su; Park, Ik Keun; Um, Byong Guk; Park, Yun Won; Kang, Suk Chul

    1998-01-01

    For an effective and efficient management of large amounts of preservice/inservice inspection(PSI/ISI) data in nuclear power plants, an intelligent Windows 95-based data management program was developed. This program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis in the past are avoided. The program extracts, and the associated remedies. Furthermore, additional inspection data and comments can be easily added or deleted for subsequent PSI/ISI operation. Although the initial version of the program was applied to Kori nuclear power plant, this program can be equally applied to other nuclear power plant. And also this program can be used to offer the fundamental data for application of evaluation data related to fracture mechanics analysis(FMA), probabilistic reliability assessment(PRA) of PSI/ISI results, performance demonstration initiative(PDI) and risk-informed ISI based on probability of detection(POD) information of ultrasonic examination. Besides, the program can be further developed as a unique PSI/ISI data management expert system that can be apart of PSI/ISI data management expert system that can be a part of PSI/ISI Total Support System(TSS) for Korean nuclear power plants

  3. Chemistry management system for nuclear power plants

    International Nuclear Information System (INIS)

    Nagasawa, Katsumi; Maeda, Katsuji

    1998-01-01

    Recently, the chemistry management in the nuclear power plants has been changing from the problem solution to the predictive diagnosis and maintenance. It is important to maintain the integrity of plant operation by an adequate chemistry control. For these reasons, many plant operation data and chemistry analysis data should be collected and treated effectively to evaluate chemistry condition of the nuclear power plants. When some indications of chemistry anomalies occur, quick and effective root cause evaluation and countermeasures should be required. The chemistry management system has been developed as to provide sophisticate chemistry management in the nuclear power plants. This paper introduces the concept and functions of the chemistry management system for the nuclear power plants. (author)

  4. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  5. Preliminary regulatory assessment of nuclear power plants vulnerabilities

    International Nuclear Information System (INIS)

    Kostadinov, V.; Petelin, S.

    2004-01-01

    Preliminary attempts to develop models for nuclear regulatory vulnerability assessment of nuclear power plants are presented. Development of the philosophy and computer tools could be new and important insight for management of nuclear operators and nuclear regulatory bodies who face difficult questions about how to assess the vulnerability of nuclear power plants and other nuclear facilities to external and internal threats. In the situation where different and hidden threat sources are dispersed throughout the world, the assessment of security and safe operation of nuclear power plants is very important. Capability to evaluate plant vulnerability to different kinds of threats, like human and natural occurrences and terrorist attacks and preparation of emergency response plans and estimation of costs are of vital importance for assurance of national security. On the basis of such vital insights, nuclear operators and nuclear regulatory bodies could plan and optimise changes in oversight procedures, organisations, equipment, hardware and software to reduce risks taking into account security and safety of nuclear power plants operation, budget, manpower, and other limitations. Initial qualitative estimations of adapted assessments for nuclear applications are shortly presented. (author)

  6. Occupational dose control in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Viktorsson, C.; Lochard, J.; Benedittini, M.; Baum, J.; Khan, T.A.

    1990-01-01

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

  7. Seismic review of existing nuclear power plants

    International Nuclear Information System (INIS)

    Yanev, P.I.; Mayes, R.L.; Jones, L.R.

    1975-01-01

    Because of developments in the fields of earthquake and structural engineering over the last two decades, the codes, standards and design criteria for Nuclear Power Plants and other critical structures have changed substantially. As a result, plants designed only a few years ago do not satisfy the requirements for new plants. Accordingly, the Regulatory Agencies are requiring owners of older Nuclear Power Plants to re-qualify the plants seismically, using codes, standards, analytical techniques and knowledge developed in recent years. Seismic review consists of three major phases: establishing the design and performance criteria, re-qualifying the structures, and re-qualifying the equipment. The authors of the paper have been recently involved in the seismic review of existing nuclear power plants in the United States. This paper is a brief summary of their experiences

  8. 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

  9. 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)

  10. 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.

  11. Power generation by nuclear power plants

    International Nuclear Information System (INIS)

    Bacher, P.

    2004-01-01

    Nuclear power plays an important role in the world, European (33%) and French (75%) power generation. This article aims at presenting in a synthetic way the main reactor types with their respective advantages with respect to the objectives foreseen (power generation, resources valorization, waste management). It makes a fast review of 50 years of nuclear development, thanks to which the nuclear industry has become one of the safest and less environmentally harmful industry which allows to produce low cost electricity: 1 - simplified description of a nuclear power generation plant: nuclear reactor, heat transfer system, power generation system, interface with the power distribution grid; 2 - first historical developments of nuclear power; 3 - industrial development and experience feedback (1965-1995): water reactors (PWR, BWR, Candu), RBMK, fast neutron reactors, high temperature demonstration reactors, costs of industrial reactors; 4 - service life of nuclear power plants and replacement: technical, regulatory and economical lifetime, problems linked with the replacement; 5 - conclusion. (J.S.)

  12. The historical development of criteria on the safety of nuclear power plants

    International Nuclear Information System (INIS)

    Talarek, H.D.

    1976-01-01

    Starting from the lump-sum criterion of distance, the criterion of MCA has developed based on the idea of limiting accident consequences with the object in mind of guaranteeing the protection of the population in case of the maximum credible accident in its absolute sense. This claim has proved to be indefensible for the utilization and design of the MCA criterion on nuclear power plants of larger capacities on sites near to conurbation centres. Within the concept of design basis accidents this is not claimed, an imperative formulation was found instead concerning the sort of accident to be considered, including possible demands on its safety design. Using probability methods has lead to a blurring of the relationship with the technological system of nuclear power plants for formulating a criterion for the advantage of risk quantification. If the probability method is to be applied in the licensing procedure concerning nuclear power plants it will be one of the tasks of future safety research to elaborate this relationship clearly. (orig.) [de

  13. 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

  14. Development of maintenance tools based on tribology for nuclear power plant

    International Nuclear Information System (INIS)

    Iwai, Yoshiro; Honda, Tomomi; Yoshinaga, Shigeki

    2007-01-01

    Many tribological problems occur in the maintenance of nuclear power plants. In this paper, we introduced our developed maintenance tools based on tribology such as a particle counter and wear sensors. Their principals were shown briefly and their usefulness was clarified by the experiments on monitoring of wear. (author)

  15. The problems of plant control on modern stage of development of the nuclear industry

    Directory of Open Access Journals (Sweden)

    Gusev S. S.

    2017-04-01

    Full Text Available the article describes the successful development of nuclear industry at the present stage of its development, the problems of control of nuclear power plants, their classes and the choices of modern science in the field of design of fast neutron reactors as one of the promising directions of development of atomic energy.

  16. Global development of advanced nuclear power plants, and related IAEA activities

    International Nuclear Information System (INIS)

    2006-09-01

    Renewed interest in the potential of nuclear energy to contribute to a sustainable worldwide energy mix is underlining the IAEA's statutory role in fostering the peaceful uses of nuclear energy, in particular the need for effective exchanges of information and collaborative research and technology development among Member States on advanced nuclear power technologies deployable in the near term as well as in the longer term. For applications in the medium to longer term, with rising expectations for the role of nuclear energy in the future, technological innovation has become a strong focus of nuclear power technology developments by many Member States. To meet Member States' needs, the IAEA conducts activities to foster information exchange and collaborative research and development in the area of advanced nuclear reactor technologies. These activities include coordination of collaborative research, organization of international information exchange, and analyses of globally available technical data and results, with a focus on reducing nuclear power plant capital costs and construction periods while further improving performance, safety and proliferation resistance. In other activities, evolutionary and innovative advances are catalyzed for all reactor lines such as advanced water cooled reactors, high temperature gas cooled reactors, liquid metal cooled reactors and accelerator driven systems, including small and medium sized reactors. In addition, there are activities related to other applications of nuclear energy such as seawater desalination, hydrogen production, and other process heat applications. This brochure summarizes the worldwide status and the activities related to advanced nuclear power technology development and related IAEA activities. It includes a list of the collaborative research and development projects conducted by the IAEA, as well as of the status reports and other publications produced

  17. State of the art and further development of reinforced concrete wall cells for nuclear power plant construction

    International Nuclear Information System (INIS)

    Uhlemann, E.; Wartenberg, J.

    1985-01-01

    Reinforced concrete wall cells have been developed for nuclear power plant construction by the USSR and GDR. In this article, a new type of these cells, which will be used for constructing auxiliary equipment of the Stendal nuclear power plant, is described

  18. Development of a SPV management program for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Eun-Chan; Na, Jang-Hwan; Lee, Doo-Young; Oh, Seong-Jong; Jerng, Dong-Wook

    2009-01-01

    The Single Point Vulnerability (SPV) is a characteristic of a component whose failure results in plant transients. KHNP (Korea Hydro and Nuclear Power Co.) has evaluated major systems with critical components and developed a SPV management program to reduce the trip frequency and to raise plant's availability. This study includes a comprehensive methodology for SPV evaluation and its results. This methodology consists of the qualitative evaluation focused on the SPV component list preparation and the quantitative evaluation through FMEA (Failure Mode Effect Analyses) and FTA (Fault Tree Analyses) of critical systems. The qualitative evaluation reduced differences of the SPV lists between the identically designed plants and established strategies for the improvement of the SPV component reliability. The quantitative evaluation identified additional SPV components and developed the fault tree model for a Trip Monitor which showed logic relationships of channel components in the trip-related systems. (author)

  19. Development of IT-based Cyber Security Technology for Nuclear Power Plant

    International Nuclear Information System (INIS)

    Hong, S. B.; Lee, J. C.; Choi, Y. S.; Choi, Y. R.; Cho, J. W.; Jung, C. E.; Jeong, K. I.; Park, B.; Koo, I. S.

    2009-11-01

    Development and enlargement of the high speed communication network make it possible the user to access online information easily. It generates changing offline activities to online in the economics, expansion of cultural interchanges and convenient life. But it also causes misuse, wiretapping, forgery and alteration of the information via illegal invasion(virus, hacking), and these are derived from the open network characteristic, weakness of the securities of the TCP/IP protocol and information systems. The security of individual and the national foundation facility(industry and government) can be threatened because of these problems, and theses can be used as a instrument of cyber-war. Many cyber security technologies have been developed to corp with the cyber threat. One of the most important national facility is the nuclear power plant and the necessity of the cyber security for the digital I and C of it have been proposed since middle of the 2000. KINS announced the regulation of the cyber security for the digital I and C of the nuclear power plant in 2007. The main concept of the cyber security for it is similar to the IT field that is treated as a leader of the cyber security. Because of the difference of the characteristics between the IT field and the nuclear industry, applying the cyber security technologies developed and used in the IT field to the nuclear industry has some critical constraints. We will analyze these problems and propose a cyber security method based on cryptograph and authentication for the I and C communication network in this report

  20. Development of IT-based Cyber Security Technology for Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hong, S. B.; Lee, J. C.; Choi, Y. S.; Choi, Y. R.; Cho, J. W.; Jung, C. E.; Jeong, K. I.; Park, B.; Koo, I. S

    2009-11-15

    Development and enlargement of the high speed communication network make it possible the user to access online information easily. It generates changing offline activities to online in the economics, expansion of cultural interchanges and convenient life. But it also causes misuse, wiretapping, forgery and alteration of the information via illegal invasion(virus, hacking), and these are derived from the open network characteristic, weakness of the securities of the TCP/IP protocol and information systems. The security of individual and the national foundation facility(industry and government) can be threatened because of these problems, and theses can be used as a instrument of cyber-war. Many cyber security technologies have been developed to corp with the cyber threat. One of the most important national facility is the nuclear power plant and the necessity of the cyber security for the digital I and C of it have been proposed since middle of the 2000. KINS announced the regulation of the cyber security for the digital I and C of the nuclear power plant in 2007. The main concept of the cyber security for it is similar to the IT field that is treated as a leader of the cyber security. Because of the difference of the characteristics between the IT field and the nuclear industry, applying the cyber security technologies developed and used in the IT field to the nuclear industry has some critical constraints. We will analyze these problems and propose a cyber security method based on cryptograph and authentication for the I and C communication network in this report.

  1. 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

  2. Development of Heavy-Duty and High-Precision Hydraulic Manipulator for Inspection, Maintenance and Decommission of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sung Uk; Seo, Yong-chil; Jung, Kyung Min; Kim, Chang-hoi; Choi, Byung-seon; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Robotic manipulators have been used for inspection, maintenance and decommission of nuclear power plants because nuclear power plants have high radiation and human workers cannot easily access the plants. And also, to inspecting, maintaining and decommissioning nuclear power plants require various manipulators. Only one manipulator cannot response to many required tasks. The existing manipulators that was used at nuclear power plants can only operate only focused specific task and cannot be used at several tasks. The actuators used at manipulators are varied and many companies sell actuators depending on power, torque and speed. However, the commercial product is not standardized. Therefore, the development of manipulator is time consuming and expensive. The essential item of a manipulator is an actuator module. If actuator module is standardized, it’s easier to develop a manipulator and also maintain a manipulator. Recently, manipulator having high-radiation, high-duty and high-precision is necessary to inspection, maintain and decommissioning of nuclear power plants. Hydraulic actuator has been used to development high-duty manipulator. But control performance of a hydraulic actuator is not better than that of an electric actuator so that hydraulic manipulator cannot easily satisfy the required precision. In this paper, we developed high-duty and high-precision actuator modules and hydraulic manipulator using the developed actuator modules. The developed hydraulic manipulator have a payload of 250kg and a precision of ±1mm. Four modularized hydraulic actuator modules were developed for inspection, maintenance and decommission. Using the developed actuator modules, the manipulator for decommissioning is easily developed. And also, various manipulators having different kinematic structure for specific tasks will be easily developed by using hydraulic modules.

  3. Development of Heavy-Duty and High-Precision Hydraulic Manipulator for Inspection, Maintenance and Decommission of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Sung Uk; Seo, Yong-chil; Jung, Kyung Min; Kim, Chang-hoi; Choi, Byung-seon; Moon, Jei-kwon

    2016-01-01

    Robotic manipulators have been used for inspection, maintenance and decommission of nuclear power plants because nuclear power plants have high radiation and human workers cannot easily access the plants. And also, to inspecting, maintaining and decommissioning nuclear power plants require various manipulators. Only one manipulator cannot response to many required tasks. The existing manipulators that was used at nuclear power plants can only operate only focused specific task and cannot be used at several tasks. The actuators used at manipulators are varied and many companies sell actuators depending on power, torque and speed. However, the commercial product is not standardized. Therefore, the development of manipulator is time consuming and expensive. The essential item of a manipulator is an actuator module. If actuator module is standardized, it’s easier to develop a manipulator and also maintain a manipulator. Recently, manipulator having high-radiation, high-duty and high-precision is necessary to inspection, maintain and decommissioning of nuclear power plants. Hydraulic actuator has been used to development high-duty manipulator. But control performance of a hydraulic actuator is not better than that of an electric actuator so that hydraulic manipulator cannot easily satisfy the required precision. In this paper, we developed high-duty and high-precision actuator modules and hydraulic manipulator using the developed actuator modules. The developed hydraulic manipulator have a payload of 250kg and a precision of ±1mm. Four modularized hydraulic actuator modules were developed for inspection, maintenance and decommission. Using the developed actuator modules, the manipulator for decommissioning is easily developed. And also, various manipulators having different kinematic structure for specific tasks will be easily developed by using hydraulic modules

  4. Guidelines for nuclear plant response to an earthquake

    International Nuclear Information System (INIS)

    1989-12-01

    Guidelines have been developed to assist nuclear plant personnel in the preparation of earthquake response procedures for nuclear power plants. The objectives of the earthquake response procedures are to determine (1) the immediate effects of an earthquake on the physical condition of the nuclear power plant, (2) if shutdown of the plant is appropriate based on the observed damage to the plant or because the OBE has been exceeded, and (3) the readiness of the plant to resume operation following shutdown due to an earthquake. Readiness of a nuclear power plant to restart is determined on the basis of visual inspections of nuclear plant equipment and structures, and the successful completion of surveillance tests which demonstrate that the limiting conditions for operation as defined in the plant Technical Specifications are met. The guidelines are based on information obtained from a review of earthquake response procedures from numerous US and foreign nuclear power plants, interviews with nuclear plant operations personnel, and a review of reports of damage to industrial equipment and structures in actual earthquakes. 7 refs., 4 figs., 4 tabs

  5. 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

  6. 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

  7. Nuclear plant engineering work and integrated management system

    International Nuclear Information System (INIS)

    Ohkubo, Y.; Obata, T.; Tanaka, K.

    1992-01-01

    The Application of computers to the design, engineering, manufacturing and construction works of nuclear power plants has greatly contributed to improvement of productivity and reliability in the nuclear power plants constructed by Mitsubishi Nuclear Group for more than ten years. However, in most cases, those systems have been developed separately and utilized independently in different computer software and hardware environments and have not been fully utilized to achieve high efficiency and reliability. In order to drastically increase the productivity and efficiency, development of NUclear power plant engineering Work and INtegrated manaGement System (NUWINGS) started in 1987 to unify and integrate various conventional and developing systems using the state-of-the-art computer technology. The NUWINGS is almost completed and is now applied to actual plant construction. (author)

  8. Developments of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2003-03-15

    The objective of this research is to develop an efficient evaluation technology and to investigate applicability of newly-developed technology, such as internet-based cyber platform, to operating power plants. Development of efficient evaluation systems for Nuclear Power Plant components, based on structural integrity assessment techniques, are increasingly demanded for safe operation with the increasing operating period of Nuclear Power Plants. The following five topics are covered in this project: development of assessment method for wall-thinned nuclear piping based on pipe test; development of structural integrity program for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for mam components of NPP; development of internet-based cyber platform and integrity program for primary components of NPP; effect of aging on strength of dissimilar welds.

  9. 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.)

  10. Information Technology for Nuclear Power Plant Configuration Management

    International Nuclear Information System (INIS)

    2010-07-01

    Configuration management (CM) is an essential component of nuclear power plant design, construction and operation. The application of information technology (IT) offers a method to automate and ensure the timely and effective capture, processing and distribution of key nuclear power plant information to support CM principles and practical processes and procedures for implementation of CM at nuclear power plants. This publication reviews some of the principles established in IAEA-TECDOC-1335, 'Configuration Management in Nuclear Power Plants.' It also recaps tenets laid out in IAEA- TECDOC-1284, 'Information Technology Impact on Nuclear Power Plant Documentation' that supports CM programmes. This publication has been developed in conjunction with and designed to support these other two publications. These three publications combined provide a comprehensive discussion on configuration management, information technology and the relationship between them. An extensive discussion is also provided in this publication on the role of the design basis of the facility and its control through the CM process throughout the facility's lifetime. While this report was developed specifically for nuclear power plants, the principles discussed can be usefully applied to any high hazard nuclear facility

  11. CAS medium-size nuclear plants

    International Nuclear Information System (INIS)

    Vogelweith, L.; Weiss, A.

    1977-01-01

    CEA has developed a range of pressurized water reactors of the type CAS Compact, which are adapted to civil ship propulsion, or to electric power production, combined possibly with heat production, up to outputs equivalent to 125MW(e). Nuclear plants equipped with these reactors are suitable for medium-size electric networks, especially in developing countries, because they are easily adaptable, owing to their flexibility; they can be installed and used in a variety of ways (on land, floating installation, combination of electric power and other production, etc.); they can be used as training reactors by countries wishing to limit their investment plans before undertaking a wider nuclear development. Examples of two possible realizations are presented: as a floating plant, and as a combined electric and desalting plant. (author)

  12. Development of Northeast Asia Nuclear Power Plant Accident Simulator.

    Science.gov (United States)

    Kim, Juyub; Kim, Juyoul; Po, Li-Chi Cliff

    2017-06-15

    A conclusion from the lessons learned after the March 2011 Fukushima Daiichi accident was that Korea needs a tool to estimate consequences from a major accident that could occur at a nuclear power plant located in a neighboring country. This paper describes a suite of computer-based codes to be used by Korea's nuclear emergency response staff for training and potentially operational support in Korea's national emergency preparedness and response program. The systems of codes, Northeast Asia Nuclear Accident Simulator (NANAS), consist of three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. To quickly assess potential doses to the public in Korea, NANAS includes specific reactor data from the nuclear power plants in China, Japan and Taiwan. The completed simulator is demonstrated using data for a hypothetical release. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  13. Emergency control centers for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Guidance is provided for the development and implementation of emergency control centers for nuclear power plants, including nuclear plant control room, nuclear plant company headquarters, emergency control center, and nuclear plant alternate emergency control center. Requirements and recommendations are presented for the mission, communications, instrumentation and equipment associated with each type of control center. Decisional aids, manning requirements and resources are also given; the decision aids cover both the accident assessment and protective action areas. Both normal and alternate means of communications are considered. Off-site emergency control centers, although not covered in the strict sense by this standard, are considered in an appendix

  14. Development of module-based simulation system for nuclear power plant

    International Nuclear Information System (INIS)

    Yoshikawa, H.

    1990-01-01

    Module-based Simulation System (MSS) has been developed to realize a new software environment enabling versatile dynamic simulation of a complex nuclear power plant system flexibly. Described in the paper are (i) fundamental methods utilized in MMS and its software systemization, (ii) development of human interface system to help users in generating integrated simulation programs automatically, and (iii) development of an intelligent user support system for helping users in the two phases of automatical semantic diagnosis and consultation to automatic input data setup for the MSS-generated programs

  15. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

    Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

    2011-01-01

    The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

  16. Next Generation Nuclear Plant Materials Research and Development Program Plan

    International Nuclear Information System (INIS)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-01-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R and D) Program is responsible for performing R and D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R and D Program includes the following elements: (1) Developing a specific approach, program plan and other project management

  17. Nuclear plant analyzer desktop workstation

    International Nuclear Information System (INIS)

    Beelman, R.J.

    1990-01-01

    In 1983 the U.S. Nuclear Regulatory Commission (USNRC) commissioned the Idaho National Engineering Laboratory (INEL) to develop a Nuclear Plant Analyzer (NPA). The NPA was envisioned as a graphical aid to assist reactor safety analysts in comprehending the results of thermal-hydraulic code calculations. The development was to proceed in three distinct phases culminating in a desktop reactor safety workstation. The desktop NPA is now complete. The desktop NPA is a microcomputer based reactor transient simulation, visualization and analysis tool developed at INEL to assist an analyst in evaluating the transient behavior of nuclear power plants by means of graphic displays. The NPA desktop workstation integrates advanced reactor simulation codes with online computer graphics allowing reactor plant transient simulation and graphical presentation of results. The graphics software, written exclusively in ANSI standard C and FORTRAN 77 and implemented over the UNIX/X-windows operating environment, is modular and is designed to interface to the NRC's suite of advanced thermal-hydraulic codes to the extent allowed by that code. Currently, full, interactive, desktop NPA capabilities are realized only with RELAP5

  18. Developments in operator assistance techniques for nuclear power plant control and operation

    International Nuclear Information System (INIS)

    Poujol, A.; Papin, B.; Beltranda, G.; Soldermann, R.

    1989-01-01

    This paper describes an approach which has been developed in order to improve nuclear power plants control and monitoring in normal and abnormal situations. These developments take full advantage of the trend towards the computerization of control rooms in industrial continuous processes. This research program consists in a thorough exploration of different information processing techniques, ranking from the rather simple visual synthetization of informations on graphic displays to sophisticated Artificial Intelligence (AI) techniques. These techniques are put into application for the solving of man-machine interface problems in the different domains of plant operation

  19. Maintenance planning for nuclear power plants

    International Nuclear Information System (INIS)

    Mattu, R.K.; Cooper, S.E.; Lauderdale, J.R.

    2004-01-01

    Maintenance planning for nuclear power plants is similar to that in other industrial plants but it is heavily influenced by regulatory rules, with consequent costs of compliance. Steps by the nuclear industry and the Nuclear Regulatory Commission to address that problem include development of guidelines for maintenance of risk-critical equipment, using PRA-based techniques to select a set of equipment that requires maintenance and reliability-centered maintenance (RCM) approaches for determining what maintenance is required. The result of the process is a program designed to ensure effective maintenance of the equipment most critical to plant safety. (author)

  20. Nuclear plant life - A business decision

    International Nuclear Information System (INIS)

    Joosten, J.K.

    1995-01-01

    Regarding the future of the nuclear power option, many scenarios have been put forth over the years. The most commonly accepted projections for installed nuclear capacity show it growing at a rate of about 2% per year throughout the next few decades. These projections appear modes on the surface. However, underlying the projections are critical assumptions and sometimes misconceptions about the lifetimes of existing reactors and how they are determined. The notion of a 40 year plant life is very common. Consequently, many projections start either with the assumption that no plants will be retired in the near terms or with the assumption that each retired plant will be replaced by another nuclear plant after 40 years. Effectively, these assumptions yield future projections for installed capacity that might be characterized as low growth, medium growth and high growth scenarios - or grow, grow, grow. The question remains as to whether or not these assumptions accurately model the driving forces and constraints to nuclear development. After all, there is no scientific basis for believing that all plants, PWRs BWRs, RBMKs, etc., should have the same 40 year life. Most power plant owners purchase the plant for the main reason of supplying electrical power to their consumer. For these owners, electricity production is a day to day commercial activity with various alternatives on how to achieve the prime objective. The decision of which electricity generation alternative to select (gas, coal, nuclear or renewable energy) and how long to operate the plant before replacing it with a new one is essentially a business decision. The paper discusses ageing, the nuclear plant life decision process, the factors which influence the decision and their ramifications regarding the near term growth of nuclear power capacity. The modelling of nuclear plant lifetimes is also discussed. (author). 5 refs, 10 figs, 1 tab

  1. Development of safety culture by improving risk communication in a nuclear power plant

    International Nuclear Information System (INIS)

    Sugiman, Toshio; Yoshikawa, Hidekazu

    2004-01-01

    Safety culture is conceptually examined from the viewpoint of activity theory proposed by Engestroem. The theory is instrumental in broadening our scope of views to the extent that a particular (group of person(s) and his/her (their) environment are regarded as a part of activity of a larger collectivity consisting of people and their physical and institutional environments. Overwhelming orientation toward an unmanned plant is reflected in object → outcome and mediating artifacts in the structure of activity in a nuclear power plant while it is contradicted with another orientation toward the improvement of employee's ability in community, rules, and division of labor. Three possible ways to transform a currently dominant activity into a new form were suggested depending on a preliminary study of our research project headed by the seconds author. First, community of a nuclear power plant may as well be expanded to the extent that nuclear experts outside the plant, especially those working for a plant/equipment manufacturing company, can share information with workers inside the plant through internet system that has been developed in our project. Second, community of workplace may as well be reexamined concerning division of labor between a supervisor and subordinates. Among all, leader behaviors of a supervisor that were effective to reduce psychological stress of subordinates, which, in turn, make positive contribution to safety culture, were identified by a questionnaire survey. Last, a minority of workers who tend to take risks for radiation exposure more seriously than the majority and share similar risk cognition with ordinary citizens may as well be utilized as linking pin that brings a warning signal from both a minority of nuclear experts outside the plant and ordinary citizens to the majority of workers in the plant who tend to be devoted to implementing everyday job. (author)

  2. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    P. E. MacDonald

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

  3. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-31

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

  4. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

  5. World nuclear power plant capacity

    International Nuclear Information System (INIS)

    1991-01-01

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

  6. Problems of implementation of the first nuclear power plant in developing countries with particular reference to Egypt

    International Nuclear Information System (INIS)

    Effat, K.E.; El-Fouly, M.F.; El-Saiedi, A.F.

    1977-01-01

    Implementation of nuclear power plants generally passes through three main phases; namely, the planning and decision to go to nuclear power, precontractual phase, and the construction phase. Each has its own particular problems that are usually encountered in developing countries, especially in implementation of the first nuclear plant. The decision to go nuclear is tied to the local and international energy market, both in the present and as projected. In the precontractual phase, which involves preparing plant specifications, invitation to tenderers, bids evaluation and negotiations with the selected vendor, problems of a different nature are encountered. Availability of qualified management, engineering, and technical personnel required to participate in design reviews, quality assurance, management, and scheduling in the construction phase is a major problem in developing countries. The paper discusses all these problems with special emphasis on the local conditions in Egypt. Our experience dealing with these issues could be of value to other developing countries

  7. 76 FR 75771 - Emergency Planning Guidance for Nuclear Power Plants

    Science.gov (United States)

    2011-12-05

    ... Guidance for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of NUREG... Support of Nuclear Power Plants;'' NSIR/DPR-ISG-01, ``Interim Staff Guidance Emergency Planning for Nuclear Power Plants;'' and NUREG/CR-7002, ``Criteria for Development of Evacuation Time Estimate Studies...

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

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  9. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  10. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  11. Seismic reevaluation of existing nuclear power plants

    International Nuclear Information System (INIS)

    Hennart, J.C.

    1978-01-01

    The codes and regulations governing Nuclear Power Plant seismic analysis are continuously becoming more stringent. In addition, design ground accelerations of existing plants must sometimes be increased as a result of discovery of faulting zones or recording of recent earthquakes near the plant location after plant design. These new factors can result in augmented seismic design criteria. Seismic reanalysius of the existing Nuclear Power Plant structures and equipments is necessary to prevent the consequences of newly postulated accidents that could cause undue risk to the health or safety of the public. This paper reviews the developments of seismic analysis as applied to Nuclear Power Plants and the methods used by Westinghouse to requalify existing plants to the most recent safety requirements. (author)

  12. Nuclear regulation. License renewal questions for nuclear plants need to be resolved

    International Nuclear Information System (INIS)

    Fultz, Keith O.; Kruslicky, Mary Ann; McDowell, William D. Jr.; Coleman, Robert L.

    1989-04-01

    A December 1986 pipe rupture at Virginia Power's Surry unit 2 nuclear power plant injured eight workers; four later died. As a result of this accident, Representative Edward J. Markey requested GAO to examine the Surry accident and assess the problems confronting aging nuclear plants. In March 1988 we reported our findings concerning the accident and a July 1987 incident at the Trojan nuclear plant in Oregon. This report addresses problems confronting aging nuclear plants by examining the Nuclear Regulatory Commission's (NRC) program to develop a license renewal policy and accompanying regulations, and the initiatives underway by the Department of Energy (DOE) and the electric utility industry to extend the operating lives of these plants. Nuclear power has become second only to coal as the largest producer of electricity in the United States. The 110 nuclear plants currently in service are operated by 54 utilities, provide about 20 percent of the nation's electricity, and represent a capital investment of over $200 billion. The Atomic Energy Act authorizes NRC to issue nuclear plant operating licenses for up to 40 years and provides for license extensions beyond the initial operating period. The act does not, however, stipulate the criteria for evaluating a utility request to operate a nuclear plant longer than 40 years. The oldest operating license currently in effect will expire in the year 2000. According to NRC, about one-half of the existing operating licenses will terminate by the year 2015, and most licenses will expire by about 2030. Many utilities will have to decide in the early 1990s whether to continue operating older nuclear plants or to construct new generating capacity. A clear understanding of the terms and conditions governing the license renewal process will be a key element in deciding how to meet future electricity demand. Although NRC has developed 3 possible license renewal policy options and identified 15 areas of regulatory uncertainty that

  13. Nuclear power. Volume 1. Nuclear power plant design

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

    NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

  14. Space nuclear power plant technology development philosophy for a ground engineering phase

    International Nuclear Information System (INIS)

    Buden, D.; Trapp, T.J.; Los Alamos National Lab., NM)

    1985-01-01

    The development of a space qualified nuclear power plant is proceeding from the technical assessment and advancement phase to the ground engineering phase. In this new phase, the selected concept will be matured by the completion of activities needed before protoflight units can be assembled and qualified for first flight applications. This paper addresses a possible philosophy to arrive at the activities to be performed during the ground engineering phase. The philosophy is derived from what we believe a potential user of nuclear power would like to see completed before commitment to a flight development phase. 5 references

  15. Space nuclear power plant technology development philosophy for a ground engineering phase

    International Nuclear Information System (INIS)

    Buden, D.; Trapp, T.J.

    1985-01-01

    The development of a space qualified nuclear power plant is proceeding from the Technical Assessment and Advancement Phase to the Ground Engineering Phase. In this new phase, the selected concept will be matured by the completion of activities needed before protoflight units can be assembled and qualified for first flight applications. This paper addresses a possible philosophy to arrive at the activities to be performed during the Ground Engineering Phase. The philosophy is derived from what we believe a potential user of nuclear power would like to see completed before commitment to a flight development phase

  16. Development of standard technical report on using and selecting wireless device in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.

    2011-11-01

    1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

  17. Development of Internal Dose Assessment Program for Nuclear Power Plant Employees

    Energy Technology Data Exchange (ETDEWEB)

    Song, Myung Jae; Kang, Duck Won; Maeng, Sung Jun; Kim, Hee Geun; Son, Soon Whan; Lim, Young Kee; Son, Joong Kwon; Park, Keyoung Rock [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jang, See Young; Ha, Jong Woo; Suh, Keyoung Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Oh, Oak Doo; Lee, Joong Woo; Yoon, Sung Sik [Yonsei University, Seoul (Korea, Republic of)

    1996-12-31

    Internal exposure monitoring based on new concept of radiation protection. Analysis and Performance test of the in vivo systems being operated in nuclear power plants in Korea. Design and fabrication of humanoid phantom for calibration of in vivo system. Development of internal dose evaluation code based on the ICRP 30 dosimetric model. (author). 44 refs., figs.

  18. Development of computer-aided design and production system for nuclear power plant

    International Nuclear Information System (INIS)

    Ishii, Masanori

    1983-01-01

    The technically required matters related to the design and production of nuclear power stations tended to increase from the viewpoint of the safety and reliability, and it is indispensable to cope with such technically required matters skillfully for the rationalization of the design and production and for the construction of highly reliable plants. Ishikawajima Harima Heavy Industries Co., Ltd., has developed the computer-aided design data information and engineering system which performs dialogue type design and drawing, and as the result, the design-production consistent system is developed to do stress analysis, production design, production management and the output of data for numerically controlled machine tools consistently. In this paper, mainly the consistent system in the field of plant design centering around piping and also the computer system for the design of vessels and others are outlined. The features of the design works for nuclear power plants, the rationalization of the design and production management of piping and vessels, and the application of the CAD system to other general equipment and improvement works are reported. This system is the powerful means to meet the requirement of heightening quality and reducing cost. (Kako, I.)

  19. Current status of nuclear power development

    International Nuclear Information System (INIS)

    Dias, P.M.

    1994-01-01

    Nuclear power is not a viable energy source for Sri Lanka at present because of a number of reasons, the main reason being the non-availability of small and economically viable nuclear power plants. However several suppliers of nuclear power plants are in the process of developing small and medium power plants (SMPRs) which could be economically competitive with coal. The paper deals with past and future trends of nuclear power plants, their economics and safety. It also deals with environmental effects and public acceptance of nuclear power plants

  20. Procedure Development and Qualification of the Phased Array Ultrasonic Testing for the Nuclear Power Plant Piping Weld

    International Nuclear Information System (INIS)

    Yoon, Byung Sik; Yang, Seung Han; Kim, Yong Sik; Lee, Hee Jong

    2010-01-01

    The manual ultrasonic examination for the nuclear power plant piping welds has been demonstrated by using KPD(Korean Performance Demonstration) generic procedure. For automated ultrasonic examination, there is no generic procedure and it should be qualified by using applicable automated equipment. Until now, most of qualified procedures used pulse-echo technique and there is no qualified procedure using phased array technique. In this study, data acquisition and analysis software were developed and phased-array transducer and wedge were designed to implement phased array technique for nuclear power plant in-service inspection. The developed procedure are qualified for performance demonstration for the flaw detection, length sizing and depth sizing. The qualified procedure will be applied for the field examination in the nuclear power plant piping weld inspection

  1. Economics of Nuclear Power Plant and the development of nuclear power in Viet Nam

    International Nuclear Information System (INIS)

    Thanh, Thuy Nguyen Thi; Song, JinHo; Ha, Kwang Soon

    2015-01-01

    There are many factors affecting the capital costs like: increased plant size, multiple unit construction, improved construct methods, increase the lifetime of plant and so on, and beside is technical to enhancing the safety for NPPs. For the question that whether building a NPP is really economic than other energy resources or not, we will find the answer by comparing the USD per kWh of different energy sources as: nuclear power, coal, oil, hydro natural energy sources. The situation of energy in Vietnam was also mentioned in this paper. Vietnam has an abundant natural resources likes: coal, gas, hydro power etc, but from year 2013 to now Vietnam facing of electricity shortage and to solve the problem, Vietnam Government has chosen nuclear power energy to achieve energy balance between the rate of energy consumption and the ability to energy supply. Eight units will be built in Vietnam and in October 2014 Vietnamese officials have chosen Rosatom's AES-2006 design with VVER-1200/v-491 reactors for country's first nuclear power plant at Ninh Thuan and a second plant should follow based on a partnership with Japan. In this paper, the breakdown of NPP costs is considered. All the costs for building a NPP includes: the investment costs are the largest components (about 60%), fuel costs (15%), O and M costs (25%) and external costs are lower than 1% of the kWh costs. The situation for energy in Vietnam was mentioned with increase annually by 5.5 %, and now the shortage electricity is the big problem in power section. The purpose of this report is to give a general picture to consider the cost of nuclear power. It includes all the costs for building a nuclear power plant like total capital investment costs, production costs, external costs in which the capital investment costs is the largest component of the kWh cost. Nuclear energy Power was chosen to deal with situation of diminishing resources shortages

  2. Economics of Nuclear Power Plant and the development of nuclear power in Viet Nam

    Energy Technology Data Exchange (ETDEWEB)

    Thanh, Thuy Nguyen Thi; Song, JinHo [University of Science and Technology, Daejeon (Korea, Republic of); Ha, Kwang Soon [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    There are many factors affecting the capital costs like: increased plant size, multiple unit construction, improved construct methods, increase the lifetime of plant and so on, and beside is technical to enhancing the safety for NPPs. For the question that whether building a NPP is really economic than other energy resources or not, we will find the answer by comparing the USD per kWh of different energy sources as: nuclear power, coal, oil, hydro natural energy sources. The situation of energy in Vietnam was also mentioned in this paper. Vietnam has an abundant natural resources likes: coal, gas, hydro power etc, but from year 2013 to now Vietnam facing of electricity shortage and to solve the problem, Vietnam Government has chosen nuclear power energy to achieve energy balance between the rate of energy consumption and the ability to energy supply. Eight units will be built in Vietnam and in October 2014 Vietnamese officials have chosen Rosatom's AES-2006 design with VVER-1200/v-491 reactors for country's first nuclear power plant at Ninh Thuan and a second plant should follow based on a partnership with Japan. In this paper, the breakdown of NPP costs is considered. All the costs for building a NPP includes: the investment costs are the largest components (about 60%), fuel costs (15%), O and M costs (25%) and external costs are lower than 1% of the kWh costs. The situation for energy in Vietnam was mentioned with increase annually by 5.5 %, and now the shortage electricity is the big problem in power section. The purpose of this report is to give a general picture to consider the cost of nuclear power. It includes all the costs for building a nuclear power plant like total capital investment costs, production costs, external costs in which the capital investment costs is the largest component of the kWh cost. Nuclear energy Power was chosen to deal with situation of diminishing resources shortages.

  3. Utilizing reliability concepts in the development of IEEE recommended good practices for nuclear plant maintenance

    International Nuclear Information System (INIS)

    Gradin, L.P.

    1986-01-01

    This paper presents information describing the concern for nuclear power plant electrical equipment maintenance and the IEEE Nuclear Power Engineering Committee's method to address that concern. That method includes the creation of Working Group 3.3, ''Maintenance Good Practices'' which is developing specific maintenance good practice documents, supporting technical information exchange, and providing a vehicle to promote practices which can reduce cost and enhance plant safety. The foundation for that effort is the utilization of Reliability concepts

  4. Nuclear power plant's safety and risk

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1975-01-01

    Starting with a comprehensive safety strategy as evolved over the past years and the present legal provisions for the construction and operation of nuclear power plants, the risk of the intended operation, of accidents and unforeseen events is discussed. Owing to the excellent safety record of nuclear power plants, main emphasis in discussing accidents is given to the precautionary analysis within the framework of the licensing procedure. In this context, hypothetical accidents are mentioned only as having been utilized for general risk comparisons. The development of a comprehensive risk concept for a completely objective safety assessment of nuclear power plants remains as a final goal. (orig.) [de

  5. Development of a daily maintenance work management system for nuclear power plants

    International Nuclear Information System (INIS)

    Yoshimura, Sadanori; Maita, Keikichi; Ogawa, Koutaro; Tabata, Nobuyuki; Shibuya, Shinya

    1999-01-01

    Maintenance work plays an important role in keeping the safety and reliability of nuclear power plants. Especially, with the recent trends of reducing the outage length, safe and reliable execution of maintenance work is more earnestly required than ever. Taking this situation into account, a daily maintenance work management system has been developed to support the execution of maintenance work for nuclear power plants. This system supports maintenance personnel in writing and approving the daily work instruction sheet and reduces their workload by providing predetermined lists of items necessary for filling up the sheet and by applying an electronic approval procedure. It also provides information through a computer network to improve the communication among maintenance personnel. For work steps to be treated in the daily work instruction sheet, an analysis was made to identify potential human errors and related counter measures, which were then linked to safety and quality assurance instructions of the sheet. Based on this information, the system automatically presents the safety and quality assurance instructions related to the work content listed in the sheet to improve the appropriateness of the instructions. A prototype of the daily maintenance work management system was developed and a trial use was made for actual periodic maintenance work at a nuclear power plant. This experience shows the usefulness of the system in reducing the workload of maintenance personnel and in providing safer work instructions. (author)

  6. 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

  7. Development of web-based integrity evaluation system for primary components in a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J. [SAFE Research Center, Sungkyunkwan Univ., Suwon (Korea); Choi, S.N.; Jang, K.S.; Hong, S.Y. [Korea Electronic Power Research Inst., Daejeon (Korea)

    2004-07-01

    A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

  8. Development of web-based integrity evaluation system for primary components in a nuclear power plant

    International Nuclear Information System (INIS)

    Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J.; Choi, S.N.; Jang, K.S.; Hong, S.Y.

    2004-01-01

    A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

  9. Development of computer program for safety of nuclear power plant against tsunami

    International Nuclear Information System (INIS)

    Jin, S. B.; Choi, K. R.; Lee, S. K.; Cho, Y. S.

    2001-01-01

    The main objective of this study is the development of a computer program to check the safety of nuclear power plants along the coastline of the Korean Peninsula. The computer program describes the propagation and associated run-up process of tsunamis by solving linear and nonlinear shallow-water equations with finite difference methods. The computer program has been applied to several ideal and simplified problems. Obtained numerical solutions are compared to existing and available solutions and measurements. A very good agreement between numerical solutions and existing measurement is observed. The computer program developed in this study can be to check the safety analysis of nuclear power plants against tsunamis. The program can also be used to study the propagation of tsunamis for a long distance, and associated run-up and run-down process along a shoreline. Furthermore, the computer program can be used to provide the proper design criteria of coastal facilities and structures

  10. China's nuclear energy demand and CGNPC's nuclear power development

    International Nuclear Information System (INIS)

    Rugang, Sh.

    2007-01-01

    By importation, assimilation and innovation from French nuclear power technology and experience, the China Guangdong Nuclear Power Plant Holding Company (CGNPC) has developed the capabilities of indigenous construction and operation of 1000 MW-class nuclear power plants. Through the industrial development over the past 20 years, four 1000 MW-class reactors have been built and put into commercial operation in China. CGNPC is negotiating with AREVA on the transfer of the EPR technology and the application of this technology for the Yangjang nuclear power plant depends on the negotiation results. Since China became a member of the 4. Generation International Forum, CGNPC as a large state-owned enterprise, will take an active part in the 4. generation nuclear power technology developments under the leadership of China Atomic Energy Authority, particularly it will contribute to the research work on the high-temperature gas-cooled reactor and on the super-critical water reactor

  11. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    1992-01-01

    The Code on Design (Safety Series 50-C-D (Rev. 1)) within the NUSS (Nuclear Safety Standards) programme of the IAEA points out the necessity of measures for protecting plant items which are important to safety against fires of internal and external origin. Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice. Figs, 1 tab

  12. Model developments for quantitative estimates of the benefits of the signals on nuclear power plant availability and economics

    International Nuclear Information System (INIS)

    Seong, Poong Hyun

    1993-01-01

    A novel framework for quantitative estimates of the benefits of signals on nuclear power plant availability and economics has been developed in this work. The models developed in this work quantify how the perfect signals affect the human operator's success in restoring the power plant to the desired state when it enters undesirable transients. Also, the models quantify the economic benefits of these perfect signals. The models have been applied to the condensate feedwater system of the nuclear power plant for demonstration. (Author)

  13. Safety goals for commercial nuclear power plants

    International Nuclear Information System (INIS)

    Roe, J.W.

    1988-01-01

    In its official policy statement on safety goals for the operation of nuclear power plants, the Nuclear Regulatory Commission (NRC) set two qualitative goals, supported by two quantitative objectives. These goals are that (1) individual members of the public should be provided a level of protection from the consequences of nuclear power plant operation such that individuals bear no significant additional risk to life and health; and (2) societal risks to life and health from nuclear power plant operation should be comparable to or less than the risks of generating electricity by viable competing technologies and should not be a significant addition to other societal risks. As an alternative, this study proposes four quantitative safety goals for nuclear power plants. It begins with an analysis of the NRC's safety-goal development process, a key portion of which was devoted to delineating criteria for evaluating goal-development methods. Based on this analysis, recommendations for revision of the NRC's basic benchmarks for goal development are proposed. Using the revised criteria, NRC safety goals are evaluated, and the alternative safety goals are proposed. To further support these recommendations, both the NRC's goals and the proposed goals are compared with the results of three major probabilistic risk assessment studies. Finally, the potential impact of these recommendations on nuclear safety is described

  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. ALARA at nuclear power plants

    International Nuclear Information System (INIS)

    Baum, J.W.

    1991-01-01

    Implementation of the ALARA principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed through a variety of dose reduction techniques. Initiatives by the ICRP, NCRP, NRC, INPO, EPRI, and BNL ALARA Center have all contributed to a heightened interest and emphasis on dose reduction. The NCRP has formed Scientific Committee 46-9 which is developing a report on ALARA at Nuclear Power Plants. It is planned that this report will include material on historical aspects, management, valuation of dose reduction ($/person-Sv), quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report

  17. Development of vendor independent safety analysis capability for nuclear power plants in Taiwan

    International Nuclear Information System (INIS)

    Tang, J.-R.

    2001-01-01

    The Institute of Nuclear Energy Research (INER) and the Taiwan Power Company (TPC) have long-term cooperation to develop vendor independent safety analysis capability to provide support to nuclear power plants in Taiwan in many aspects. This paper presents some applications of this analysis capability, introduces the analysis methodology, and discusses the significance of vendor independent analysis capability now and future. The applications include a safety analysis of core shroud crack for Chinshan BWR/4 Unit 2, a parallel reload safety analysis of the first 18-month extended fuel cycle for Kuosheng BWR/6 Unit 2 Cycle 13, an analysis to support Technical Specification change for Maanshan three-loop PWR, and a design analysis to support the review of Preliminary Safety Analysis Report of Lungmen ABWR. In addition, some recent applications such as an analysis to support the review of BWR fuel bid for Chinshan and Kuosheng demonstrates the needs of further development of the analysis capability to support nuclear power plants in the 21 st century. (authors)

  18. Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

    Energy Technology Data Exchange (ETDEWEB)

    Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

    1983-02-01

    This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants.

  19. Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

    International Nuclear Information System (INIS)

    Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

    1983-02-01

    This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants

  20. 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

  1. Arguments for the installation of small LWR nuclear power plants in developing countries

    International Nuclear Information System (INIS)

    Lezenik, B.

    1977-01-01

    soft- and hardware according to the latest state of technical developement, different procedures of awarding are selected, depending on the nuclear experience of the electric utility. An analysis and comparison show the advantages and disadvantages of the usual awarding procedures and possibilities of having the national industry take part in the construction of a plant are discussed

  2. 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)

  3. Development of hydrogeological modelling approaches for assessment of consequences of hazardous accidents at nuclear power plants

    International Nuclear Information System (INIS)

    Rumynin, V.G.; Mironenko, V.A.; Konosavsky, P.K.; Pereverzeva, S.A.

    1994-07-01

    This paper introduces some modeling approaches for predicting the influence of hazardous accidents at nuclear reactors on groundwater quality. Possible pathways for radioactive releases from nuclear power plants were considered to conceptualize boundary conditions for solving the subsurface radionuclides transport problems. Some approaches to incorporate physical-and-chemical interactions into transport simulators have been developed. The hydrogeological forecasts were based on numerical and semi-analytical scale-dependent models. They have been applied to assess the possible impact of the nuclear power plants designed in Russia on groundwater reservoirs

  4. Medium-size nuclear plants

    International Nuclear Information System (INIS)

    Vogelweith, L.; Lavergne, J.C.; Martinot, G.; Weiss, A.

    1977-01-01

    CEA (TECHNICATOME) has developed a range of pressurized water reactors of the type ''CAS compact'' which are adapted to civil ship propulsion, or to electric power production, combined possibly with heat production, up to outputs equivalent to 125 MWe. Nuclear plants equipped with these reactors are suitable to medium-size electric networks. Among the possible realizations, two types of plants are mentioned as examples: 1) Floating electron-nuclear plants; and 2) Combined electric power and desalting plants. The report describes the design characteristics of the different parts of a 125 MWe unit floating electro-nuclear plant: nuclear steam system CAS 3 G, power generating plant, floating platform for the whole plant. The report gives attention to the different possibilities according to site conditions (the plant can be kept floating, in a natural or artificial basin, it can be put aground, ...) and to safety and environment factors. Such unit can be used in places where there is a growing demand in electric power and fresh water. The report describes how the reactor, the power generating plant and multiflash distillation units of an electric power-desalting plant can be combined: choice of the ratio water output/electric power output, thermal cycle combination, choice of the gain ratio, according to economic considerations, and to desired goal of water output. The report analyses also some technical options, such as: choice of the extraction point of steam used as heat supply of the desalting station (bleeding a condensation turbine, or recovering steam at the exhaust of a backpressure turbine), design making the system safe. Lastly, economic considerations are dealt with: combining the production of fresh water and electric power provides usually a much better energy balance and a lower cost for both products. Examples are given of some types of installations which combine medium-size reactors with fresh water stations yielding from 10000 to 120000 m 3 per day

  5. Implementation of nuclear power plant in a developing country - the case of Turkey

    International Nuclear Information System (INIS)

    Aybers, N.

    1996-01-01

    This paper discusses problems encountered in the integration of the first nuclear power plant in Turkey. Past activities and the current situation is reviewed, special problems associated with the Akkuyu project are discussed, and topics such as optimal size selection, policy for nuclear fuel cycle, choice of reactor type, and regulatory matters are discussed. It is concluded that the introduction of a well-planned, long-term, economically viable nuclear power program into a developing country is a difficult task, which can be accomplished only through effective organization. (author). 7 refs., 4 tabs., 2 figs

  6. Implementation of nuclear power plant in a developing country - the case of Turkey

    International Nuclear Information System (INIS)

    Aybers, N.

    1996-01-01

    This paper discusses problems encountered in the integration of the first nuclear power plant in Turkey. Past activities and the current situation is reviewed, special problems associated with the AKKUYU project are discussed, and topics such as optimal size selection, policy for nuclear fuel cycle, choice of reactor type, and regulatory matters are discussed. It is concluded that the introduction of a well-planned, long-term, economically viable nuclear power program into a developing country is a difficult task, which can be accomplished only through effective organization. (author)

  7. Development of safety assessment of nuclear power plants using indicators; Ydinvoimalaitosten turvallisuuden arvioinnin kehittaeminen tunnuslukujen avulla

    Energy Technology Data Exchange (ETDEWEB)

    Tiippana, P.

    1997-11-01

    The study is based on an indicator system which is under development at the Radiation and Nuclear Safety Authority (STUK). The goal of this study was to define and develop both PSA-based indicators and indicators from failure statistics. As PSA-based indicators the possibility was studied to define and express the risk importance of exemptions from the Technical Specifications, failures, preventive maintenance and other disconnections of devices covered by the Technical Specifications, operating events covered by Guide YVL 1.5 and plant modifications. In this piece of research the applicability of plant specific living PSA-models used for calculation of indicators was examined. The research included both Loviisa and Olkiluoto nuclear power plants in Finland. 47 refs.

  8. Nuclear plant simulation using the Nuclear Plant Analyzer

    International Nuclear Information System (INIS)

    Beelman, R.J.; Laats, E.T.; Wagner, R.J.

    1984-01-01

    The Nuclear Plant Analyzer (NPA), a state-of-the-art computerized safety analysis and engineering tool, was employed to simulate nuclear plant response to an abnormal transient during a training exercise at the US Nuclear Regulatory Commission (USNRC) in Washington, DC. Information relative to plant status was taken from a computer animated color graphics display depicting the course of the transient and was transmitted to the NRC Operations Center in a manner identical to that employed during an actual event. Recommendations from the Operations Center were implemented during on-line, interactive execution of the RELAP5 reactor systems code through the NPA allowing a degree of flexibility in training exercises not realized previously. When the debriefing was conducted, the RELAP5 calculations were replayed by way of the color graphics display, adding a new dimension to the debriefing and greatly enhancing the critique of the exercise

  9. Development of stainless steels for nuclear power plant - Advanced nuclear materials development -

    International Nuclear Information System (INIS)

    Hong, Jun Hwa; Ryu, Woo Seog; Chi, Se Hwan; Lee, Bong Sang; Oh, Yong Jun; Byun, Thak Sang; Oh, Jong Myung

    1994-07-01

    This report reviews the status of R and D and the material specifications of nuclear components in order to develop the stainless steels for nuclear applications, and the technology of computer-assisted alloy design is developed to establish the thermodynamic data of Fe-Cr-Ni-Mo-Si-C-N system which is the basic stainless steel systems. High strength and corrosion resistant stainless steels, 316LN and super clean 347, are developed, and the manufacturing processes and heat treatment conditions are determined. In addition, a martensitic steel is produced as a model alloy for turbine blade, and characterized. The material properties showed a good performance for nuclear applications. (Author)

  10. 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

  11. Development of Czechoslovak nuclear power complex

    International Nuclear Information System (INIS)

    Rajci, T.

    1986-01-01

    The research project ''Development of the Czechoslovak nuclear power complex'' was undertaken by several Czechoslovak institutions and was coordinated by the Research Institute of the Fuel and Power Complex in Bratislava. Involved in the project was a staff of 170 people. 274 reports were pulished and the cost approached 70 mill. Czechoslovak crowns. The results are characterized of all six partial tasks. Basic information was prepared for the forecast of the solution of fuel and power problems in Czechoslovakia up to the year 2000 and their prospects up to the year 2020. Program MORNAP was written for the development of nuclear power, which models the operation of a power generation and transmission system with a selectable number of nuclear power plants. Another partial task related to the fuel cycle of nuclear power plants with respect to long-term provision and management of nuclear fuel. Nuclear safety was split into three problem groups, viz.: system safety of nuclear power plant operation; radiation problems of nuclear power plant safety; quality assurance of nuclear power plant components. The two remaining tasks were devoted to nuclear power engineering and to civil engineering. (Z.M.). 3 tabs., 1 refs

  12. Development of alarm cause tracking system for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Kim, Jung Taek; Park, Jae Chang; Lee, Hyun Chul; Park, Joong Pal

    2004-05-01

    The proposed system, the ACTS(Alarm Cause Tracking System), in the 1st and 2nd development period(2001. 7 ∼ 2003. 6), tracks and displays the causes of alarms on-line from computerized logic diagrams. And the system highlights the specific procedures related the causes in the procedure of the alarm. In this period(2003. 7 ∼ 2004. 4), we developed the ACTS for Korea standard nuclear power plant. Also, we computerized control logic diagrams and alarm procedures for the ACTS. A long-term target is to apply the ACTS at the real power plant, and a short-term target is to connect the ACTS with the ITF(Intergrated Test Facility) in KAERI site to develop other applications

  13. In-plant reliability data base for nuclear power plant components: data collection and methodology report

    International Nuclear Information System (INIS)

    Drago, J.P.; Borkowski, R.J.; Pike, D.H.; Goldberg, F.F.

    1982-07-01

    The development of a component reliability data for use in nuclear power plant probabilistic risk assessments and reliabiilty studies is presented in this report. The sources of the data are the in-plant maintenance work request records from a sample of nuclear power plants. This data base is called the In-Plant Reliability Data (IPRD) system. Features of the IPRD system are compared with other data sources such as the Licensee Event Report system, the Nuclear Plant Reliability Data system, and IEEE Standard 500. Generic descriptions of nuclear power plant systems formulated for IPRD are given

  14. Pre-fire planning for nuclear power plants

    International Nuclear Information System (INIS)

    Talbert, J.H.

    1980-01-01

    Regardless of the fire prevention measures which are taken, plant experience indicates that fires will occur in a nuclear power plant. When a fire occurs, the plant staff must handle the fire emergency. Pre-fire planning is a method of developing detailed fire attack plans and salvage operations to protect equipment from damage due to fire and fire fighting operations. This paper describes the purpose and use of a pre-fire plan to achieve these goals in nuclear power plants

  15. Nuclear power for developing countries

    International Nuclear Information System (INIS)

    Hirschmann, H.; Vennemann, J.

    1980-01-01

    The paper describes the energy policy quandary of developing countries and explains why nuclear power plants of a suitable size - the KKW 200 MW BWR nuclear power plant for electric power and/or process steam generation is briefly presented here - have an economic advantage over fossil-fuelled power plants. (HP) [de

  16. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Pack, R.W.

    1978-01-01

    The Electric Power Research Institute has started research in human factors in nuclear power plants. One project, completed in March 1977, reviewed human factors problems in operating power plants and produced a report evaluating those problems. A second project developed computer programs for evaluating operator performance on training simulators. A third project is developing and evaluating control-room design approaches. A fourth project is reviewing human factors problems associated with power-plant maintainability and instrumentation and control technician activities. Human factors engineering is an interdisciplinary specialty concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. The Electric Power Research Institute (EPRI) has undertaken four projects studying the application of human factors engineering principles to nuclear power plants. (author)

  17. Nuclear Power Plant Control and Instrumentation in Pakistan

    International Nuclear Information System (INIS)

    Iqleem, J.; Hashmi, J.A.; Siddiqui, Z.H.

    1990-01-01

    Nuclear reactors generate 15% of the world's supply electric power. The substantial growth in world energy demand is inevitably continuing throughout the next century. Nuclear power which has already paid more than enough for itself and its development, will provide increasing share of electricity production both in the developed and developing countries. For Pakistan with limited natural resources such as oil, gas, and fully tapped hydel power, nuclear power is the only viable option. However, things are not simple for developing countries which embark on nuclear power program. A technical infrastructure should be established as it has been shown by the experience of Control and Instrumentation of the Karachi Nuclear Power Plant. The national report describes the program of Pakistan Atomic Energy Commission in (NPP) Computers, Control and Instrumentation for design, construction, operation, and maintenance of nuclear power plants. (author)

  18. Nuclear plant fire incident data file

    International Nuclear Information System (INIS)

    Sideris, A.G.; Hockenbury, R.W.; Yeater, M.L.; Vesely, W.E.

    1979-01-01

    A computerized nuclear plant fire incident data file was developed by American Nuclear Insurers and was further analyzed by Rensselaer Polytechnic Institute with technical and monetary support provided by the Nuclear Regulatory Commission. Data on 214 fires that occurred at nuclear facilities have been entered in the file. A computer program has been developed to sort the fire incidents according to various parameters. The parametric sorts that are presented in this article are significant since they are the most comprehensive statistics presently available on fires that have occurred at nuclear facilities

  19. 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

  20. Development of Web-Based Common Cause Failure (CCF) Database Module for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-young [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

    2015-05-15

    Probabilistic safety assessment (PSA) has been used to identify risk vulnerabilities and derive the safety improvement measures from construction to operation stages of nuclear power plants. In addition, risk insights from PSA can be applied to improve the designs and operation requirements of plants. However, reliability analysis methods for quantitative PSA evaluation have essentially inherent uncertainties, and it may create a distorted risk profiles because of the differences among the PSA models, plant designs, and operation status. Therefore, it is important to ensure the quality of the PSA model so that analysts identify design vulnerabilities and utilize risk information. Especially, the common cause failure (CCF) has been pointed out as one of major issues to be able to cause the uncertainty related to the PSA analysis methods and data because CCF has a large influence on the PSA results. Organization for economic cooperation and development /nuclear energy agent (OECD/NEA) has implemented an international common cause failure data exchange (ICDE) project for the CCF quality assurance through the development of the detailed analysis methodologies and data sharing. However, Korea Hydro and Nuclear Power company (KHNP) does not have the basis for the data gathering and analysis for CCF analyses. In case of methodology, the Alpha Factor parameter estimation, which can analyze uncertainties and estimate an interface factor (Impact Vector) with an ease, is ready to be applied rather than the Multi Greek Letter (MGL) method. This article summarizes the development of the plant-specific CCF database (DB) module considering the raw data collection and the analysis procedure based on the CCF parameter calculation method of ICDE. Although the portion affected by CCF in the PSA model is quite a large, the development efforts of the tools to collect and analyze data were insufficient. Currently, KHNP intends to improve PSA quality and ensure CCF data reliability by

  1. Development of Web-Based Common Cause Failure (CCF) Database Module for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-young

    2015-01-01

    Probabilistic safety assessment (PSA) has been used to identify risk vulnerabilities and derive the safety improvement measures from construction to operation stages of nuclear power plants. In addition, risk insights from PSA can be applied to improve the designs and operation requirements of plants. However, reliability analysis methods for quantitative PSA evaluation have essentially inherent uncertainties, and it may create a distorted risk profiles because of the differences among the PSA models, plant designs, and operation status. Therefore, it is important to ensure the quality of the PSA model so that analysts identify design vulnerabilities and utilize risk information. Especially, the common cause failure (CCF) has been pointed out as one of major issues to be able to cause the uncertainty related to the PSA analysis methods and data because CCF has a large influence on the PSA results. Organization for economic cooperation and development /nuclear energy agent (OECD/NEA) has implemented an international common cause failure data exchange (ICDE) project for the CCF quality assurance through the development of the detailed analysis methodologies and data sharing. However, Korea Hydro and Nuclear Power company (KHNP) does not have the basis for the data gathering and analysis for CCF analyses. In case of methodology, the Alpha Factor parameter estimation, which can analyze uncertainties and estimate an interface factor (Impact Vector) with an ease, is ready to be applied rather than the Multi Greek Letter (MGL) method. This article summarizes the development of the plant-specific CCF database (DB) module considering the raw data collection and the analysis procedure based on the CCF parameter calculation method of ICDE. Although the portion affected by CCF in the PSA model is quite a large, the development efforts of the tools to collect and analyze data were insufficient. Currently, KHNP intends to improve PSA quality and ensure CCF data reliability by

  2. Availability improvement factors at Taipower's nuclear power plant system

    International Nuclear Information System (INIS)

    Chen, J.H.

    1985-01-01

    Sufficient electricity to meet the needs of a growing industrial economy, is one of the most important factors in the total economic development of a nation. Currently, nuclear power is considered one of the most economical and available sources of energy. To keep pace with Taiwan's rapid economic development, while also observing our government's policy of diversifying the requirements for imported forms of energy, Taiwan Power Company has embarked upon an ambitious of nuclear power plant construction. This paper discusses the improvement of Taiwan's nuclear power plants. At the present time, Taipower has completed three nuclear power plants. Two of these are located in northern Taiwan, along the East China Sea, while the third is on the southern tip of Taiwan, bordering the South China Sea. These three plants, each with two nuclear generating units, comprise a total nuclear generating capacity of 5144 MWe

  3. Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant (Part II)

    International Nuclear Information System (INIS)

    Park, Un Su; Park, Ik Keun; Um, Byong Guk; Lee, Jong Po; Han, Chi Hyun

    2000-01-01

    In a previous paper, we have discussed the intelligent Windows 95-based data management program(IDPIN) which was developed for effective and efficient management of large amounts of pre-/in-service inspection(PSI/ISI) data of Kori nuclear power plants. The IDPIN program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis of the past are avoided. In this study, the intelligent Windows based data management program(WS-IDPIN) has been developed as an effective data management of PSI/ISI data for the Wolsong nuclear power plants. The WS-IDPIN program includes the modules of comprehensive management and analysis of PSI/ISI results, statistical reliability assessment program of PSI/ISI results(depth and length sizing performance etc), standardization of UT report form and computerization of UT results. In addition, the program can be further developed as a unique PSI/ISI data management expert system which can be part of the PSI/ISI total support system for Korean nuclear power plants

  4. Nuclear plants gain integrated information systems

    International Nuclear Information System (INIS)

    Villavicencio-Ramirez, A.; Rodriquez-Alvarez, J.M.

    1994-01-01

    With the objective of simplifying the complex mesh of computing devices employed within nuclear power plants, modern technology and integration techniques are being used to form centralized (but backed up) databases and distributed processing and display networks. Benefits are immediate as a result of the integration and the use of standards. The use of a unique data acquisition and database subsystem optimizes the high costs of engineering, as this task is done only once for the life span of the system. This also contributes towards a uniform user interface and allows for graceful expansion and maintenance. This article features an integrated information system, Sistema Integral de Informacion de Proceso (SIIP). The development of this system enabled the Laguna Verde Nuclear Power plant to fully use the already existing universe of signals and its related engineering during all plant conditions, namely, start up, normal operation, transient analysis, and emergency operation. Integrated systems offer many advantages over segregated systems, and this experience should benefit similar development efforts in other electric power utilities, not only for nuclear but also for other types of generating plants

  5. A common high standard for nuclear power plant exports: overview and analysis of the Nuclear Power Plant Exporters' Principles of Conduct

    International Nuclear Information System (INIS)

    Perkovich, George; Radzinsky, Brian

    2012-01-01

    At this time, there is no overarching global framework to regulate the development of the nuclear power industry. Laws concerning the export of nuclear technology vary across jurisdictions, and politically-binding arrangements such as the Nuclear Suppliers Group (NSG) help ensure that weapons-usable or dual-use technologies are not exported, but no single international regime or agreement manages the gamut of potential risks that may arise from the export of civilian nuclear power plants. Accordingly in 2008, the Carnegie Endowment for International Peace convened internationally-recognised experts in nuclear energy to begin a dialogue with nuclear power plant vendors about defining common criteria for the socially responsible export of nuclear power plants. The goal was to articulate a comprehensive set of principles and best practices that would raise the overall standard of practice for exports of nuclear power plants while enjoying widespread support and adherence. The outcome of this process is the Nuclear Power Plant Exporters' Principles of Conduct - an export-oriented code of conduct for nuclear power plant vendors. The Principles of Conduct help ensure that the participating companies will proceed with the sale of a new nuclear power plant only after a careful assessment of the legal, political, and technical contexts surrounding potential customers. It comprises six 'principles' that each address a major area of concern involved in the export of a nuclear power plant: safety, physical security, environmental protection and spent fuel management, systems of compensation for nuclear damage, non-proliferation and safeguards, and business ethics. The Principles of Conduct entail vendor responsibilities to apply specific standards or engage in certain practices before signing contracts and during the marketing and construction phases of a nuclear power plant export project. Conformity with the Principles of Conduct is voluntary and not-legally binding, but the

  6. Role and position of Nuclear Power Plants Research Institute in nuclear power industry

    International Nuclear Information System (INIS)

    Metke, E.

    1984-01-01

    The Nuclear Power Plants Research Institute carries out applied and experimental research of the operating states of nuclear power plants, of new methods of surveillance and diagnosis of technical equipment, it prepares training of personnel, carries out tests, engineering and technical consultancy and the research of automated control systems. The main research programme of the Institute is the rationalization of raising the safety and operating reliability of WWER nuclear power plants. The Institute is also concerned with quality assurance of selected equipment of nuclear power plants and assembly works, with radioactive waste disposal and the decommissioning of nuclear power plants as well as with the preparation and implementation of the nuclear power plant start-up. The Research Institute is developing various types of equipment, such as equipment for the decontamination of the primary part of the steam generator, a continuous analyzer of chloride levels in water, a gas monitoring instrument, etc. The prospects are listed of the Research Institute and its cooperation with other CMEA member countries. (M.D.)

  7. Development of experimental method to simulate the corrosion products in the primary system of nuclear power plant

    International Nuclear Information System (INIS)

    Kim, Sang Hyun; Kim, In Sup; Jang, Chang Heui

    2005-01-01

    Corrosion products are recognized as one of the major sources of occupational radiation exposure for nuclear power plant workers. Numerous studies have been conducted on the primary water chemistry to reduce the amount of crud in the primary circuit to avoid the radioactivity build-up in the plant. However, experiments with crud are restricted in laboratory because the crud is highly radioactive material. The objective of this study is to develop the simulating method of corrosion product in nuclear power plant

  8. 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

  9. 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

  10. Nuclear power plants 1995 - a world survey

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

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

  11. Development of a remote controlled robot system for monitoring nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Song, Myung Jae; Shin, Hyun Bum; Oh, Gil Hwan; Maeng, Sung Jun; Choi, Byung Jae; Chang, Tae Woo [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Lee, Bum Hee; Yoo, Jun; Choi, Myung Hwan; Go, Nak Yong; Lee, Kee Dong; Lee, Young Dae; Cho, Hae Kyeng; Nam, Yoon Suk [Electric and Science Research Center, (Korea, Republic of)

    1996-12-31

    It`s a final report of the development of remote controlled robot system for monitoring the facilities in nuclear power plant and contains as follows, -Studying the technologies in robot developments and analysing the requirements and working environments - Development of the test mobile robot system - Development of the mobile-robot - Development of the Mounted system on the Mobile robot - Development of the Monitoring system - Mobil-robot applications and future study. In this study we built the basic technologies and schemes for future robot developments and applications. (author). 20 refs., figs.

  12. Effort on Nuclear Power Plants safety

    International Nuclear Information System (INIS)

    Prayoto.

    1979-01-01

    Prospects of nuclear power plant on designing, building and operation covering natural safety, technical safety, and emergency safety are discussed. Several problems and their solutions and nuclear energy operation in developing countries especially control and permission are also discussed. (author tr.)

  13. 3D visualization based customer experiences of nuclear plant control room

    International Nuclear Information System (INIS)

    Sun Tienlung; Chou Chinmei; Hung Tamin; Cheng Tsungchieh; Yang Chihwei; Yang Lichen

    2011-01-01

    This paper employs virtual reality (VR) technology to develop an interactive virtual nuclear plant control room in which the general public could easily walk into the 'red zone' and play with the control buttons. The VR-based approach allows deeper and richer customer experiences that the real nuclear plant control room could not offer. When people know more about the serious process control procedures enforced in the nuclear plant control room, they will appropriate more about the safety efforts imposed by the nuclear plant and become more comfortable about the nuclear plant. The virtual nuclear plant control room is built using a 3D game development tool called Unity3D. The 3D scene is connected to a nuclear plant simulation system through Windows API programs. To evaluate the usability of the virtual control room, an experiment will be conducted to see how much 'immersion' the users could feel when they played with the virtual control room. (author)

  14. Safety and regulatory requirements of nuclear power plants

    International Nuclear Information System (INIS)

    Kumar, S.V.; Bhardwaj, S.A.

    2000-01-01

    A pre-requisite for a nuclear power program in any country is well established national safety and regulatory requirements. These have evolved for nuclear power plants in India with participation of the regulatory body, utility, research and development (R and D) organizations and educational institutions. Prevailing international practices provided a useful base to develop those applicable to specific system designs for nuclear power plants in India. Their effectiveness has been demonstrated in planned activities of building up the nuclear power program as well as with unplanned activities, like those due to safety related incidents etc. (author)

  15. Nuclear renaissance in Asia. Energy security and development of nuclear power generation system

    International Nuclear Information System (INIS)

    Nakasugi, Hideo

    2009-01-01

    The energy policy and strategy of development of nuclear power generation system of China, India and Korea are stated on the basis of use of light water reactors (LWRs). The conditions of power generation and introduction plans of nuclear energy of other Asian countries such as Vietnam, Thailand, Indonesia, Malaysia and Philippines are described. The power plant capacity of China increased from 50,500 MW in 2004, to 65,000 MW in 2005, and the target value is 40,000 MW of operating nuclear plants and 18,000 MW in building in 2020. China is lagging behind in peaceful use of nuclear energy technologies. A plan for the reform of nuclear industry and nuclear power generation projects of China are summarized. Total power plant capacity of India is 145,000 MW, but the nuclear plant capacity is 4,120 MW in 2008 and 63,000 MW of the target in 2032. Development of nuclear power, circumstance, and cooperation with other countries' industries are explained. 17,716 MW of nuclear power is in operation, 6,800 MW in building and 2,800 MW in the planning stage in Korea. History of development of national reactors and the subjects of development of the fourth generation reactor of Korea are stated. Management system of nuclear power plants in China, technical bases of nuclear power plants in China, development system of nuclear power generation in India, the conditions of power production of Korea in 2008, the capacity factor of Korea, Japan and world from 1998 to 2008, and comparison of nuclear industries in China, India and Korea are illustrated. (S.Y.)

  16. Experiences in the development of an emergency response facility (ERF) system for a nuclear power plant

    International Nuclear Information System (INIS)

    Seisdedos, A.; Sanchez-Fornie, M.A.

    1985-01-01

    The TMI-2 accident gave rise to a series of new requirements with which Nuclear Power Plants must comply and amongst which the implementation of emergency response facilities, particularly the SPDS, has received special attention. This paper covers the experience and problems encountered in the developing of the engineering necessary for the detailed definition of the ERF in a Nuclear Power Plant in the commercial operation phase. Also, a real example is provided for the case of a plant in the last phase of construction and installation. This will serve to illustrate each of the topics covered. (author)

  17. A PIP chart for nuclear plant safety

    International Nuclear Information System (INIS)

    Suzuki, Tatsujiro; Yamaoka, Taiji

    1992-01-01

    While it is known that social and political aspects of nuclear safety issues are important, little study has been done on identifying the breadth of stakeholders whose policies have important influences over nuclear plant safety in a comprehensive way. The objectives of this study are to develop a chart that visually identifies important stakeholders and their policies and illustrates these influences in a hierarchical representation so that the relationship between stakeholders and nuclear safety will be better understood. This study is based on a series of extensive interviews with major stakeholders, such as nuclear plant managers, corporate planning vice presidents, state regulators, news media, and public interest groups, and focuses on one US nuclear power plant. Based on the interview results, the authors developed a conceptual policy influence paths (PIP) chart. The PIP chart illustrates the hierarchy of influence among stakeholders. The PIP chart is also useful in identifying possible stakeholders who can be easily overlooked without the PIP chart. In addition, it shows that influence flow is circular rather than linear in one direction

  18. Development of Nuclear Plant Specific Analysis Simulators with ATLAS

    International Nuclear Information System (INIS)

    Jakubowski, Z.; Draeger, P.; Horche, W.; Pointner, W.

    2006-01-01

    The simulation software ATLAS, based on the best-estimate code ATHLET, has been developed by the GRS for a range of applications in the field of nuclear plant safety analysis. Through application of versatile simulation tools and graphical interfaces the user should be able to analyse with ATLAS all essential accident scenarios. Detailed analysis simulators for several German and Russian NPPs are being constructed on the basis of ATLAS. An overview of the ATLAS is presented in the paper, describing its configuration, functions performed by main components and relationships among them. A significant part of any power plant simulator are the balance-of-plant (BOP) models, not only because all the plant transients and non-LOCA accidents can be initiated by operation of BOP systems, but also because the response of the plant to transients or accidents is strongly influenced by the automatic operation of BOP systems. Modelling aspects of BOP systems are shown in detail, also the interface between the process model and BOP systems. Special emphasis has been put on the BOP model builder based on the methodology developed in the GRS. The BOP modeler called GCSM-Generator is an object oriented tool which runs on the online expert system G2. It is equipped with utilities to edit the BOP models, to verification them and to generate a GCSM code, specific for the ATLAS. The communication system of ATLAS presents graphically the results of the simulation and allows interactively influencing the execution of the simulation process (malfunctions, manual control). Displays for communications with simulated processes and presentation of calculations results are also presented. In the framework of the verification of simulation models different tools are used e.g. the PC-codes MATHCAD for the calculation and documentation, ATLET-Input-Graphic for control of geometry data and the expert system G2 for development of BOP-Models. The validation procedure and selected analyses results

  19. 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

  20. 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.)

  1. Worldwide nuclear-plant performance

    International Nuclear Information System (INIS)

    Surrey, J.; Thomas, S.

    1980-01-01

    The authors compare the performance of different reactor systems to identify the determinants of plant performance, to examine the evidence of technological maturation, and to discover the principal causes of outage or unavailability. In the light of the findings, they discuss the implications for the UK regarding reactor choice and technology development. They make no judgements about the relative merits of nuclear and fossil-fuel plants, or about safety. (author)

  2. Technical Meeting/Workshop on Topical Issues on Infrastructure Development: Managing the Development of a National Infrastructure for Nuclear Power Plants. Presentations

    International Nuclear Information System (INIS)

    2012-01-01

    The main purpose of the TM/Workshop is to provide an opportunity for exchange of specific information on the management of the development of a sustainable national infrastructure for Nuclear Power Plants as it is recommended in the Agency's Milestones approach. Taking into account the actual status of new nuclear power programmes in Member States, this Agency event shall focus on the moving beyond the consideration of the nuclear power and advancing to the next phase, when future partners (Consultants, NPP Vendors, EPC Contractors, etc.) shall be selected and contracted for the first Nuclear Power Plant. The objectives of the Technical Meeting/Workshop are the following: 1. To exchange specific information and to facilitate the management and coordination of the development and implementation of a national infrastructure for nuclear power; 2. To present and discuss case studies, good practices and lessons learned about recent experiences in implementing an appropriate infrastructure for nuclear power, including management methods and self-evaluation processes; 3. To allow participants to improve their knowledge of various aspects of nuclear infrastructure development; and 4. To provide a forum in which participants can discuss common challenges, opportunities for cooperation, concerns and issues their countries face in the infrastructure implementation process.

  3. Abnormality diagnostic technology for nuclear power plants

    International Nuclear Information System (INIS)

    Ishikawa, Satoshi

    1986-01-01

    In nuclear power plants, it is feared that the failure of the installations containing radioactive substances may inflict serious damage on public and workers. Therefore in nuclear power plants, the ensuring of safety is planned by supposing hypothetical accidents which are not likely to occur from engineering viewpoint, and multiple protection measures are taken in the plant constitution. In addition to the safety measures from such hardware aspect, recently in order to prevent the occurrence of accidents by using various safety-confirming means, and to detect early when any accident occurred, the development and putting in practical use of many monitoring equipments have been promoted. In such background, the development of nuclear power generation supporting system was carried out for five years since fiscal year 1980, subsidized by the Ministry of International Trade and Industry, and in this report, the technology of equipment abnormality diagnosis developed as a part of that project and the diagnostic techniques for actual plants are described. The technology of diagnosing nuclear reactor abnormality includes the diagnosis of loose metal pieces and the abnormal vibration of in-core structures. The detection and diagnosis of valve leak and the diagnosis of the deterioration of detectors are also explained. (Kako, I.)

  4. CANDU 9 nuclear power plant simulator

    International Nuclear Information System (INIS)

    Kattan, M.; MacBeth, M.J.; Lam, K.

    1995-01-01

    Simulators are playing, an important role in the design and operations of CANDU reactors. They are used to analyze operating procedures under standard and upset conditions. The CANDU 9 nuclear power plant simulator is a low fidelity, near full scope capability simulator. It is designed to play an integral part in the design and verification of the control centre mock-up located in the AECL design office. It will also provide CANDU plant process dynamic data to the plant display system (PDS), distributed control system (DCS) and to the mock-up panel devices. The simulator model employs dynamic mathematical models of the various process and control components that make up a nuclear power plant. It provides the flexibility to add, remove or update user supplied component models. A block oriented process input is provided with the simulator. Individual blocks which represent independent algorithms of the model are linked together to generate the required overall plant model. As a design tool the simulator will be used for control strategy development, human factors studies (information access, readability, graphical display design, operability), analysis of overall plant control performance, tuning estimates for major control loops and commissioning strategy development. As a design evaluation tool, the simulator will be used to perform routine and non-routine procedures, practice 'what if' scenarios for operational strategy development, practice malfunction recovery procedures and verify human factors activities. This paper will describe the CANDU 9 plant simulator and demonstrate its implementation and proposed utility as a tool in the control system and control centre design of a CANDU 9 nuclear power plant. (author). 2 figs

  5. Development and recent trend of design of BWR nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kani, J [Tokyo Shibaura Electric Co. Ltd., Kawasaki, Kanagawa (Japan)

    1977-11-01

    Many improvements have been carried out in BWR nuclear power plants from BWR-1, represented by Dresden No. 1 plant, to the present BWR-6 as the capacity has increased. In Japan, the plants up to BWR-5 have been constructed. In addition, further fine design improvements are being performed in the complete domestic manufacturing of BRWs based on the operational experiences to date. A variety of investigations on the standardization of nuclear power facilities have been progressing under the leadership of Japanese Ministry of International Trade and Industry since 1975. In this standardization, it is intended to forward the plant design taking eight concrete items into consideration, mainly aiming at carrying cut unerringly the maintenance and inspection, reduction of exposure of employees to radiation, and improvements of the rate of operation of plants and equipment reliability. The containment vessel has been developed in three forms, from Mark 1 through 3, adopting the pressure control system consistently since BWR-2. Mark 1 and 2 were constructed in Japan. However, these designs sacrificed the workability and increased radiation exposure during maintenance as a result of placing emphasis on the safety facilities, therefore Toshiba Electric has investigated the advanced Mark 1 type. Its features are the design for improving the work efficiency in a containment vessel, reducing the radiation exposure of workers, shortening plant construction period, and considering the aseismatic capability. In addition, the following themes are being planned as future standardization: (1) electrically driven control rod driving system, (2) improved design of reactor core, and (3) internal pump system as compared with external re-circulation.

  6. Development and recent trend of disign of BWR nuclear power plants

    International Nuclear Information System (INIS)

    Kani, Jiro

    1977-01-01

    Many improvements have been carried out in BWR nuclear power plants from BWR-1, represented by Dresden No. 1 plant, to the present BWR-6 as the capacity has increased. In Japan, the plants up to BWR-5 have been constructed. In addition, further fine design improvements are being performed in the complete domestic manufacturing of BRWs based on the operational experiences to date. A variety of investigations on the standardization of nuclear power facilities have been progressing under the leadership of Japanese Ministry of International Trade and Industry since 1975. In this standardization, it is intended to forward the plant design taking eight concrete items into consideration, mainly aiming at carrying cut unerringly the maintenance and inspection, reduction of exposure of employees to radiation, and improvements of the rate of operation of plants and equipment reliability. The containment vessel has been developed in three forms, from Mark 1 through 3, adopting the pressure control system consistently since BWR-2. Mark 1 and 2 were constructed in Japan. However, these designs sacrificed the workability and increased radiation exposure during maintenance as a result of placing emphasis on the safety facilities, therefore Toshiba Electric has investigated the advanced Mark 1 type. Its features are the design for improving the work efficiency in a containment vessel, reducing the radiation exposure of workers, shortening plant construction period, and considering the aseismatic capability. In addition, the following themes are being planned as future standardization: (1) electrically driven control rod driving system, (2) improved design of reactor core, and (3) internal pump system as compared with external re-circulation. (Wakatsuki, Y.)

  7. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Yang Heui; Shin, Hyun Mok [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2001-12-15

    The most part of the nuclear power plants operating currently in Korea are more than 20 years old and obviously we cannot pretend that their original performance is actually maintained. In addition, earthquake occurrences show an increasing trend all over the world, and Korea can no more be considered as a zone safe from earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  8. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Ho Hyun; Cho, Yang Hui [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2000-12-15

    Some of nuclear power plants operating currently in Korea have been passed about 20 years after construction. Moreover, in the case of KORI I the service year is over 20 years, so their abilities are different from initial abilities. Also, earthquake outbreak increase, our country is not safe area for earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  9. Development of integrated D/B system for the safety-related structures in nuclear power plant

    International Nuclear Information System (INIS)

    Cho, M. S.; Song, Y. C.; Lee, J. S.; Choi, W. S.

    2002-01-01

    The integrated D/B system is developed for digitalizing the history of the safety-related structures of nuclear power plant. It have 5 database which are consist of Generals, Structural and Design, Materials, Construction, Aging and repair information D/B. For efficient operation of the system, we are to set up the outline of the system, find out data field for target structures, and develop utilities. Utilities will be the aging and repair data management program, the close examination management program, the data search engine with various options which help users to find the information quickly, and the data management program restoring, updating and exchanging input data. Development of the integrated D/B system of the safety-related structures will contribute to management of the structures of nuclear power plant with advanced technology

  10. Safety and effective developing nuclear power to realize green and low-carbon development

    Directory of Open Access Journals (Sweden)

    Qi-Zhen Ye

    2016-03-01

    Full Text Available This paper analyzes the role of nuclear power of China's energy structure and industry system. Comparing with other renewable energy the nuclear power chain has very low greenhouse gas emission, so it will play more important role in China's low-carbon economy. The paper also discussed the necessity of nuclear power development to achieve emission reduction, energy structure adjustment, nuclear power safety, environmental protection, enhancement of nuclear power technology, nuclear waste treatment, and disposal, as well as nuclear power plant decommissioning. Based on the safety record and situation of the existing power plants in China, the current status of the development of world nuclear power technology, and the features of the independently designed advanced power plants in China, this paper aims to demonstrate the safety of nuclear power. A nuclear power plant will not cause harm either to the environment and nor to the public according to the real data of radioactivity release, which are obtained from an operational nuclear plant. The development of nuclear power technology can enhance the safety of nuclear power. Further, this paper discusses issues related to the nuclear fuel cycle, the treatment, and disposal strategies of nuclear waste, and the decommissioning of a nuclear power plant, all of which are issues of public concern.

  11. 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.)

  12. Development and characteristics of halogen-free flame-retardant cables for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kanemitsuya, K.; Furukawa, K.; Tachibana, T.; Ohara, H.; Ebiike, Y.; Hamachi, K.; Makino, M. (Mitsubishi Cable Industries Ltd., Tokyo (Japan))

    1992-10-01

    Halogen-free flame-retardant (HF-FR) cables for use in nuclear power plants, especially in pressurized water type (PWR) plants, have been developed to advancing the safety and reliability of nuclear power plants. HF-FR cables generate no corrosive gases and minimal amount of toxic gases and smoke during fires, and are accordingly quite safe in comparison with the conventional cables which can cause the secondary calamity by eliminating a large amount of hydrogen halide gas and smoke. HF-FR ethylene-propylene rubber (EPR) and crosslinked polyolefin (XLPO) are used as insulating materials, and HF-FR ethylene-vinyl acetate (EVA) elastomer and polyolefin (PO) are used as jacketing materials. The results of a series of experiments on several types of HF-FR cables have revealed that these cables fully satisfy every requirement, including reliability under LOCA (Loss of Coolant Accidents) simulated conditions, long-term (40y) reliability under thermal and [gamma]-ray exposure, and flame resistivity under vertical tray test (IEEE Std. 383). (author).

  13. Nuclear power plant control and instrumentation 1982. Proceedings of an international symposium on nuclear power plant control and instrumentation

    International Nuclear Information System (INIS)

    1983-01-01

    Ever increasing demands for nuclear power plant safety and availability imply a need for the introduction of modern measurement and control methods, together with data processing techniques based on the latest advances in electronic components, transducers and computers. Nuclear power plant control and instrumentation is therefore an extremely rapidly developing field. The present symposium, held in Munich, FR Germany, was prepared with the help of the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation and organized in close co-operation with the Gesellschaft fur Reaktorsicherheit, Federal Republic of Germany. A number of developments were highlighted at the Munich symposium: - The increased use of computers can bring clear advantages and this technique is now proven as a tool for supervising and controlling plant operation. Advanced computerized systems for operator support are being developed on a large scale in many countries. The progress in this field is quite obvious, especially in disturbance analysis, safety parameter display, plant operator guidance and plant diagnostics. The new trend of introducing computers and microprocessors in protection systems makes it easy to implement 'defence-in-depth' strategies which give better assurance of correct system responses and also prevent unnecessary reactor trips, thus improving plant availability. The introduction of computerized systems for control of reactor power, reactor water level and reactor pressure as well as for reactor start-up and shut-down could improve the reliability and availability of nuclear power plants. The rapid technical development in the area of control and instrumentation makes it necessary to plan for at least one replacement of obsolete equipment in the course of the 30 years lifetime of a nuclear power plant and retrofitting of currently operating reactors with new control systems. Major design improvements and regulatory requirements also require

  14. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  15. Financial analysis of large versus small nuclear power plants

    International Nuclear Information System (INIS)

    Louh, R.F.; Becker, M.; Wicks, F.

    1986-01-01

    There have been no new orders for nuclear plants and many nuclear plants under construction have been cancelled in recent years in the United States. Financing problems have been a major factor in this slow down of new nuclear plant activity. Meanwhile, the nuclear plants that have been completed have been operating cost effectively and yielding fossil fuel conservation and air quality benefits. Smaller plants have been designed in the past for the purpose of penetrating markets in developing countries and countries with relatively small utility systems. This paper examines the question of whether these smaller plants would be a viable option to large nuclear plants in the United States. Although the smaller plants are estimated to have a somewhat higher capital cost on a $/k W basis, they have the potential advantage of a lower total financial committment. The computational tools required for this evaluation are optimal generation planning and financial simulation programs and the corresponding generation and financial data bases for a variety of systems

  16. Discussion on anti-flood renovation of operational nuclear power plants

    International Nuclear Information System (INIS)

    Chen Jiangang; Chen Haiqiao; Zhang Lihan; Wang Sen; Liu Shifeng

    2014-01-01

    The design of nuclear power plants on anti-flood performance was only based on design basis condition in China. The Fukushima nuclear accident revealed the possibility of suffering flood under beyond design basis condition, which caused the continuously deterioration of Fukushima nuclear accident. After the accident, China national nuclear safety regulators proposed new requirements on performance of anti-flood of nuclear power plants. Then, Qinshan Phase II carried out research of anti-flood technology. This paper introduced the background, research and development of anti-flood renovation technology for important safety buildings of Qinshan Phase II, and discussed the necessary for improvement of anti-flood capacity of nuclear power plants and relative measures in China, which is helpful to improve anti-flood performance of operational nuclear power plants and nuclear power plants under construction. (authors)

  17. From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World's First nuclear power plant

    Science.gov (United States)

    Rachkov, V. I.; Kalyakin, S. G.; Kukharchuk, O. F.; Orlov, Yu. I.; Sorokin, A. P.

    2014-05-01

    Successful commissioning in the 1954 of the World's First nuclear power plant constructed at the Institute for Physics and Power Engineering (IPPE) in Obninsk signaled a turn from military programs to peaceful utilization of atomic energy. Up to the decommissioning of this plant, the AM reactor served as one of the main reactor bases on which neutron-physical investigations and investigations in solid state physics were carried out, fuel rods and electricity generating channels were tested, and isotope products were bred. The plant served as a center for training Soviet and foreign specialists on nuclear power plants, the personnel of the Lenin nuclear-powered icebreaker, and others. The IPPE development history is linked with the names of I.V. Kurchatov, A.I. Leipunskii, D.I. Blokhintsev, A.P. Aleksandrov, and E.P. Slavskii. More than 120 projects of various nuclear power installations were developed under the scientific leadership of the IPPE for submarine, terrestrial, and space applications, including two water-cooled power units at the Beloyarsk NPP in Ural, the Bilibino nuclear cogeneration station in Chukotka, crawler-mounted transportable TES-3 power station, the BN-350 reactor in Kazakhstan, and the BN-600 power unit at the Beloyarsk NPP. Owing to efforts taken on implementing the program for developing fast-neutron reactors, Russia occupied leading positions around the world in this field. All this time, IPPE specialists worked on elaborating the principles of energy supertechnologies of the 21st century. New large experimental installations have been put in operation, including the nuclear-laser setup B, the EGP-15 accelerator, the large physical setup BFS, the high-pressure setup SVD-2; scientific, engineering, and technological schools have been established in the field of high- and intermediate-energy nuclear physics, electrostatic accelerators of multicharge ions, plasma processes in thermionic converters and nuclear-pumped lasers, physics of compact

  18. 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

  19. How safe are nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1976-09-01

    After naming the countries in which power plants are operated today, the author discusses the attitudes of their governments towards the problem of nuclear safety as well as the question if today's measures are sufficient in developing countries considering the increasing utilization of nuclear energy.

  20. Occupational dose reduction developments and data collected at nuclear power plants

    International Nuclear Information System (INIS)

    Dionne, B.J.; Baum, J.W.

    1984-01-01

    Occupational dose reduction developments and data collected at nuclear power plants have been described. Written descriptions of repetitive high dose jobs, their collective dose equivalent ranges and list of dose reduction techniques will aid in reducing collective dose equivalents from these dose-reduction targets. Knowing which components contribute to high maintenance or repair dose will aid in reducing routine maintenance collective dose equivalents. The radwaste dose reduction improvements will aid in reducing radwaste operations collective dose equivalent and reduce the number of radwaste workers who exceed their administrative dose limits. The identification and rating of managers' and workers' ALARA incentives will provide the basis for recommendations to improve dose reduction incentives. Lastly, the identification and rating of the key components of an ALARA program will aid in the development and coordination of the nuclear station ALARA programs

  1. Nuclear electric power plants. [Journal, in Russian]. Atomnye elektricheskie stantsii

    Energy Technology Data Exchange (ETDEWEB)

    Voronin, L M [ed.

    1980-01-01

    Separate articles are concerned with experience gained in the planning, exploitation, and adjustment of nuclear power plants with channel reactors. An examination is made of measures to be taken for assuring equipment reliability for nuclear power plants during the planning stage. Also examined is the experience gained in the operation of the pilot plants of the Kursk and Chernobyl' nuclear power plants, and the Bilibin nuclear thermal electric power plant. Considerable attention is given to the reprocessing and disposal of radioactive waste, the quality control of metal ducts in nuclear power plants, and the development of methods and means of controlling technological processes and equipment. The journal is intended for engineering-technical personnel of power plants, power supply administrations, adjustment, repair, and planning organizations.

  2. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An Kang Il; Hong, Suk Young; Lee, Jeong Soo; Lee, Kwang Yeol; Shin, Sun Hee; Lee, Chun Wha; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2003-03-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following: development of H/W that is necessary to acquire operating real time data of heating and hydraulic power, selection of a safety variable about major system by each type (the fourth unit), communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server, development of connecting database for controlling and storing of heating and hydraulic power operating data, real time monitoring system development based on web using JAVA.

  3. Nuclear power development

    International Nuclear Information System (INIS)

    Nealey, S.

    1990-01-01

    The objective of this study is to examine factors and prospects for a resumption in growth of nuclear power in the United States over the next decade. The focus of analysis on the likelihood that current efforts in the United States to develop improved and safer nuclear power reactors will provide a sound technical basis for improved acceptance of nuclear power, and contribute to a social/political climate more conducive to a resumption of nuclear power growth. The acceptability of nuclear power and advanced reactors to five social/political sectors in the U.S. is examined. Three sectors highly relevant to the prospects for a restart of nuclear power plant construction are the financial sector involved in financing nuclear power plant construction, the federal nuclear regulatory sector, and the national political sector. For this analysis, the general public are divided into two groups: those who are knowledgeable about and involved in nuclear power issues, the involved public, and the much larger body of the general public that is relatively uninvolved in the controversy over nuclear power

  4. 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.)

  5. 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)

  6. Materials for Nuclear Plants From Safe Design to Residual Life Assessments

    CERN Document Server

    Hoffelner, Wolfgang

    2013-01-01

    The clamor for non-carbon dioxide emitting energy production has directly  impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments  provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts.   Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, material...

  7. Development of Real Time Operating System for Safety Grade PLC (POSAFE-Q) for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Son, Han Seong; Hwang, Sung Jae; Lee, Young Joon; Kim, Chang Hwoi; Lee, Dong Young

    2006-01-01

    POSAFE-Q is a newly developed programmable logic controller (PLC) in order to apply to digital safety system of nuclear power plants (NPP) according to Nuclear Power Plant safety requirements. POSAFE-Q hardware and software development process, including design, review, verification and validation, and configuration control and quality assurance, satisfies the requirements imposed by 10CFR50, Appendix B. This article introduces a real time operating system pCOS, which is the core of POSAFE-Q. Section 2 describes the structure of pCOS. Section 3 describes a few important features of pCOS, which are necessary to the application for the digital safety system of NPP

  8. Development of Real Time Operating System for Safety Grade PLC (POSAFE-Q) for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Han Seong [ENESYS, Taejon (Korea, Republic of); Hwang, Sung Jae [POSCON, Seoul (Korea, Republic of); Lee, Young Joon; Kim, Chang Hwoi; Lee, Dong Young [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    POSAFE-Q is a newly developed programmable logic controller (PLC) in order to apply to digital safety system of nuclear power plants (NPP) according to Nuclear Power Plant safety requirements. POSAFE-Q hardware and software development process, including design, review, verification and validation, and configuration control and quality assurance, satisfies the requirements imposed by 10CFR50, Appendix B. This article introduces a real time operating system pCOS, which is the core of POSAFE-Q. Section 2 describes the structure of pCOS. Section 3 describes a few important features of pCOS, which are necessary to the application for the digital safety system of NPP.0.

  9. An environmental report for the first Israeli nuclear power plant

    International Nuclear Information System (INIS)

    Velner, S.

    1977-01-01

    At the end of 1974, following general activity in planning the nuclear power plant, the need for an Environment Report (ER) for that plant came up. The ER should concentrate mainly on the quality of life, while the Licensing Division of the IAEC is the body that supervises all the aspects of the ''safety of life''. The conclusions about the ER role can be summarized thus: it should be based on the American format adjusted to Israeli conditions, a separation between Safety of life and Quality of life factors will be utilized. The ER should deal with safety subjects only at a minimal level, the ER will deal with several alternate sites, most of information would be based on existing knowledge. These four principles are further developed in the content of the ER. Chapters of the ER: need of power, need of nuclear energy, siting of the nuclear plant, site comparison - demography and land and water use, site comparison - physical and ecological conditions, selection of site to be recommended, the nuclear plant, environmental impacts of the nuclear plant, the nuclear plant in the framework of overall Master plant for development of Electrical power. (B.G.)

  10. Fighting and preventing post-earthquake fires in nuclear power plant

    International Nuclear Information System (INIS)

    Lu Xuefeng; Zhang Xin

    2011-01-01

    Nuclear power plant post-earthquake fires will cause not only personnel injury, severe economic loss, but also serious environmental pollution. For the moment, nuclear power is in a position of rapid development in China. Considering the earthquake-prone characteristics of our country, it is of great engineering importance to investigate the nuclear power plant post-earthquake fires. This article analyzes the cause, influential factors and development characteristics of nuclear power plant post-earthquake fires in details, and summarizes the three principles should be followed in fighting and preventing nuclear power plant post-earthquake fires, such as solving problems in order of importance and urgency, isolation prior to prevention, immediate repair and regular patrol. Three aspects were pointed out that should be paid attention in fighting and preventing post-earthquake fires. (authors)

  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. Reliability methods in nuclear power plant ageing management

    International Nuclear Information System (INIS)

    Simola, K.

    1999-01-01

    The aim of nuclear power plant ageing management is to maintain an adequate safety level throughout the lifetime of the plant. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time-dependent degradation. The phases of ageing analyses are generally the identification of critical components, identification and evaluation of ageing effects, and development of mitigation methods. This thesis focuses on the use of reliability methods and analyses of plant- specific operating experience in nuclear power plant ageing studies. The presented applications and method development have been related to nuclear power plants, but many of the approaches can also be applied outside the nuclear industry. The thesis consists of a summary and seven publications. The summary provides an overview of ageing management and discusses the role of reliability methods in ageing analyses. In the publications, practical applications and method development are described in more detail. The application areas at component and system level are motor-operated valves and protection automation systems, for which experience-based ageing analyses have been demonstrated. Furthermore, Bayesian ageing models for repairable components have been developed, and the management of ageing by improving maintenance practices is discussed. Recommendations for improvement of plant information management in order to facilitate ageing analyses are also given. The evaluation and mitigation of ageing effects on structural components is addressed by promoting the use of probabilistic modelling of crack growth, and developing models for evaluation of the reliability of inspection results. (orig.)

  13. Reliability methods in nuclear power plant ageing management

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. [VTT Automation, Espoo (Finland). Industrial Automation

    1999-07-01

    The aim of nuclear power plant ageing management is to maintain an adequate safety level throughout the lifetime of the plant. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time-dependent degradation. The phases of ageing analyses are generally the identification of critical components, identification and evaluation of ageing effects, and development of mitigation methods. This thesis focuses on the use of reliability methods and analyses of plant- specific operating experience in nuclear power plant ageing studies. The presented applications and method development have been related to nuclear power plants, but many of the approaches can also be applied outside the nuclear industry. The thesis consists of a summary and seven publications. The summary provides an overview of ageing management and discusses the role of reliability methods in ageing analyses. In the publications, practical applications and method development are described in more detail. The application areas at component and system level are motor-operated valves and protection automation systems, for which experience-based ageing analyses have been demonstrated. Furthermore, Bayesian ageing models for repairable components have been developed, and the management of ageing by improving maintenance practices is discussed. Recommendations for improvement of plant information management in order to facilitate ageing analyses are also given. The evaluation and mitigation of ageing effects on structural components is addressed by promoting the use of probabilistic modelling of crack growth, and developing models for evaluation of the reliability of inspection results. (orig.)

  14. 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

  15. Cost benefit justification of nuclear plant reliability improvement

    International Nuclear Information System (INIS)

    El-Sayed, M.A.H.; Abdelmonem, N.M.

    1985-01-01

    The design of the secondary steam loop of the nuclear power plant has a significant effect on the reliability of the plant. Moreover, the necessity to cool a reactor safely has increased the reliability demanded from the system. The rapidly rising construction costs and fuel prices in recent years have stimulated a great deal in optimizing the productivity of a nuclear power plant through reliability improvement of the secondary steamloop and the reactor cooling system. A method for evaluating the reliability of steam loop and cooling system of a nuclear power plant is presented. The method utilizes the cut-set technique. The developed method can be easily used to show to what extent the overall reliability of the nuclear plant is affected by the possible failures in the steam and cooling subsystem. A model for calculating the increase in the nuclear plant productivity resulting from a proposed improvement in the two subsystems reliability is discussed. The model takes into account the capital cost of spare parts for several components, replacement energy, operating and maintenance costs

  16. Generic nuclear power plant component failure data bank

    International Nuclear Information System (INIS)

    Araujo Goes, A.G. de; Gibelli, S.M.O.

    1988-11-01

    This report consist in the development of a generic nuclear power plant component failure data bank. This data bank was implemented in a PC-XT microcomputer, IBM compatible, using the Open Access II program. Generic failure data tables for Westinghouse nuclear power plants and for general PWR power plants are presented. They are the final product of a research which included a preselection and a selection of data collected from the available sources in the library of CNEN (National Nuclear Energy Commission) and from the CIN/CNEN (Neclear Information Center). Futhermore, a proposal of evaluating models of average failure rates of pumps and valves are also presented. Through the electronic data bank one can easily have a generic view of failure rate ranges as well as failure models foe a certain component. It is very importante to develop procedures to collect and store generic failure data that can be quickly accessed, in order to update the Probabilistic Safety Study of Angra-1 and to used in studies which may have component failures of nuclear power plant safety systems. In the future, data specialization can be achieved by means of statistical calculations involving specific data collected from the operational experience of Angra-1 nuclear power plant and the generic data bank. (author) [pt

  17. Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

    International Nuclear Information System (INIS)

    Okuda, Yasunori; Yoshida, Yoshitaka; Gotou, Kazuko

    2001-01-01

    A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

  18. Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Okuda, Yasunori; Yoshida, Yoshitaka [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Gotou, Kazuko [Kansai Electric Power Co., Inc., Osaka (Japan)

    2001-09-01

    A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

  19. Development of a nuclear power plant system analysis code

    International Nuclear Information System (INIS)

    Sim, Suk K.; Jeong, J. J.; Ha, K. S.; Moon, S. K.; Park, J. W.; Yang, S. K.; Song, C. H.; Chun, S. Y.; Kim, H. C.; Chung, B. D.; Lee, W. J.; Kwon, T. S.

    1997-07-01

    During the period of this study, TASS 1.0 code has been prepared for the non-LOCA licensing and reload safety analyses of the Westinghouse and the Korean Standard Nuclear Power Plants (KSNPP) type reactors operating in Korea. TASS-NPA also has been developed for a real time simulation of the Kori-3/4 transients using on-line graphical interactions. TASS 2.0 code has been further developed to timely apply the TASS 2.0 code for the design certification of the KNGR. The COBRA/RELAP5 code, a multi-dimensional best estimate system code, has been developed by integrating the realistic three-dimensional reactor vessel model with the RELAP5 /MOD3.2 code, a one-dimensional system code. Also, a 3D turbulent two-phase flow analysis code, FEMOTH-TF, has been developed using finite element technique to analyze local thermal hydraulic phenomena in support of the detailed design analysis for the development of the advanced reactors. (author). 84 refs., 27 tabs., 83 figs

  20. Fatigue assessments in operating nuclear power plants

    International Nuclear Information System (INIS)

    Gosselin, S.R.; Deardorff, A.F.; Peltola, D.W.

    1994-01-01

    In November 1991, the ASME Section XI Task Group on Operating Plant Fatigue Assessment was formed to develop criteria and evaluation methodology for evaluating the effects of cyclic operation in operating nuclear power plants. The objective was to develop guidelines for inclusion in Section XI that could be used by plant operators in evaluating fatigue concerns and their impact on serviceability. This paper discusses the work performed by the Task Group. It explores the concept of ''Fatigue Design Basis'' versus ''Fatigue Operating Basis'' by examining the roles of ASME Section III and ASME Section XI in the design and operation of the nuclear power plants. Guidelines are summarized that may help plant operators perform effective design transient cycle evaluations and optimize cycle counting and fatigue usage tracking. The alternative fatigue evaluation approach using flaw tolerance is also introduced

  1. Intelligent operation system for nuclear power plants

    International Nuclear Information System (INIS)

    Morioka, Toshihiko; Fukumoto, Akira; Suto, Osamu; Naito, Norio.

    1987-01-01

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

  2. The development of robotic system for the nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Lee, Jae Kyung; Kim, Ki Ho; Jung, Seung Ho; Kim, Chang Hoi; Kim, Byung Soo; Hwang, Suk Yeoung; Seo, Yong Chil; Lee, Young Kwang; Lee, Yong Bum; Kim, Woong Ki; Park, Soon Yong

    1996-07-01

    This project focuses on the development of a heavy-duty telerobotic system (HDTS) and a light-duty mobile robotic system (LDMRS) for use in nuclear power plants. HDTS has been developed for performing tasks such as the installation and removal of nozzle dam inside of water chamber of steam generator. HDTS that is remotely controlled could eliminate or significantly reduce human exposure to hazardous nuclear environment. HDTS has four major subsystems : a 6 degree of freedom master-slave manipulator, a guiding device, a monitoring device and a remote control center. Functional connections of each subsystems has resulted in HDTS that exhibits a high level of dexterity and a broad range of capabilities. LDMRS has been developed to be used in emergency response applications such as monitoring and mapping radiation areas, handling radioactive materials and performing decontamination tasks. LDMRS equipped with four-omnidirectional planetary wheels is capable of ascending and descending stairs by employing a automatic stair climbing algorithm. A force-reflective algorithm developed enables LDMRS to be navigated flat surface with zero turning radius without collision by giving an operator a sense of force. The significance of developments is in providing both HDTS and LDMRS that can be operated from remote locations to perform tasks such as the maintenance of nozzle dam and the video surveillance of the nuclear facilities efficiently and without endangering human workers. This report describes the mechanical design, features, control system, and capabilities of both HDTS and LDMRS. (author). 59 refs., 38 tabs., 132 figs.

  3. The development of robotic system for the nuclear power plant

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Lee, Jae Kyung; Kim, Ki Ho; Jung, Seung Ho; Kim, Chang Hoi; Kim, Byung Soo; Hwang, Suk Yeoung; Seo, Yong Chil; Lee, Young Kwang; Lee, Yong Bum; Kim, Woong Ki; Park, Soon Yong.

    1996-07-01

    This project focuses on the development of a heavy-duty telerobotic system (HDTS) and a light-duty mobile robotic system (LDMRS) for use in nuclear power plants. HDTS has been developed for performing tasks such as the installation and removal of nozzle dam inside of water chamber of steam generator. HDTS that is remotely controlled could eliminate or significantly reduce human exposure to hazardous nuclear environment. HDTS has four major subsystems : a 6 degree of freedom master-slave manipulator, a guiding device, a monitoring device and a remote control center. Functional connections of each subsystems has resulted in HDTS that exhibits a high level of dexterity and a broad range of capabilities. LDMRS has been developed to be used in emergency response applications such as monitoring and mapping radiation areas, handling radioactive materials and performing decontamination tasks. LDMRS equipped with four-omnidirectional planetary wheels is capable of ascending and descending stairs by employing a automatic stair climbing algorithm. A force-reflective algorithm developed enables LDMRS to be navigated flat surface with zero turning radius without collision by giving an operator a sense of force. The significance of developments is in providing both HDTS and LDMRS that can be operated from remote locations to perform tasks such as the maintenance of nozzle dam and the video surveillance of the nuclear facilities efficiently and without endangering human workers. This report describes the mechanical design, features, control system, and capabilities of both HDTS and LDMRS. (author). 59 refs., 38 tabs., 132 figs

  4. Developing a taxonomy of coordination behaviours in nuclear power plant control rooms during emergencies.

    Science.gov (United States)

    Wang, Dunxing; Gao, Qin; Li, Zhizhong; Song, Fei; Ma, Liang

    2017-12-01

    This study aims to develop a taxonomy of coordination behaviours during emergencies in nuclear power plants (NPPs). We summarised basic coordination behaviours from literature in aviation, health care and nuclear field and identified coordination behaviours specific to the nuclear domain by interviewing and surveying control crew operators. The established taxonomy includes 7 workflow stages and 24 basic coordination behaviours. To evaluate the reliability and feasibility of the taxonomy, we analysed 12 videos of operators' training sessions by coding coordination behaviours with the taxonomy and the inter-rater reliability was acceptable. Further analysis of the frequency, the duration and the direction of the coordination behaviours revealed four coordination problems. This taxonomy provides a foundation of systematic observation of coordination behaviours among NPP crews, advances researchers' understanding of the coordination mechanism during emergencies in NPPs and facilitate the possibility to deepen the understanding of the relationships between coordination behaviours and team performance. Practitioner Summary: A taxonomy of coordination behaviours during emergencies in nuclear power plants was developed. Reliability and feasibility of the taxonomy was verified through the analysis of 12 training sessions. The taxonomy can serve as an observation system for analysis of coordination behaviours and help to identify coordination problems of control crews.

  5. History of nuclear technology development in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Kiyonobu, E-mail: yamashita.kiyonobu@jaea.go.jp [Visiting Professor, at the Faculty of Petroleum and Renewable Energy Engineering, University Teknologi Malaysia Johor Bahru 81310 (Malaysia); General Advisor Nuclear HRD Centre, Japan Atomic Energy Agency, TOKAI-mura, NAKA-gun, IBARAKI-ken, 319-1195 (Japan)

    2015-04-29

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  6. History of nuclear technology development in Japan

    Science.gov (United States)

    Yamashita, Kiyonobu

    2015-04-01

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  7. History of nuclear technology development in Japan

    International Nuclear Information System (INIS)

    Yamashita, Kiyonobu

    2015-01-01

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident

  8. Development of a coordinated control system for BWR nuclear power plant and HVDC transmission system

    International Nuclear Information System (INIS)

    Ishikawa, M.; Hara, T.; Hirayama, K.; Sekiya, K.

    1986-01-01

    The combined use of dc and ac transmissions or so-called hybrid transmission was under study, employing both dc and ac systems to enable stable transmission of 10,000 MW of electric power generated by the BWR nuclear plant, scheduled to be built about 800 km away from the center of the load. It was thus necessary to develop a hybrid power transmission control system, the hybrid power transmission system consisting of a high voltage dc transmission system (HVDC) and an ultrahigh ac transmission system (UHVAC). It was also necessary to develop a control system for HVDC transmission which protects the BWR nuclear power plant from being influenced by any change in transmission mode that occurs as a result of faults on the UHVAC side when the entire power of the BWR plant is being sent by the HVDC transmission. This paper clarifies the requirements for the HVDC system control during hybrid transmission and also during dc transmission. The control method that satisfies these requirements was studied to develop a control algorithm

  9. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 3

    International Nuclear Information System (INIS)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2006-01-01

    This is the 2006 update (Revision 3) of the NGNP Materials Research and Development Program Plan. This law established that the U.S Department of Energy (DOE) Secretary of Energy shall establish a ''Next Generation Nuclear Plant'' (NGNP) project. The NGNP project named in the Act was given the following attributes and guiding principles to manage its development: (1) The NGNP consists of research, development, design (R and DD), construction, and operation of a prototype reactor to generate electricity and hydrogen; (2) The project shall be managed by the DOE Office of Nuclear Energy; (3) The Idaho National Laboratory (INL) shall be the lead DOE laboratory for the NGNP; (4) The INL shall establish collaborations with selected institutions of higher education, other research institutes and international researchers; (5) The INL shall organize an industrial consortium of partners for cost-shared R and DD, construction; (6) The project shall be sited at the INL; (7) The project shall be licensed by the Nuclear Regulatory Commission (NRC) and by July, 2008 the NRC and DOE shall jointly submit a licensing strategy to Congress; (8) The project shall be organized to maximize technical interchange with the nuclear power industry, nuclear power plant construction firms, the chemical process industry and to seek international cooperation, participation and contributions; (9) The Nuclear Energy Research Advisory Committee (NERAC) shall review all program plans for the NGNP; (10) Phase 1 of the project (selection of hydrogen production technology, conduct R and DD and initial design activities) shall be completed no later than September 30, 2011; (11) Phase 2 of the project (continue R and DD, develop final design, apply for a license, construct and start operations) shall be completed by September 30, 2021; and (12) Provision for authorization of appropriations was made. As a result of the direction provided, the INL and the DOE issued an NGNP Preliminary Project Management

  10. Development of probabilistic methods for safety assessment of nuclear power plants

    International Nuclear Information System (INIS)

    Schott, H.; Berg, H.P.

    1998-01-01

    Since its introduction by the German Risk Study, Probabilistic Safety Assessment (PSA) has developed in Germany to a valuable tool in regulatory decision-making. Plant specific PSAs of Level 1+ are now conducted for all nuclear power plants in the frame of Periodic Safety Reviews. This paper is devoted to the description or key elements set out in the regulatory guidelines for PSA-Level 1+ and the corresponding technical documents and the further development of PSA methodology in the Federal Republic of Germany. In the course of the next years it is intended to make progress in the modeling of common cause failures, human reliability evaluation, reduction of uncertainties in PSA modeling techniques and data estimation, analysis of low power and shut down states as well as in reaching a mature methodology for inclusion of external events into the analysis. (author)

  11. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    Klevans, E.H.

    1992-01-01

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

  12. 76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-01-10

    ... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Environmental Assessment... Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Impact Statement for License Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power Plant (NUREG-1437...

  13. Passive Nuclear Plants Program (UPDATE)

    International Nuclear Information System (INIS)

    Chimeno, M. A.

    1998-01-01

    The light water passive plants program (PCNP), today Advanced Nuclear Power Plants Program (PCNA), was constituted in order to reach the goals of the Spanish Electrical Sector in the field of advanced nuclear power plants, optimize the efforts of all Spanish initiatives, and increase joint presence in international projects. The last update of this program, featured in revision 5th of the Program Report, reflects the consolidation of the Spanish sector's presence in International programs of the advanced power plants on the basis of the practically concluded American ALWR program. Since the beginning of the program , the PCNP relies on financing from the Electrical sector, Ocide, SEPI-Endesa, Westinghouse, General Electric, as well as from the industrial cooperators, Initec, UTE (Initec- Empresarios Agrupados), Ciemat, Enusa, Ensa and Tecnatom. The program is made up of the following projects, already concluded: - EPRI's Advanced Light Water Plants Certification Project - Westinghouse's AP600 Project - General Electric's SBWR Project (presently paralyzed) and ABWR project Currently, the following project are under development, at different degrees of advance: - EPP project (European Passive Plant) - EBWR project (European Advanced Boiling Water Reactor)

  14. NPAR [Nuclear Plant Aging Research] approach to managing aging in nuclear power plants

    International Nuclear Information System (INIS)

    Christensen, J.A.

    1989-01-01

    Over the past 5 years, the Nuclear Plant Aging Research program (NPAR) has been devoted to developing technical understanding of the time dependent processes that, through deterioration of components, systems, or structures (C/S/S), can reduce safety margins in nuclear power plants. A major and necessary element of the program involves the application of this basic knowledge in defining functional approaches to managing aging by anticipating and mitigating important deterioration processes. Fundamental understanding and characterization of aging processes are being accomplished through NPAR-sponsored research projects, review and analysis of aging related information, integration of NPAR results with those from industry and other aging studies, and interfacing of all of these with the existing body of codes, standards and regulatory instruments that convey aging-related guidance to NPP licensees. Products of these efforts are applied to structuring and providing aging-related technical recommendations in forms that are useful in: (1) developing and implementing good aging management practices, (2) developing regulatory guidance and requirements for understanding and managing aging during normal plant operations and in support of license renewal, and (3) planning and implementing other regulatory actions and initiatives in which aging-related concerns have a bearing on scope or priority

  15. Development of computerized supporting system for emergency response in nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Jae Il

    1992-02-01

    In emergency situation of nuclear power plants, effective use of emergency operating procedures (EOPs) is a crucial part of the emergency response process. However, there are several problems in the emergency operating procedures because of the form of the written procedures. They are voluminous and complicate for effective references under high stress situation. Inevitably, it takes time that could be better spent employing measures to control and stabilize to select the correct procedures and apply the decision logic. In this study, a computerized supporting system has been developed to reduce the operator error possibility under emergency situations of nuclear power plant. Using on-line input parameters, the system can determine the status of the critical safety functions and can find appropriate procedures and necessary operator actions automatically. Moreover, the system can help the operator decision making in the core melt accident situation. By tracking the EOP in an on-line mode, most steps concerning checking or verifying plant state are processed automatically without operator participations. Therefore, the interactions between the system and the operator are simplified significantly and the possibility of human error is reduced

  16. Location and public acceptance of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Takahashi, Hiroshi

    1978-01-01

    Analysis of problems concerning the sites of nuclear power plants and policy of the government to develop nuclear power plants are presented. At present, national consensus about atomic energy is not yet sufficient in Japan. Accordingly, it is hard to get proper location for nuclear power plants, and more effort is required. Reasons of the hindrance of atomic energy development are not same, but they are based on lack of understanding, social and local situations, and interests accompanying atomic energy development. Also, there is effects from the activities of opposition groups. The most important factor is lack of communication between those concerned with the development and residents around prospective sites. The government has investigated how to promote the atomic energy development, taking into account the present status of public acceptance. The system to promote the development of sites for nuclear power plants has been established. Political efforts for improving the welfare of residents have been made, and three laws for the purpose were approved. According to these laws, subsidiary money is paid to cities, towns and villages where power plants are located. Speeding up and smoothing of legal procedures concerning the location for power plants are also studied. (Kato, T.)

  17. On-site tests on the nuclear power plants

    International Nuclear Information System (INIS)

    Morilhat, P.; Favennec, J.M.; Neau, P.; Preudhomme, E.

    1996-01-01

    On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

  18. The nuclear plants at Dodewaard and Borssele

    International Nuclear Information System (INIS)

    Wessels, M.

    In this writing, the main benefits and drawbacks of the functioning of the Dutch nuclear power plants at Dodewaard and Borssele are discussed. First, an introductory chapter is devoted to the nuclear developments in the Netherlands and Europe after World War II. Next, the economic aspects of the possible dismantlement of the Dodewaard and Borssele plants are considered. The last part deals with some other aspects like nuclear research and industrial activities in the Netherlands and their relation with Borssele and Dodewaard; safety aspects; the waste problem and non-proliferation problems. (G.J.P.)

  19. Life management plants at nuclear power plants PWR

    International Nuclear Information System (INIS)

    Esteban, G.

    2014-01-01

    Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

  20. Development of Open Test-bed for Autonomous Operation in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Seungmin; Heo, Gyunyoung

    2017-01-01

    Nuclear power plants also recognize the need for automation. However, it is dangerous technology to have a significant impact on human society. In addition, due to the uncertain legal responsibility for autonomous operation, the application and development speed of nuclear energy related automation technology will be significantly decrease compared to other industries. It is argued that the application of AI and automation technology to power plants should not be prematurely applied or not based on the principle of applying proven technology since nuclear power plants are the highest level security operated facilities. As described above, the overall algorithm of the Test Bed is an autonomous operation algorithm (rulebased algorithm, learning-based algorithm, semiautonomous operation algorithm) to judge the entry condition of the procedure through condition monitoring and to enter the appropriate operating procedure. In order to make a test bed, the investigation for the heuristic part of the existing procedures and the heuristic part from the circumstance which is not specified in the procedure is needed. In the learning based and semi-autonomous operation algorithms, using MARS to extract its operating data and operational logs and try out various diagnostic algorithms as described above. Through the completion of these future tasks, the test bed which can compared with actual operators will be constructed and that it will be able to check its effectiveness by improving competitively with other research teams through the characteristics of shared platform.

  1. 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).

  2. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1991-06-01

    A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

  3. 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)

  4. 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

  5. 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

  6. The design, development and operation of a compact nuclear power plant simulator

    International Nuclear Information System (INIS)

    Lynch, M.F.

    1987-01-01

    This paper discusses the philosophy and technological considerations necessary for constructing and utilizing a plant specific compact nuclear power plant simulator, how it compares to full scope replica simulators, engineering simulators, part task simulators and basic principles training simulators. Included in this discussion are the design process, scope of simulation, the manufacturing process, test programs and experiences with operator training. Items addressed include the applicability and use of a compact simulator, how well it reproduces the actual reference plant, how well the transferral of knowledge is accomplished and what financial considerations need to be evaluated. This paper tries to provide the details on just how this type of machine was designed and developed by Westinghouse for the Swiss Utility, Nordostschweizerische Kraftwerke (NOK) AG

  7. Licensing the First Nuclear Power Plant. INSAG-26. A report by the International Nuclear Safety Group

    International Nuclear Information System (INIS)

    2012-01-01

    This report is primarily addressed to policy makers and nuclear safety regulatory bodies in IAEA Member States planning to establish their first nuclear power plant. It outlines the key challenges with suggestions on how the regulator and policy makers might address them and also prepare for further development of nuclear power in the country. INSAG believes that development of technical competence of the national regulatory body is a necessary condition for the safe development of nuclear power. Therefore, regulatory infrastructure development should be a national policy requirement, as opposed to being a challenge only for the regulator. A major challenge in the deployment of the first nuclear power plant is the development of the underlying nuclear safety infrastructure and knowledge base. Since an independent regulatory body is an important part of such infrastructure, its establishment and development must be addressed at an early stage and adequate resources must be made available for this purpose. This is to ensure smooth and efficient conduct of the licensing process and regulatory oversight of the first nuclear power plant through an informed decision making process. It is essential that the legal framework starts to be implemented with a main component being the issuance of a nuclear law establishing fundamental principles and defining the responsibilities of the principal organizations, particularly the operating organization and the regulatory body. The regulatory body on its part should develop the regulatory framework that includes the establishment of regulations against which the nuclear power project will be assessed, definition of the licensing steps and corresponding documentation to be submitted by the applicant, and the implementation of a quality management system. It is expected that the 'reference plant' concept will be employed whereby the country's first nuclear power plant would have essentially the same design and safety features as a

  8. Engineering experiences through nuclear power development in Japan

    International Nuclear Information System (INIS)

    Uchida, Hideo

    2004-01-01

    This keynote paper deals with: energy issues and nuclear power development in Japan, problems of radiation protection, licensing and safety regulations, research on LOCA and ECCS, stress corrosion cracks related to pressure vessels, nuclear fuel failures, steam generators, incidents, waste management and fuel cycle facilities. In conclusion it is stated that: on order to cope with global matters vitally affecting the electricity generation, taking into consideration Japanese specific energy issues, the nuclear power development has been an indispensable policy of Japan. In order to proceed with further development of nuclear power plants, it is necessary to obtain proper understanding by the public, showing assurance of the safety and reliable operation of nuclear power plants through daily plant operation. The nuclear safety issues should be considered from a global point of view. It is necessary to establish common safety standards which could harmonize the safety level of nuclear power plants in the world. The safety goal concerning severe accidents should be established as an internationally agreeable one. Japan has accumulated highly technological experience in maintenance of nuclear power plants. It is believed that the cumulative experiences in Japan can contribute to the further improvement of safety of nuclear power plants throughout the world, and for this aim a mutual information exchange should be encouraged

  9. Development of the simulation system IMPACT for analysis of nuclear power plant severe accidents

    International Nuclear Information System (INIS)

    Naitoh, Masanori; Ujita, Hiroshi; Nagumo, Hiroichi

    1997-01-01

    The Nuclear Power Engineering Corporation (NUPEC) has initiated a long-term program to develop the simulation system IMPACT for analysis of hypothetical severe accidents in nuclear power plants. IMPACT employs advanced methods of physical modeling and numerical computation, and can simulate a wide spectrum of senarios ranging from normal operation to hypothetical, beyond-design-basis-accident events. Designed as a large-scale system of interconnected, hierarchical modules, IMPACT's distinguishing features include mechanistic models based on first principles and high speed simulation on parallel processing computers. The present plan is a ten-year program starting from 1993, consisting of the initial one-year of preparatory work followed by three technical phases: Phase-1 for development of a prototype system; Phase-2 for completion of the simulation system, incorporating new achievements from basic studies; and Phase-3 for refinement through extensive verification and validation against test results and available real plant data

  10. Nuclear power plant decommissioning: state-of-the-art review

    International Nuclear Information System (INIS)

    Williams, D.H.

    1984-01-01

    A brief orientation to the state-of-the-art of nuclear power plant decommissioning discusses the related areas of experience, tools and techniques, and planning. There have been 68 nuclear reactor decommissionings to date, including 9 power plants, some of which were mothballed. The picture suggests that the term art may be misapplied since decommissioning is now more of a mature commercial industrial than a research and development endeavor. It also suggests that the nuclear industry has shown foresight by preparing for it before a crisis situation developed. Some of this has already influenced operators of coal power plants, especially where hazardous materials may be involved. 33 references, 1 table

  11. Are atomic power plants saver than nuclear power plants

    International Nuclear Information System (INIS)

    Roeglin, H.C.

    1977-01-01

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

  12. Nuclear Power Plant Control and Instrumentation activities in Finland

    International Nuclear Information System (INIS)

    Haapanen, P.; Wahlstroem, B.

    1990-01-01

    Finland has achieved some remarkable achievements in nuclear power production. Existing four plants have some of the best operating records in the world - high capacity factors, low occupational doses and short refuelling outages. Although public opinion was strongly turned against nuclear power after Chernobyl accident, and no decisions for new nuclear plants can be made before next elections in 1991, the nuclear option is still open. Utility companies are maintaining readiness to start new construction immediately after a positive political decision is made. One important component of the good operation history of the Finnish nuclear power plants is connected to the continuous research, development, modification and upgrading work, which is proceeding in Finland. In the following a short description is given on recent activities related to the I and C-systems of the nuclear power plants. (author). 2 tabs

  13. Czechoslovakia's electrical energy industry with special regard on the development of nuclear power plants

    International Nuclear Information System (INIS)

    Paulina, A.

    1979-01-01

    In electric energy production and consumption, Czechoslovakia holds a remarkable place. Its development after the second world war can be divided into four characteristic periods. The author summarizes the features of the past development and points out the tasks of the future in which the extension of nuclear power plant building plays an important role. (author)

  14. Potential of light water reactors for future nuclear power plants

    International Nuclear Information System (INIS)

    Gueldner, R.

    2003-01-01

    Energy consumption worldwide is going to increase further in the next few decades. Reliable supplies of electricity can be achieved only by centralized power plant structures. In this scenario, nuclear power plants are going to play a leading role as reliable and competitive plants, also under deregulated market conditions. Today, light water reactors have achieved a leading position, both technically and economically, contributing 85% to worldwide electricity generation in nuclear plants. They will continue to be a proven technology in power generation. In many countries, activities therefore are concentrated on extending the service life of plants beyond a period of forty years. New nuclear generating capacities are expected to be created and added from the end of this decade onward. Most of this capacity will be in light water reactors. The concepts of third-generation reactors will meet all economic and technical safety requirements of the 21st century and will offer considerable potential for further development. Probably some thirty years from now, fourth-generation nuclear power plants will be ready for commercial application. These plants will penetrate especially new sectors of the energy markets. Public acceptance of new nuclear power plants is not a matter of reactor lines, provided that safety requirements are met. The important issue is the management of radioactive waste. The construction of new nuclear power plants in Western Europe and North America mainly hinges on the ability to explain to the public that there is a need for new plants and that nuclear power is fundamental to assuring sustainable development. (orig.)

  15. Striving for excellence in nuclear plant safety and reliability

    International Nuclear Information System (INIS)

    Beard, P.M.

    1985-01-01

    The Institute of Nuclear Power Operations, or INPO, promotes excellence in the construction and operation of nuclear power plants. All US nuclear utilities are INPO members. Additionally, INPO has an active international programme that includes utility participants from 13 countries and a supplier programme composed of 13 firms that provide construction, design or manufacturing services for nuclear utilities. INPO's activities revolve around four programme categories: (1) evaluating US nuclear plant construction projects and operating nuclear power plants; (2) assisting utilities in developing and maintaining performance-based training programmes and accrediting US nuclear plant training programmes; (3) analysing and sharing information on operating experience from plants around the world; (4) providing technical assistance to members and participants. INPO periodically evaluates all US operating nuclear power plants. Additionally, INPO uses the evaluations to observe good practices that can be shared with nuclear utilities world wide. The Significant Event Evaluation and Information Network (SEE-IN) programme provides a system for collecting, analysing and sharing information on plant operating experience throughout the world. SEE-IN provides the industry with information on events that could lead to serious consequences and provides recommendations on how these events can be prevented or their effects mitigated. INPO's international programme promotes information exchange among members and participants. The international programme centres on three activities: (1) collecting, analysing and sharing information on international nuclear plant operating experience; (2) establishing a forum for nuclear utilities world-wide to exchange technical data with each other; (3) providing technical assistance to participants on a variety of concerns

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

    International Nuclear Information System (INIS)

    Ikegami, Tsukasa; Aoki, Masataka; Shimura, Takao; Kaimori, Kimihiro; Koike, Masahiro

    2001-01-01

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

  17. An integrated reliability management system for nuclear power plants

    International Nuclear Information System (INIS)

    Kimura, T.; Shimokawa, H.; Matsushima, H.

    1998-01-01

    The responsibility in the nuclear field of the Government, utilities and manufactures has increased in the past years due to the need of stable operation and great reliability of nuclear power plants. The need to improve the reliability is not only for the new plants but also for those now running. So, several measures have been taken to improve reliability. In particular, the plant manufactures have developed a reliability management system for each phase (planning, construction, maintenance and operation) and these have been integrated as a unified system. This integrated reliability management system for nuclear power plants contains information about plant performance, failures and incidents which have occurred in the plants. (author)

  18. Development of Czechoslovak nuclear power engineering

    International Nuclear Information System (INIS)

    Keher, J.

    1985-01-01

    The output of Czechoslovak nuclear power plants is envisaged at 2200 MW by 1985, 4400 MW by 1990 and 10,280 MW by the year 2000. The operation so far is assessed of Bohunice V-1 and Bohunice V-2 power plants as is the construction of the Dukovany nuclear power plant. International cooperation in the fulfilment of the nuclear power programme is based on the General Agreement on Cooperation in the Prospective Development and Interlinkage of CMEA Power Systems to the year 1990, the Agreement on Multilateral International Specialization and Cooperation of Production and on Mutual Deliveries of Nuclear Power Plant Equipment. The most important factor in international cooperation is the Programme of Cooperation between the CSSR and the USSR. The primary target in the coming period is the Temelin nuclear power plant project and the establishment of unified control of the nuclear power complex. (M.D.)

  19. 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.)

  20. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    International Nuclear Information System (INIS)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee

    2004-02-01

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA

  1. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2004-02-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA.

  2. Standardization of nuclear power plants in the United States: recent regulatory developments

    International Nuclear Information System (INIS)

    Cowan, B.Z.; Tourtellotte, J.R.

    1992-01-01

    On April 18, 1989, the United States (U.S.) Nuclear Regulatory Commission (NRC) amended the regulations governing the process for licensing nuclear power plants in the United States to provide for issuance of early site permits, standard design certifications and combined construction permits and operating licenses for nuclear power reactors. The new regulations are designed to achieve early resolution of licensing issues and facilitate standardization of nuclear power plants in the United States. The program for design standardization is central to efforts mounted by the U.S. government and industry to ensure that there will be a next generation of nuclear power facilities in the U.S. The most significant changes are provisions for certification of standard designs and for issuance prior to start of construction of combined licenses which incorporate a construction permit and an operating license with conditions. Such certifications and combined licenses must contain tests, inspections and analyses, and acceptance criteria, which are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will operate in accordance with the combined license. A number of significant implementation issues have arisen. In addition a major court case brought by several anti-nuclear groups is pending, challenging NRC authority to issue combined licenses. It is the goal of the U.S. nuclear industry to have the first of the next generation of standardized nuclear power plants ordered, licensed, constructed and on-line by the year 2000. (author)

  3. Operator support system for nuclear power plants

    International Nuclear Information System (INIS)

    Mori, Nobuyuki; Tai, Ichiro; Sudo, Osamu; Naito, Norio.

    1987-01-01

    The nuclear power generation in Japan maintains the high capacity factor, and its proportion taken in the total generated electric power exceeded 1/4, thus it has become the indispensable energy source. Recently moreover, the nuclear power plants which are harmonious with operators and easy to operate are demanded. For realizing this, the technical development such as the heightening of operation watching performance, the adoption of automation, and the improvement of various man-machine systems for reducing the burden of operators has been advanced by utilizing electronic techniques. In this paper, the trend of the man-machine systems in nuclear power plants, the positioning of operation support system, the support in the aspects of information, action and knowledge, the example of a new central control board, the operation support system using a computer, an operation support expert system and the problems hereafter are described. As the development of the man-machine system in nuclear power plants, the upgrading from a present new central control board system PODIA through A-PODIA, in which the operational function to deal with various phenomena arising in plants and safety control function are added, to 1-PODIA, in which knowledge engineering technology is adopted, is expected. (Kako, I.)

  4. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    2003-01-01

    The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2002 was made up on bases of answers on questionnaires from 65 electric power companies and other nuclear organizations in 28 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

  5. Nuclear energy and its functions for development

    International Nuclear Information System (INIS)

    Nevskij, V.P.

    1980-01-01

    25 years have passed since the first nuclear power plant in the Soviet Union started operation and thus laid the foundations for the development of a fundamentally new branch of economy - nuclear industry. At present the following nuclear power plants are operated in the Soviet Union: Belojarsk, Kola, Bilibino, Armenia, Leningrad, Kursk, and Tschernobylj, the number of power plant units amounting to 19, the total electric power to 0.09 GW. In total the plants have generated 44.8 billion kWh in 1978; for 1979 a total generation of 54 billion kWh is expected. By the following five-year plans the construction of nuclear power plants is to be still essentially extended: about 20% of the total electric power is planned to be produced by nuclear power plants. In the course of this extension the new nuclear power plants are planned to achieve individual capacities between 4 and 6 GW, the nuclear heating power plants 2 GW. In addition there will be facilities for nuclear production of heat only with a thermal output of up to 1 GW. (orig./UA) [de

  6. Development of nuclear safety issues program

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K

    2006-12-15

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants.

  7. Development of nuclear safety issues program

    International Nuclear Information System (INIS)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K.

    2006-12-01

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants

  8. Development of CAP code for nuclear power plant containment: Lumped model

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Soon Joon, E-mail: sjhong90@fnctech.com [FNC Tech. Co. Ltd., Heungdeok 1 ro 13, Giheung-gu, Yongin-si, Gyeonggi-do 446-908 (Korea, Republic of); Choo, Yeon Joon; Hwang, Su Hyun; Lee, Byung Chul [FNC Tech. Co. Ltd., Heungdeok 1 ro 13, Giheung-gu, Yongin-si, Gyeonggi-do 446-908 (Korea, Republic of); Ha, Sang Jun [Central Research Institute, Korea Hydro & Nuclear Power Company, Ltd., 70, 1312-gil, Yuseong-daero, Yuseong-gu, Daejeon 305-343 (Korea, Republic of)

    2015-09-15

    Highlights: • State-of-art containment analysis code, CAP, has been developed. • CAP uses 3-field equations, water level oriented upwind scheme, local head model. • CAP has a function of linked calculation with reactor coolant system code. • CAP code assessments showed appropriate prediction capabilities. - Abstract: CAP (nuclear Containment Analysis Package) code has been developed in Korean nuclear society for the analysis of nuclear containment thermal hydraulic behaviors including pressure and temperature trends and hydrogen concentration. Lumped model of CAP code uses 2-phase, 3-field equations for fluid behaviors, and has appropriate constitutive equations, 1-dimensional heat conductor model, component models, trip and control models, and special process models. CAP can run in a standalone mode or a linked mode with a reactor coolant system analysis code. The linked mode enables the more realistic calculation of a containment response and is expected to be applicable to a more complicated advanced plant design calculation. CAP code assessments were carried out by gradual approaches: conceptual problems, fundamental phenomena, component and principal phenomena, experimental validation, and finally comparison with other code calculations on the base of important phenomena identifications. The assessments showed appropriate prediction capabilities of CAP.

  9. Development of CAP code for nuclear power plant containment: Lumped model

    International Nuclear Information System (INIS)

    Hong, Soon Joon; Choo, Yeon Joon; Hwang, Su Hyun; Lee, Byung Chul; Ha, Sang Jun

    2015-01-01

    Highlights: • State-of-art containment analysis code, CAP, has been developed. • CAP uses 3-field equations, water level oriented upwind scheme, local head model. • CAP has a function of linked calculation with reactor coolant system code. • CAP code assessments showed appropriate prediction capabilities. - Abstract: CAP (nuclear Containment Analysis Package) code has been developed in Korean nuclear society for the analysis of nuclear containment thermal hydraulic behaviors including pressure and temperature trends and hydrogen concentration. Lumped model of CAP code uses 2-phase, 3-field equations for fluid behaviors, and has appropriate constitutive equations, 1-dimensional heat conductor model, component models, trip and control models, and special process models. CAP can run in a standalone mode or a linked mode with a reactor coolant system analysis code. The linked mode enables the more realistic calculation of a containment response and is expected to be applicable to a more complicated advanced plant design calculation. CAP code assessments were carried out by gradual approaches: conceptual problems, fundamental phenomena, component and principal phenomena, experimental validation, and finally comparison with other code calculations on the base of important phenomena identifications. The assessments showed appropriate prediction capabilities of CAP

  10. Lifetime Management in Non-US-Technology Nuclear Power Plants using US Regulations

    International Nuclear Information System (INIS)

    Cornelius Steenkamp, J.; Encabo Espartero, J.; Garcia Iglesias, R.

    2013-01-01

    In July 2009 the Spanish Nuclear Regulator (CSN) issued a Safety Instruction (IS-22) for the development of Lifetime Management in the Nuclear Power Plants within Spain. The context of this Safety Instruction is based on the American Regulations 10CFR54, NUREG1800/1801 and the technical guide NEI95-10. All these regulations are aimed at US-Technology Nuclear Power Plants. Lifetime Management of Nuclear Power Plants with a plant design different from US technologies can most certainly be developed with the mentioned US regulations. The successful development of Lifetime Management in these cases depends on the adaptation of the different requirements of the regulations. Challenges resulting from the adaptation process can be resolved by taking into consideration the plant design of the plant in question.

  11. 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)

  12. Assessment of defence in depth for nuclear power plants

    International Nuclear Information System (INIS)

    2005-01-01

    Defence in depth is a comprehensive approach to safety that has been developed by nuclear power experts to ensure with high confidence that the public and the environment are protected from any hazards posed by the use of nuclear power for the generation of electricity. The concepts of defence in depth and safety culture have served the nuclear power industry well as a basic philosophy for the safe design and operation of nuclear power plants. Properly applied, defence in depth ensures that no single human error or equipment failure at one level of defence, nor even a combination of failures at more than one level of defence, propagates to jeopardize defence in depth at the subsequent level or leads to harm to the public or the environment. The importance of the concept of defence in depth is underlined in IAEA Safety Standards, in particular in the requirements set forth in the Safety Standards: Safety of Nuclear Power Plants: Design (NS-R-1) and Safety Assessment and Verification for Nuclear Power Plants (NS-G-1.2). A specific report, Defence in Depth in Nuclear Safety (INSAG-10), describes the objectives, strategy, implementation and future development in the area of defence in depth in nuclear and radiation safety. In the report Basic Safety Principles for Nuclear Power Plants (INSAG-12), defence in depth is recognized as one of the fundamental safety principles that underlie the safety of nuclear power plants. In consonance with those high level publications, this Safety Report provides more specific technical information on the implementation of this concept in the siting, design, construction and operation of nuclear power plants. It describes a method for comprehensive and balanced review of the provisions required for implementing defence in depth in existing plants. This publication is intended to provide guidance primarily for the self-assessment by plant operators of the comprehensiveness and quality of defence in depth provisions. It can be used

  13. 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

  14. Experiment research on cognition reliability model of nuclear power plant

    International Nuclear Information System (INIS)

    Zhao Bingquan; Fang Xiang

    1999-01-01

    The objective of the paper is to improve the reliability of operation on real nuclear power plant of operators through the simulation research to the cognition reliability of nuclear power plant operators. The research method of the paper is to make use of simulator of nuclear power plant as research platform, to take present international research model of reliability of human cognition based on three-parameter Weibull distribution for reference, to develop and get the research model of Chinese nuclear power plant operators based on two-parameter Weibull distribution. By making use of two-parameter Weibull distribution research model of cognition reliability, the experiments about the cognition reliability of nuclear power plant operators have been done. Compared with the results of other countries such USA and Hungary, the same results can be obtained, which can do good to the safety operation of nuclear power plant

  15. Nuclear power for developing countries

    International Nuclear Information System (INIS)

    Kendall, J.; Kupitz, J.; Rogner, H. H.

    2000-01-01

    Nuclear power is a proven technology which currently makes a large contribution to the electricity supply in a number of countries and, to a much less extent, to heat supply in some countries. Nuclear power is economically competitive with fossil fuels for base load electricity generation in many countries, and is one of the commercially proven energy supply options that could be expanded in the future to reduce environmental burdens, especially greenhouse gas emissions, from the electricity sector. Over the past five decades, nearly ten thousand reactor-years of operating experience have been accumulated with current nuclear power plants. Building upon this background of success and applying lessons learned from the experience of operating plants, new generations of nuclear power plants have been, or are being developed. Improvements incorporated into these advance designs include features that will allow operators more time to perform equipment protection and safety actions in response to equipment failures and other off normal operating conditions, and that will reduce and simplify the actions required. Great attention is also paid to making new plants simpler to operate, inspect, maintain and repair, thus increasing their overall cost efficiency and their compatibility with the infrastructure of developing countries. The paper provides a discussion of future world energy supply and demand projections, current status and prospects for nuclear power, a short summary of advanced reactor concepts and non-electrical applications of nuclear energy for developing countries, and a review of the role of the IAEA. (author)

  16. Directory of nuclear power plants in the world, 1985

    International Nuclear Information System (INIS)

    Fujii, Haruo

    1985-01-01

    This book presents technical information and estimates trends of load factors and construction costs of nuclear power plants. Particularly road maps indicating plants are drawn in, which would be practical in visiting them. The data used here are directly confirmed by operators in every part of the world. Therefore, they reflect up-to-date nuclear power developments and its future. This allows wide and exact understanding of world's nuclear power. Chapter 1 presents nuclear power growth around the world and estimates forecasts based on information from electric power companies: nuclear power growths and the growths in the number of reactors around the world, in WOCA (World outside the Centrally Planned Economies Area), in CPEA (Centrally Planned Economies Area) are analyzed in detail. Chapter 2 presents nuclear power plants on maps by country. The maps show exact locations of nuclear power plants with local cities around them, rivers and lakes. For convenience, symbols are given to aid in identifying the types of reactors. Chapter 3 presents general information of nuclear power plants. Also the addresses of operators, all segments of nuclear power supply industries and nuclear organizations are included. For convenience, the index of nuclear power plants is added. Chapter 4 presents technical information, road maps in large scales and photographs of nuclear power plants in the world. The road maps show exact locations of plants. Chapter 5 presents operating experiences, load factors, refuelling and maintenance outages. The trends of data are analyzed both regionally (WOCA, CPEA) and world-widely. Chapter 6 presents trends of construction costs, component costs as percent of total construction costs and direct costs, and construction durations. (J.P.N.)

  17. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2007-09-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

  18. Development of recycling techniques for nuclear power plant decommissioning waste

    International Nuclear Information System (INIS)

    Ishikura, Takeshi; Oguri, Daiichiro; Abe, Seiji; Ohnishi, Kazuhiko

    2003-01-01

    Recycling of concrete and metal waste will provide solution to reduce waste volume, contributing to save the natural resources and to protect the environment. Nuclear Power Engineering Corporation has developed techniques of concrete and metal recycling for decommissioning waste of commercial nuclear power plants. A process of radioactive concrete usage for mortar solidification was seen to reduce concrete waste volume by 2/3. A concrete reclamation process for high quality aggregate was confirmed that the reclaimed aggregate concrete is equivalent to ordinary concrete. Its byproduct powder was seen to be utilized various usage. A process of waste metal casting to use radioactive metal as filler could substantially decrease the waste metal volume when thinner containers are applied. A pyro-metallurgical separation process was seen to decrease cobalt concentration by 1/100. Some of these techniques are finished of demonstration tests for future decommissioning activity. (author)

  19. Nuclear Power Plant Control and Instrumentation in Italy: Recent developments and future perspectives

    International Nuclear Information System (INIS)

    Santandrea, E.

    1990-01-01

    The result of the ''referendum'' in Italy in November 1987 led to cut-back nuclear activities in Italy, as far as both construction and operation on nuclear plants are concerned. A new PEN (National Energy Plan), calls, however, for a programme of research and industrial development of reactors with inherent and passive safety features. ENEA is now engaged in a critical analysis and comparison of different concepts, particularly aimed on safety and environmental and social impact. A particular attention is devoted to relevant subsystems and components with high innovation degree. For the Control System and Instrumentation there is the aim to define rules and design criteria, by evaluating the impact of inherent safety goals on the C and I design. The effort on man-machine interface is considered essential to increase safety and efficiency of advanced reactors. In the frame of the new National Energy Plan, the ENEA effort in the CI area is part of a more general Industrial Promotion Program oriented to optimize the plant process, reducing the environmental impact of energy systems. In such an effort, some questions can be solved by knowledges originally developed in the nuclear and aero-spatial field. So, the national industrial promotion program, tends to transfer to industrial application the developed competencies on disciplines like: Software engineering and reliability; engineering of diffused systems and local networks; electromagnetical compatibility; industrial diagnostic; expert systems in industrial applications; modelling and simulators; ''intelligent'' detection systems and sensors; process optimization. (author). 3 tabs

  20. Study on the safety evaluation method development for D and D of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sin, S. W.; Kang, G. D.; Kim, H. S.; Son, J. G.; Choi, Y. J.; Lee, K. J.; Koh, E. O.; Kim, K. D.; Ha, J. H. [Korea Hydro and Nuclear Power Co. Ltd., Seoul (Korea, Republic of)

    2004-02-15

    The final goal of decommissioning of Nuclear Power Plant is to remove or to isolate the radioactivity existing at the nuclear facilities which are confronted with termination of operation. The regulatory guidance and technologies of decommissioning have been developed strategically in some advanced countries. They have already stepped into the application stage from the research and development stage. The contents and the scope of this study is as follows, preparation of standard evaluation plan and establishment of standard safety evaluation system for D and D.

  1. Study on the safety evaluation method development for D and D of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sin, S. W.; Kang, G. D.; Kim, H. S.; Son, J. G.; Choi, Y. J.; Lee, K. J.; Koh, E. O.; Kim, K. D.; Ha, J. H.

    2004-02-01

    The final goal of decommissioning of Nuclear Power Plant is to remove or to isolate the radioactivity existing at the nuclear facilities which are confronted with termination of operation. The regulatory guidance and technologies of decommissioning have been developed strategically in some advanced countries. They have already stepped into the application stage from the research and development stage. The contents and the scope of this study is as follows, preparation of standard evaluation plan and establishment of standard safety evaluation system for D and D

  2. Small and medium-sized nuclear power plants

    International Nuclear Information System (INIS)

    Schmidt, R.

    1986-01-01

    Small and medium-sized nuclear power plants have long been under discussion as possible applications of nuclear power in countries with small transmission grid systems, in threshold countries and developing countries, and under special local supply conditions. IAEA has condensed and promoted this interest and tried to establish the demand, and possibilities of meeting it, in special events and campaigns. In recent years, considerable interest was registered even in industrialized countries, but here specially for heating and process heat generation applications and for special purposes and, in medium-sized units, also for combined supplies of electricity and heat. This corresponds to special reactor and plant concepts, some of which have already been developed to a stage at which construction work could begin. The analysis presented deals with necessary preconditions on the sides of the users and the vendors, with problems of economy, infrastructure and financing and with the market prospects of small nuclear power plants. (orig./HP) [de

  3. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2008-01-01

    The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2007/2008 was made up on bases of answers on questionnaires from electric power companies and other nuclear organizations around the world by JAIF. This report is comprised of 18 items, and contains generating capacity of the plants; effect of the Niigata-ken chuetsu-oki earthquake; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities, and so forth. (J.P.N.)

  4. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    2004-01-01

    The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2003 was made up on bases of answers on questionnaires from 81 electric power companies and other nuclear organizations in 33 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

  5. Development of a Flexible Computerized Management Infrastructure for a Commercial Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ali, Syed Firasat; Hajek, Brian K.; Usman, Shoaib

    2006-01-01

    The report emphasizes smooth transition from paper-based procedure systems (PBPSs) to computer-based procedure systems (CBPSs) for the existing commercial nuclear power plants in the U.S. The expected advantages and of the transition are mentioned including continued, safe and efficient operation of the plants under their recently acquired or desired extended licenses. The report proposes a three-stage survey to aid in developing a national strategic plan for the transition from PBPSs to CBPSs. It also includes a comprehensive questionnaire that can be readily used for the first stage of the suggested survey

  6. Development of a Flexible Computerized Management Infrastructure for a Commercial Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ali, Syed Firasat; Hajek, Brian K.; Usman, Shoaib

    2006-05-01

    The report emphasizes smooth transition from paper-based procedure systems (PBPSs) to computer-based procedure systems (CBPSs) for the existing commercial nuclear power plants in the U.S. The expected advantages and of the transition are mentioned including continued, safe and efficient operation of the plants under their recently acquired or desired extended licenses. The report proposes a three-stage survey to aid in developing a national strategic plan for the transition from PBPSs to CBPSs. It also includes a comprehensive questionnaire that can be readily used for the first stage of the suggested survey.

  7. Monitoring support system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashikawa, Yuichi; Kubota, Rhuji; Tanaka, Keiji; Takano, Yoshiyuki

    1996-01-01

    The nuclear power plants in Japan reach to 49 plants and supply 41.19 million kW in their installed capacities, which is equal to about 31% of total electric power generation and has occupied an important situation as a stable energy supplying source. As an aim to keeping safe operation and working rate of the power plants, various monitoring support systems using computer technology, optical information technology and robot technology each advanced rapidly in recent year have been developed to apply to the actual plants for a plant state monitoring system of operators in normal operation. Furthermore, introduction of the emergent support system supposed on accidental formation of abnormal state of the power plants is also investigated. In this paper, as a monitoring system in the recent nuclear power plants, design of control panel of recent central control room, introduction to its actual plant and monitoring support system in development were described in viewpoints of improvement of human interface, upgrade of sensor and signal processing techniques, and promotion of information service technique. And, trend of research and development of portable miniature detector and emergent monitoring support system are also introduced in a viewpoint of labor saving and upgrade of the operating field. (G.K.)

  8. 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

  9. Development of management system for nuclear power plant maintenance and information

    International Nuclear Information System (INIS)

    Nomoto, Toshihiro

    1997-01-01

    In Chubu Electric Power Co., Inc., in order to make maintenance works efficient and improve the management, 'Management system for nuclear power plant maintenance and information' was developed, and its operation on full scale was begun in Hamaoka Nuclear Power Station in October, 1996. This system is composed of equipment management system, maintenance and repair management system and work management system. As the features of the system, the dispersion of functions by client/server method, the installation of the server machines for exclusive use in power stations, the adoption of optical communication network and the ensuring of reliability by the doubled system are mentioned. This system is the function dispersion system by client/server method utilizing the in-plant LAN, and has two server computers with double hot standby constitution. The main functions of three subsystems are described. These three subsystems and piping and instrumentation chart management system and whole company work budget system are connected so as to make dealing works quick and efficient. Hereafter, by reflecting the opinions of the users through the operation, further efficient works are to be aimed at. (K.I.)

  10. Surveillance robot for nuclear power plants

    International Nuclear Information System (INIS)

    White, J.R.; Harvey, H.W.; Satterlee, P.E. Jr.

    1985-01-01

    A demonstration project to determine the feasibility and cost-effectiveness of mobile surveillance robots in nuclear power plants is being conducted by the Remote Technology Corporation (REMOTEC) for the US Nuclear Regulatory Commission. Phase I of the project was completed in March 1984 and included a survey of currently used robotic equipment and the development of a robotics application methodology. Three Tennessee Valley Authority plants were analyzed to identify specific plant areas with a high potential for surveillance robotics. Based on these results, a number of robotic system applications were prepared and evaluated for cost-effectiveness. The system with the highest potential, a mobile surveillance robot, was selected for fabrication and in-plant demonstration testing in a phase II effort. The design, fabrication, and assembly of SURBOT has been completed and cold testing is in process. It will be installed at the Browns Ferry Nuclear Plant early in 1986 for demonstration testing. Current projections are that SURBOT can be used in approx.40 rooms within the auxiliary building and will have annual savings of over 100 person-rem exposure, 1000 sets of C-zone clothing, and 1000 person-hours of labor

  11. Development of the on-site power supply in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Simon, M. [Gesellschaft fuer Reaktorsicherheit - GRS mbH, Schwertnergasse 1, D-5000 Koeln 1, Cologne (Germany)

    1986-02-15

    The design of the on-site power supply is different in German Nuclear Power Plants, depending on age and size of the plant. The cause for this is the evolution of the safety requirements. The general development of the design of safety Systems, which resulted in a strict separation of redundant trains is also reflected in the design of the emergency power system and even the complete on-site power supply System. This will be demonstrated by different examples. The advantages of this design with respect to the availability of on-site power will be explained and verified by means of operating experience. (author)

  12. Developing and assessing accident management plans for nuclear power plants

    International Nuclear Information System (INIS)

    Hanson, D.J.; Johnson, S.P.; Blackman, H.S.; Stewart, M.A.

    1992-07-01

    This document is the second of a two-volume NUREG/CR that discusses development of accident management plans for nuclear power plants. The first volume (a) describes a four-phase approach for developing criteria that could be used for assessing the adequacy of accident management plans, (b) identifies the general attributes of accident management plans (Phase 1), (c) presents a prototype process for developing and implementing severe accident management plans (Phase 2), and (d) presents criteria that can be used to assess the adequacy of accident management plans. This volume (a) describes results from an evaluation of the capabilities of the prototype process to produce an accident management plan (Phase 3) and (b), based on these results and preliminary criteria included in NUREG/CR-5543, presents modifications to the criteria where appropriate

  13. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Friske, A.; Thiele, D.

    1988-01-01

    The IAEA classification of decommissioning stages is outlined. The international development hitherto observed in decommissioning of nuclear reactors and nuclear power stations is presented. The dismantling, cutting and decontamination methods used in the decommissioning process are mentioned. The radioactive wastes from decommissioning are characterized, the state of the art of their treatment and disposal is given. The radiation burdens and the decommissioning cost in a decommissioning process are estimated. Finally, some evaluation of the trends in the decommissioning process of nuclear power plants is given. 54 refs. (author)

  14. Development of Iridium Solid-state Reference Electrode for the Water Chemistry Status Measurement in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Ku, Heekwon; Lim, Dongseok; Cho, Jaeseon

    2013-01-01

    The result of ECP measurement of piping material in nuclear power plant at low temperature using the developed iridium (SSRE) reference electrode is approximately -0.370V. Based on the various results of this study, the developed iridium (SSRE) reference electrode can be applied to the water chemistry environments of nuclear power plant. Various metallic materials used in a nuclear power plant have been exposed to a variety of water chemistry environments and the corrosion of metallic materials occurs due to the reactions between metal structures and water chemistry environments. Therefore, the management of the water chemistry factors is needed to prevent corrosion. The chemical factors affecting the corrosion are pH and Electrochemical Corrosion Potential (ECP). The world-wide studies suggest that ECP and pH are effective indicators for preventing the material damage from water chemistry condition. ECP and pH should be measured as the reference electrodes, and should show stable potential characteristics with fast responses. In this study, the iridium reference electrodes using a solid-state metal oxide electrode has been developed to measure effective indicators such as ECP and pH. The iridium (SSRE) reference electrode for the ECP measurement in water chemistry environment of nuclear power plants has been developed. A calibration for water chemistry measurement was performed by potential measurement of iridium (SSRE) reference electrode with Ag/AgCl (SSRE) reference electrode. The result exhibited a stable potential for 117 hours and a super-Nernst ian response with 63.12mV/p H. In this study, the iridium (SSRE) reference electrode shows super-Nernst ian characteristic and it may be caused by the property of electrolytically coated iridium oxide. Considering the long-term stability of the developed electrode, it is possible to apply as a reference electrode through calibration procedure

  15. Design concepts of nuclear desalination plants

    International Nuclear Information System (INIS)

    2002-11-01

    Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This has been motivated by a variety of factors, including economic competitiveness of nuclear energy, the growing need for worldwide energy supply diversification, the need to conserve limited supplies of fossil fuels, protecting the environment from greenhouse gas emissions, and potentially advantageous spin-off effects of nuclear technology for industrial development. Various studies, and at least one demonstration project, have been considered by Member States with the aim of assessing the feasibility of using nuclear energy for desalination applications under specific conditions. In order to facilitate information exchange on the subject area, the IAEA has been active for a number of years in compiling related technical publications. In 1999, an inter regional technical co-operation project on Integrated Nuclear Power and desalination System Design was launched to facilitate international collaboration for the joint development by technology holders and potential end users of an integrated nuclear desalination system. This publication presents material on the current status of nuclear desalination activities and preliminary design concepts of nuclear desalination plants, as made available to the IAEA by various Member States. It is aimed at planners, designers and potential end-users in those Member States interested in further assessment of nuclear desalination. Interested readers are also referred to two related and recent IAEA publications, which contain useful information in this area: Introduction of Nuclear Desalination: A Guidebook, Technical Report Series No. 400 (2000) and Safety Aspects of Nuclear Plants Coupled with Seawater Desalination Units, IAEA-TECDOC-1235 (2001)

  16. Nuclear energy for developing countries

    International Nuclear Information System (INIS)

    Kemery, L.S.

    1980-01-01

    This paper examines the circumstances which must prevail before a reasonable technical, administrative and sociological case can be made to justify the introduction of nuclear power technology to a developing country. The role played by the IAEA in responding to needs of developing countries is considered and problems of nuclear plant safety and materials safeguards discussed. Plans for nuclear power in several developing countries are outlined

  17. Legal advocacy and nuclear power: the impact of litigation on the Midland nuclear plant

    International Nuclear Information System (INIS)

    Cook, C.E.

    1979-01-01

    The use of litigation as an interest-group strategy is analyzed in relation to the controversy over the development of nuclear power. An assessment is made of the impact of the judicial process, with the litigation involving the Midland, Michigan, nuclear plant serving as a representative case study. In the construction permit hearings for the Midland nuclear plant, which began in 1970, the interest groups were Consumers Power Company, a Michigan utility, and the Saginaw and Mapleton Intervernors, environmentalists dwelling near the proposed plant site. The Nuclear Regulatory Commission issued a construction permit for the plant after a two-year licensing process, but the environmental groups appealed the permit to the United States Court of Appeals for the District of Columbia Circuit. In 1976, the permit was remanded by the court to the Commission for reconsideration, and Consumers Power Company appealed that decision. In 1978, the Supreme Court handed down a unanimous and definitive opinion, Consumers Power Company vs Aeschliman, that upheld the Commission's original issuance of the construction plant. The Midland case well illustrates the detrimental impact that legal advocacy has had on atomic energy by prolonging the regulatory process. The positive consequences of the Court ruling favoring the utility's position were outweighed by the expense involved in the initial ten years of thelicensing and subsequent lawsuits concerning the Midland plant. Consequently, Consumers Power Company is representative of most other American electric companies in its determination that it cannot build additional nuclear plants without mitigation of the uncertainty and duration of the regulatory process. Thus, it may be concluded that the environmental groups' use of legal advocacy at Midland and elsewhere has proven to be an effective strategy for undermining the nuclear industry and for deterring the future development of nuclear power

  18. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1999-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  19. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  20. Good practices with respect to the development and use of nuclear power plant procedures

    International Nuclear Information System (INIS)

    1998-12-01

    This technical publication is intended to provide information to nuclear power plant managers concerning good practices in respect to the development and use of NPP procedures. It is a part of an ongoing project on nuclear power plant instrumentation and control and is based on lessons learned from NPPs and utilities. The overall objective of this project is to provide systematic guidance on current and emerging instrumentation and control technologies including: protection and automation systems, control rooms, operator support systems, training simulators and human factors. It is intended to be applicable to NPPs in Member States that are in operation, under construction or being commissioned. The good practices described are consistent with the IAEA Safety Series recommendations with respect to the development and use of NPP procedures including the four categories: administrative procedures, operating procedures (normal, alarm response, abnormal and emergency procedures), maintenance and technical support procedures, and testing and surveillance procedures

  1. NRC nuclear-plant-analyzer concept and status at INEL

    International Nuclear Information System (INIS)

    Aguilar, F.; Wagner, R.J.

    1982-01-01

    The Office of Research of the US NRC has proposed development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes how we of the INEL envision the nuclear-plant analyzer. The paper also describes a pilot RELAP5 plant-analyzer project completed during the past year and current work. A great deal of analysis is underway to determine nuclear-steam-system response. System transient analysis being so complex, there is the need to present analytical results in a way that interconnections among phenomena and all the nuances of the transient are apparent. There is the need for the analyst to dynamically control system calculations to simulate plant operation in order to perform what if studies as well as the need to perform system analysis within hours of a plant emergency to diagnose the state of the stricken plant and formulate recovery actions. The NRC-proposed nuclear-plant analyzer can meet these needs

  2. Canadian programs on understanding and managing aging degradation of nuclear power plant components

    International Nuclear Information System (INIS)

    Chadha, J.A.; Pachner, J.

    1989-06-01

    Maintaining adequate safety and reliability of nuclear power plants and nuclear power plant life assurance and life extension are growing in importance as nuclear plants get older. Age-related degradation of plant components is complex and not fully understood. This paper provides an overview of the Canadian approach and the main activities and their results towards understanding and managing age-related degradation of nuclear power plant components, structures and systems. A number of pro-active programs have been initiated to anticipate, detect and mitigate potential aging degradation at an early stage before any serious impact on plant safety and reliability. These programs include Operational Safety Management Program, Nuclear Plant Life Assurance Program, systematic plant condition assessment, refurbishment and upgrading, post-service examination and testing, equipment qualification, research and development, and participation in the IAEA programs on safety aspects of nuclear power plant aging and life extension. A regulatory policy on nuclear power plants is under development and will be based on the domestic as well as foreign and international studies and experience

  3. Cooperation of nuclear, thermal and hydroelectric power plants in the power system

    International Nuclear Information System (INIS)

    1984-01-01

    The conference heard 36 papers of which 23 were incorporated in INIS. The subjects discussed were: the development of power industry in Czechoslovakia, methods of statistical analysis of data regarding nuclear power plant operation, the incorporation of WWER nuclear power plants in the power supply system, the standardization of nuclear power plants, the service life of components, use of nuclear energy sources, performance of the reactor accident protection system, the use of nuclear power and heating plants in Hungary, risk analysis, optimization of nuclear power plants, accidents caused by leakage of the primary and secondary circuit. (J.P.)

  4. Nuclear power development

    International Nuclear Information System (INIS)

    Povolny, M.

    1980-01-01

    The development and uses of nuclear power in Czechoslovakia and other countries are briefly outlined. In the first stage, the Czechoslovak nuclear programme was oriented to the WWER 440 type reactor while the second stage of the nuclear power plant construction is oriented to the WWER 10O0 type reactor. It is envisaged that 12 WWER 440 type reactors and four to five WWER 1000 type reactors will be commissioned till 1990. (J.P.)

  5. Data list of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Izumi, Fumio; Ito, Noboru; Higuchi, Suminori; Kobayashi, Kensuke; Tobioka, Toshiaki

    1987-03-01

    The PPD (Nuclear Power Plant Data Base) has been under development in JAERI since 1983 as a six-year program to provide useful information for reactor safety regulation and reactor safety research. Information source of the PPD is mainly based on SAR's (Safety Analysis Reports) of 35 nuclear power plants which are operating, under construction or under licensing review in Japan. The report BWR edition consists of several data lists stored in the PPD, concerning safety design such as performances, equipments and installations of 18 BWR plants in Japan. The informations are based on SAR Attachment Chapter 8 ''Nuclear Reactor Facility Safety Design''. (author)

  6. Nuclear power plants: a unique challenge to fire safety

    International Nuclear Information System (INIS)

    Nowlen, S.P.

    1992-01-01

    The evaluation of fire safety in a nuclear power plant must include the consideration of the impact of a fire on the operability of plant safety equipment and systems. This issue is not typical of the life safety and property protection issues which dominate traditional fire safety concerns. This paper provides a general discussion of the issue of nuclear power plant fire safety as it currently exists in the USA. Included is a discussion of the past history of nuclear power plant fire events, the development of nuclear industry specific fire safety guidelines, the adverse experience associated with the inadvertent operation of fire suppression systems, and the anticipated direction of fire safety requirements for future reactor designs in the USA. (Author)

  7. 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.

  8. Aging management of containment structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.; Graves, H.L. III; Norris, W.E.

    1996-01-01

    Research is being conducted by Oak Ridge National Laboratory under US nuclear regulatory commission (USNRC) sponsorship to address aging management of nuclear power plant containment and other safety-related structures. Documentation is being prepared to provide the USNRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Accomplishments include development of a structural materials information center containing data and information on the time variation of 144 material properties under the influence of pertinent environmental stressors or aging factors, evaluation of models for potential concrete containment degradation factors, development of a procedure to identify critical structures and degradation factors important to aging management, evaluations of non-destructive evaluation techniques, assessments of European and North American repair practices for concrete, review of parameters affecting corrosion of metals embedded in concrete, and development of methodologies for making current condition assessments and service life predictions of new or existing reinforced concrete structures in nuclear power plants. (orig.)

  9. Aging management of containment structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

    1994-01-01

    Research is being conducted by Oak Ridge National Laboratory under U.S. Nuclear Regulatory Commission sponsorship to address aging management of nuclear power plant containment and other safety-related structures. Documentation is being prepared to provide the US-NRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Accomplishments include development of a Structural Materials Information Center containing data and information on the time variation of 144 material properties under the influence of pertinent environmental stressors or aging factors, evaluation of models for potential concrete containment degradation factors, development of a procedure to identify critical structures and degradation factors important to aging management, evaluations of nondestructive evaluation techniques, assessments of European and North American repair practices for concrete, review of parameters affecting corrosion of metals embedded in concrete, and development of methodologies for making current condition assessments and service life predictions of new or existing reinforced concrete structures in nuclear power plants. (author). 29 refs., 2 figs

  10. Aging management of containment structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.; Graves, H.L. III; Norris, W.E.

    1994-01-01

    Research is being conducted by ORNL under US Nuclear Regulatory Commission (USNRC) sponsorship to address aging management of nuclear power plant containment and other safety-related structures. Documentation is being prepared to provide the USNRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Accomplishments include development of a Structural Materials Information Center containing data and information on the time variation of 144 material properties under the influence of pertinent environmental stressors or aging factors, evaluation of models for potential concrete containment degradation factors, development of a procedure to identify critical structures and degradation factors important to aging management, evaluations of nondestructive evaluation techniques. assessments of European and North American repair practices for concrete, review of parameters affecting corrosion of metals embedded in concrete, and development of methodologies for making current condition assessments and service life predictions of new or existing reinforced concrete structures in nuclear power plants

  11. A basic study for development of environmental standard review plan of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

    1999-12-15

    In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

  12. 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)

  13. Nuclear power development: History and outlook

    International Nuclear Information System (INIS)

    Char, N.L.; Csik, B.J.

    1987-01-01

    The history of nuclear power development is briefly described (including the boosts from oil price shocks to the promotion of nuclear energy). The role of public opinion in relation to nuclear power is mentioned too, in particular in connection with accidents in nuclear plants. The recent trends in nuclear power development are described and the role of nuclear power is foreseen. Estimates of total and nuclear electrical generating capacity are made

  14. Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project

    Energy Technology Data Exchange (ETDEWEB)

    Ian McKirdy

    2011-07-01

    The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

  15. 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

  16. Infrastructure development through civil nuclear cooperation

    International Nuclear Information System (INIS)

    Humphrey, A.M.; Burkart, A.R.

    2010-01-01

    Due to growing concerns over electricity demand, energy security, and climate change, numerous countries are considering the construction of new nuclear power plants. Most of these will be built in nations with existing nuclear power programs, but an increasing number of States have expressed serious interest in developing new nuclear power programs. These countries will be faced with many challenges in establishing the robust infrastructures necessary for the safe, secure, and safeguarded deployment of nuclear power. Fortunately, there is much a State can gain through cooperation with other States with more developed programs. By sharing information on previous experience and established best practices, an emerging nuclear energy State can benefit from the lessons learned by its partners. Through a broad range of civil nuclear cooperation, the United States is helping new entrants develop the sound infrastructure necessary to deploy nuclear power plants with the highest standards of safety, security, and nonproliferation

  17. The Process of Legal Drafting Regulation in the Development of the Nuclear Power Plant in Indonesia

    OpenAIRE

    Mardha, Amil

    2009-01-01

    THE PROCESS OF LEGAL DRAFTING REGULATION IN THE DEVELOPMENT OF THE NUCLEAR POWER PLANT IN INDONESIA. In Indonesia, the process of legal drafting to establish the regulation is based on the Act No. 10 Year 2004 on the Establishment of Legislation. The process shall comply with the constitutional and institutional requirements of national political and legal system. In drafting the development of the regulation of nuclear energy, BAPETEN has been involving some other agencies or other related g...

  18. Artificial intelligence in nuclear power plants

    International Nuclear Information System (INIS)

    Haapanen, P.J.

    1990-01-01

    The IAEA Specialists' Meeting on Artificial Intelligence in Nuclear Power Plants was arranged in Helsink/Vantaa, Finland, on October 10-12, 1989, under auspices of the International Working Group of Nuclear Power Plant Control and Instrumentation of the International Atomic Energy Agency (IAEA/IWG NPPCI). Technical Research Centre of Finland together with Imatran Voima Oy and Teollisuuden Voima Oy answered for the practical arrangements of the meeting. 105 participants from 17 countries and 2 international organizations took part in the meeting and 58 papers were submitted for presentation. These papers gave a comprehensive picture of the recent status and further trends in applying the rapidly developing techniques of artificial intelligence and expert systems to improve the quality and safety in designing and using of nuclear power worldwide

  19. Planting on the slope of Yangjiang nuclear power plant by spraying combined materials

    International Nuclear Information System (INIS)

    Li Ning

    2010-01-01

    During the development and construction of nuclear power projects, in order to prevent ecological degradation and soil erosion of slope hazards, taking practical measures in the works or plant is particularly important. through the main high slope green field application of Yangjiang nuclear power plant, introducing mixed vegetation spraying techniques and characteristics of the construction process, for similar projects it is also a good guide. (author)

  20. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    2000-01-01

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

  1. Development of intelligent database program for PSI/ISI data management of nuclear power plant

    International Nuclear Information System (INIS)

    Um, Byong Guk; Park, Un Su; Park, Ik Keun; Park, Yun Won; Kang, Suk Chul

    1998-01-01

    An intelligent database program has been developed under fully compatible with windows 95 for the construction of total support system and the effective management of Pre-/In-Service Inspection data. Using the database program, it can be executed the analysis and multi-dimensional evaluation of the defects detected during PSI/ISI in the pipe and the pressure vessel of the nuclear power plants. And also it can be used to investigate the NDE data inspected repetitively and the contents of treatment, and to offer the fundamental data for application of evaluation data related to Fracture Mechanics Analysis(FMA). Furthermore, the PSI/ISI database loads and material properties can be utilized to secure the higher degree of safety, integrity, reliability, and life-prediction of components and systems in nuclear power plant.

  2. An intelligent tool for the training of nuclear plant operators

    International Nuclear Information System (INIS)

    Cordier, B.

    1990-01-01

    A new type of pedagogical tool has been developped for the training of nuclear power plant operation. This tool combines simulation and expert system. The first process developped is about Steam Generator Tube Rupture (S.G.T.R.). All nuclear power plants will be equiped with this system in 1989 and 1990. After this first experiment, others processes will be developped for this tool

  3. Nuclear power plant maintenance optimisation SENUF network activity

    International Nuclear Information System (INIS)

    Ahlstrand, R.; Bieth, M.; Pla, P.; Rieg, C.; Trampus, P.

    2004-01-01

    During providing scientific and technical support to TACIS and PHARE nuclear safety programs a large amount of knowledge related to Russian design reactor systems has accumulated and led to creation of a new Network concerning Nuclear Safety in Central and Eastern Europe called ''Safety of Eastern European type Nuclear Facilities'' (SENUF). SENUF contributes to bring together all stakeholders of TACIS and PHARE: beneficiaries, end users, Eastern und Western nuclear industries, and thus, to favour fruitful technical exchanges and feedback of experience. At present the main focus of SENUF is the nuclear power plant maintenance as substantial element of plant operational safety as well as life management. A Working Group has been established on plant maintenance. One of its major tasks in 2004 is to prepare a status report on advanced strategies to optimise maintenance. Optimisation projects have an interface with the plant's overall life management program. Today, almost all plants involved in SENUF network have an explicit policy to extend their service life, thus, component ageing management, modernization and refurbishment actions became much more important. A database is also under development, which intends to help sharing the available knowledge and specific equipment and tools. (orig.)

  4. New trends in nuclear power engineering development

    International Nuclear Information System (INIS)

    Krasin, A.K.

    1974-01-01

    The specific features are considered of three designs of nuclear power plants with fast reactors: three-circuit nuclear power plant with liquid sodium as primary and secondary coolant, in the third circuit water vapor being used as turbine working medium, dual cycle nuclear power plant with pressurized helium as primary coolant and water vapor as turbine working medium, direct cycle nuclear power plant with a dissociating gas (nitrogen tetroxide N 2 O 4 ) as reactor coolant and turbine working medium. The version of the direct cycle nuclear power plant with dissociating N 2 O 4 was proposed and being developed by the Institute of Nuclear Engineering of the Academy of Sciencies of the BSSR. The thermal and physical properties of the dissociating gas allow a high-power-density reactor core to be used with a hard neutron spectra resulting in a high breeding ratio and a short doubling time. The pressure range from 150 to 170 bar was proven for this coolant under laboratory conditions and structural materials were chosen that ensure all the components of the direct cycle nuclear power plant to be workable. At present it is difficult to say which of the three versions is the most advantageous. The further development of a full-scale prototypes of a commercial nuclear power plant with a fast reactor and investigation of their technical and economic parameters remain the problems of utmost importance. A possible use of nuclear reactors is shortly considered for process heat production, in ferrous metallurgy, for hydrogen and new isotope production, and for radiation chemistry as well

  5. Development of preventive maintenance technology and advanced service equipment for operating nuclear power plants

    International Nuclear Information System (INIS)

    Abe, Kazuhiro; Sumikawa, Masaharu; Hirakawa, Hiromasa; Arakawa, Tadao; Hasegawa, Kunio; Kato, Kanji.

    1990-01-01

    Hitachi Ltd. as a manufacturer of nuclear power plants has carried out the consistent general preventive maintenance activities from the planning of the plants and the design of maintainability in the construction phase to the planning and working of preventive maintenance in the operation and maintenance phase, and exerted efforts to heighten the capacity ratio and reliability of the plants. For the purpose, the steady activities of reliability improvement have been carried out throughout the whole company, and the rationalization of the planning and management of the preventive maintenance with a computer and the development of the robots to which Al is applied have been promoted. As the technology of upgrading the facilities, boron racks, the control rods having long life and so on were developed, and their practical use is advanced. Moreover for the future, the development of the diagnostic technology on material deterioration using superconductive quantum interference devices (SQUID) is in progress. The preventive maintenance activities in Hitachi Ltd., the technical development for the purpose and the upgrading of the plant facilities are reported. (K.I.)

  6. Development and management of world nuclear power in 2012

    International Nuclear Information System (INIS)

    2012-01-01

    It deals with development and management of nuclear power of foreign countries by the 1st of January 2012 with tables and figures, which includes outline of investigation, operation experience of nuclear power plant of the world, the cardinal number according to the type of operating power plant of the world, using Mox of the world and site of nuclear power plant of the world. There are list of world nuclear power plant, explanation of abbreviations, address book of nuclear power plant of the world and table and figure of major nuclear fuel cycle.

  7. Development of plant maintenance systems

    International Nuclear Information System (INIS)

    Tomita, Jinji; Ike, Masae; Nakayama, Kenji; Kato, Hisatomo

    1989-01-01

    Toshiba is making active efforts for the continuing improvement of reliability and maintainability of operating nuclear power plants. As a part of these efforts, the company has developed new maintenance administration systems, diagnostic monitoring facilities for plant equipments, computer-aided expert systems, and remote-controlled machines for maintenance work. The maintenance administration systems provide efficient work plans and data acquisition capabilities for the management of personnel and equipments involved in nuclear power plant maintenance. The plant diagnostic facilities monitor and diagnose plant conditions for preventive maintenance, as well as enabling rapid countermeasures to be carried out should they be required. Expert systems utilizing artificial intelligence (AI) technology are also employed. The newly developed remote-controlled machines are useful tools for the maintenance inspection of equipment which can not be easily accessed. (author)

  8. Summary of nuclear power plant construction

    International Nuclear Information System (INIS)

    Tamura, Saburo

    1973-01-01

    Various conditions for the construction of nuclear power plants in Japan without natural resources were investigated. Expansion of the sites of plants, change of reactor vessels, standardization of nuclear power plants, possiblity of the reduction of construction period, approaching of nuclear power plants to consuming cities, and group construction were studied. Evaluation points were safety and economy. Previous sites of nuclear power plants were mostly on plane ground or cut and enlarge sites. Proposals for underground or offshore plants have been made. The underground plants were made at several places in Europe, and the ocean plant is now approved in U.S.A. as a plant on a man-made island. Vessels for containing nuclear reactors are the last barriers to the leakage of radioactive substance. At the initial period, the vessels were made of steel, which were surrounded by shielding material. Those were dry well type containers. Then, vessel type changed to pressure-suppression type wet containers. Now, it tends to concrete (PC or RC) type containers. There is the policy on the standardization of nuclear power plants by U.S.A.E.C. in recent remarkable activity. The merit and effect of the standardization were studied, and are presented in this paper. Cost of the construction of nuclear power plants is expensive, and interest of money is large. Then, the reduction of construction period is an important problem. The situations of plants approaching to consuming cities in various countries were studied. Idea of group construction is described. (Kato, T.)

  9. Nuclear power plant life management in a changing business world

    International Nuclear Information System (INIS)

    2000-01-01

    PLIM activities in OECD Member countries and to develop a set of recommendations that plant owners/operators, governments, industry and international organisations could consider as they take decisions on whether to keep the nuclear power option viable through improved plant life management. These recommendations were developed from technical, economic and regulatory viewpoints. The workshop also provided an opportunity for exchanges of information on lessons learned from past successes and failures and to encourage the elaboration of new ideas and strategies for success under deregulated electricity market conditions. (author)

  10. IAEA-IFRAM joint development of nuclear plant aging management handbooks

    International Nuclear Information System (INIS)

    Yeji Kim, II Soon Hwang

    2015-01-01

    As attentions to the beyond design basis accident have increased following Fukushima accident, the importance of aging management for key system, structure and components of nuclear power plant (NPP) also has been emerged as the key factor for safety and reliability of NPPs. The diverse experiences can serve as the foundation for aging management processes that has major trust in the understanding of materials degradation mechanisms. IAEA and IFRAM have collaborated to produce the nuclear plant aging management handbook in order to help entry-level engineers and graduate students understand big pictures. As the number of old NPPs and new-comer countries have increased, sharing experiences and accumulated knowledge from existing nuclear industries has become increasingly important. From this point of view, the handbook has been completed for publication by IAEA which assembled a panel of international experts to integrate the vast body of background knowledge regarding aging mechanism and the extensive know-hows of expertsinto a primer handbook. The next step is to actively utilize the IAEA handbook to produce its web version. In order to reach the ultimate purpose of nuclear safety culture of IAEA, information the handbook should be made easily accessible ana understandable. In this regards, the conversion of IFRAM handbook to web version is being planned. Careful considerations about how to restructure the content and how to reflect opinions from experts and readers are needed. In addition, this handbook can be extended to a training program for maintenance managers, vendors, research organizations and regulators to assist them in their work on aging management in operating NPPs. Through these two aspects, this IFRAM handbook on aging management of NPPs will support of NPP staff both new-comer and established countries. This paper introduces the purpose, approach, structure, content of already completed IAEA handbook and the status and plan for IFRAM Web

  11. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    1998-01-01

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

  12. Development of SC structure modularization in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Mun, Taeyoup

    2008-01-01

    New Focus on NPP are Rising Concerns on Global Warming, Potential energy crisis (geo-political), Improved reliability and safety of nuclear power plant, Advent of Generation 3+ NPP technology and Economical Energy Resource. New NPPs are 6 units in Korea and 23 in Asia being built, 32 units being planned in China by 2020 (150 by 2050), 10 units being planned in US by 2020 and IAEA expects $200 billions on NPP construction next 25 years (up to 30% of total world energy). □ SC(Steel Plate Concrete) structure · Steel Plate is used as a Structural Element instead of Reinforcing Bars in RC · SC structure consists of Steel Plate with Headed Studs. Connected by Tie-bars - The Primary Purpose of Tie-bars is to Stiffen and Hold Together the Plates during Construction Process - Headed Studs are Welded to the Inside of Steel Plate for composite action □ Benefits of SC Structure · Shorten Construction Duration for Re bar, Forming and Scaffolding Works · Minimize Site Labors · Improve the Construction Quality · Enable Construction Sites to be kept Clean □ SC Modularization · Fit for Modular Construction for Structural Features · Fit for Modular Construction for Structural Features · Inattentively Effective for Integrated Modules · Pre-fabrication, Pre-assembly and Modularization □ Project Overview · Project Name: Development of SC structure for Modularization in NPP · Project Type: Electric Power Industry R and D (Ministry of Knowledge Economy) · Duration: Sep. 2005 ∼ Aug. 2008 (36 Months) · Research Team and Scopes - Project Management: Korea Hydro and Nuclear Power Company (KHNP) - Development of Code and Standards for SC Structure: Korea Society of Steel Construction (KSSC) Korea Electric Power Research Institute (KEPRI) - Development of SC Structural Analysis and Design: Korea Power Engineering Company (KOPEC) - Development of Construction Techniques for SC Modularization: KHNP, Korea Institute of Nuclear Safety(KINS), KOPEC □ Performance

  13. 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

  14. Projected role of nuclear power in Egypt and problems encountered in implementing the first nuclear power plant

    International Nuclear Information System (INIS)

    Effat, K.E.A.; Sirry, H.; El-Sharkawy, E.

    1977-01-01

    The increasing rise in fossil-fuel prices has favourably affected the economics of nuclear power generation bringing down the economically competitive size of nuclear units closer to small sizes compatible with grid capacities in developing countries. This encouraged Egypt to turn to nuclear power to fulfil its future power needs. In implementing its first nuclear power plant, Egypt is facing various problems. The capacity of the national electric power system and its inherent characteristics pose certain restrictions on the size and design of the nuclear plant required. The availability of sufficient local qualified management, engineering and technical personnel to participate in both precontractual and construction phases of the plant is quite a major problem. Lack of local developed industry to back up the construction phase implies the dependence to a large extent on imported equipment, materials and technology. The paper reviews the present and projected power demands in Egypt and the factors behind the decision to introduce a nuclear power generation programme. Various problems encountered and anticipated in introducing the first nuclear power plant are also discussed. (author)

  15. An approach to nuclear plant design and modification support for Russian-designed plants in Eastern Europe

    International Nuclear Information System (INIS)

    Ioannidi, J.; Akins, M.J.

    2002-01-01

    The Western nuclear countries have embarked on numerous programs to improve the safety of the Russian-designed nuclear power plants. In Russian-designed plants in Eastern Europe, plant management is being asked for the first time to decide which safety projects to implement and is finding itself lacking in nuclear safety analytical tools and practices, funds, and experience with project management and project engineering skills and tools. Some of the major areas where assistance is needed are: 1) Defining plant weaknesses toward nuclear safety. 2) Evaluating and grading the importance to safety of proposed modification. 3) Project Planning and Scheduling using computer based scheduling software. 4) Project Finance Development and Management using well defined cash flow management techniques. 5) Contract Management and Change Control. 6) Interface Management. Each of these areas requires a significant amount of discussion to understand the issues and problems associated with them. However, this paper is limited to the Project Management areas. This paper encourages the use of a design engineering firm experienced in safety practices and associated management and technical skills to serve as the Owner's Engineer/Project Management Consultant for the program period for a Russian-designed plants located outside Russia. This approach would allow for the availability and transfer of knowledge of safety practices to plant personnel and owners engineers at nuclear plants outside Russia, improving their nuclear safety culture. The plant personnel would control plant modernizations and upgrades based upon a proven and well-defined process for detailed project definition, configuration change control, and project management. This offers the opportunity to enhance the long-term safety culture by developing plant personnel knowledgeable of the safety practices, plant design basis, developing a modification control process enabling them to control the design basis through future

  16. Safety provision for nuclear power plants during remaining running time

    International Nuclear Information System (INIS)

    Rossnagel, Alexander; Hentschel, Anja

    2012-01-01

    With the phasing-out of the industrial use of nuclear energy for the power generation, the risk of the nuclear power plants has not been eliminated in principle, but only for a limited period of time. Therefore, the remaining nine nuclear power plants must also be used for the remaining ten years according to the state of science and technology. Regulatory authorities must substantiate the safety requirements for each nuclear power plant and enforce these requirements by means of various regulatory measures. The consequences of Fukushima must be included in the assessment of the safety level of nuclear power plants in Germany. In this respect, the regulatory authorities have the important tasks to investigate and assess the security risks as well as to develop instructions and orders.

  17. Presenting a model of repair and preventing maintenance of Bushehr nuclear power plants analyzing the data of similar nuclear power plants

    International Nuclear Information System (INIS)

    Parikhan, Hammidreza

    1997-01-01

    Due to the increase application of nuclear energy for producing electricity, special attention must be paid to their maintenance activities in general and preventive maintenance in particular. It has been shown that a well established preventive maintenance programme will enhance the reliability and availability of nuclear power plants. A model of preventive maintenance for Buhehr nuclear power plant which is due to be completed by 2001 is developed. The prescribed model is based on past experiences of VVER nuclear power plants around the world. The utilized data is provided by International Atomic Energy Agency (IAEA) in Vienna, Austria. The data and past experiences reveal such important information as availability, energy loss, types of failures, duration of failure, etc. A strategy for designing a database is established. These data are then analyzed by statistical methods such as Pareto analysis, t-test, K-S test, analysis of variance, etc. The results of our analysis reveal important information in regard to establishment of a well-defined preventive maintenance programme in Buhshehr nuclear power plant. The results show that certain equipment such turbo-generator and control-rods play an important role in the maintenance of a VVER nuclear power plant. Other findings are discussed in great detail

  18. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young

    2016-01-01

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety

  19. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young [KHNP, Daejeon (Korea, Republic of)

    2016-10-15

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety.

  20. Development of Soil Derived Concentration Guidance Levels for Decommissioning at Overseas Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Wook; Yoon, Suk Bon; Kim, Jeongju [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    In Korea, the criteria are expected to be given in terms of dose as in US and Spain. However, since dose cannot be measured, corresponding measurable concentration limits, so-called Derived Concentration Guidance Levels (DCGLs), should be developed for each radionuclide which is expected to be present in the site. Also, as they serve as a goal of decommissioning and direct dismantling and decontamination methods applicable to the site, DCGLs should be developed in the early phase of decommissioning. This paper describes how each overseas nuclear power plant developed its site-specific Soil DCGLs: what kind of post closure use of the site (scenario) was assumed and how the site-specific Soil DCGLs were calculated based on the scenario assumed for each plant. Through this, it is intended to derive lessons learned which will be instructive for future decommissioning of domestic nuclear power plants including Kori Unit 1. It is very important to have as good under-standing as possible of characteristics of the site by collection of relevant information and data in order to apply a scenario which is most foreseeable and plausible for a site to be decommissioned and to provide site-specific inputs to the calculation of the Soil DCGLs. These efforts will help to have not-overly conservative values for the Soil DCGLs, thus thereby reducing the costs and time needed for performing the decommissioning.

  1. Program change management during nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Bushart, Sean; Kim, Karen; Naughton, Michael

    2011-01-01

    Decommissioning a nuclear power plant is a complex project. The project involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As certain project Milestones are met, the evolution of such plant programs and regulations can help optimize project execution and cost. This paper will provide information about these Milestones and the plant departments and programs that change throughout a decommissioning project. The initial challenge in the decommissioning of a nuclear plant is the development of a definitive plan for such a complex project. EPRI has published several reports related to decommissioning planning. These earlier reports provided general guidance in formulating a Decommissioning Plan. This Change Management paper will draw from the experience gained in the last decade in decommissioning of nuclear plants. The paper discusses decommissioning in terms of a sequence of major Milestones. The plant programs, associated plans and actions, and staffing are discussed based upon experiences from the following power reactor facilities: Maine Yankee Atomic Power Plant, Yankee Nuclear Power Station, and the Haddam Neck Plant. Significant lessons learned from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissioning projects. The development of a definitive Decommissioning Plan can result in considerable project savings. The decommissioning plants in the U.S. have planned and executed their projects using different strategies based on their unique plant circumstances. However, experience has shown that similar project milestones and actions applied through all of these projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transitions from an operating plant through decommissioning, the reduction and termination of defunct programs and regulations can help optimize all facets of

  2. Economical aspects of a nuclear power plant project

    International Nuclear Information System (INIS)

    Meldonian, N.L.; Santos, E.M. dos

    1992-01-01

    This work describes different aspects and parameters that should be regarded as guidelines for economic evaluation of small and medium power plant projects. The main objective of an economic evaluation is to establish the plant's unitary cost and its economic figure of merit. To achieve that, a number of studies must be undertaken to compare the global competitiveness of a nuclear power plant with other energetic alternatives. These studies involve macro economy, energy generation, electricity transmission and global feasibility of the enterprise. It is concluded that the economic evaluation of a nuclear power plant should be considered as the culmination of a long process of planning at a national level. The main reasons are the investments involved, the technological developments required and political implications of the utilization of nuclear power energy. (author)

  3. Implementing national nuclear safety plan at the preliminary stage of nuclear power project development

    International Nuclear Information System (INIS)

    Xue Yabin; Cui Shaozhang; Pan Fengguo; Zhang Lizhen; Shi Yonggang

    2014-01-01

    This study discusses the importance of nuclear power project design and engineering methods at the preliminary stage of its development on nuclear power plant's operational safety from the professional view. Specifically, we share our understanding of national nuclear safety plan's requirement on new reactor accident probability, technology, site selection, as well as building and improving nuclear safety culture and strengthening public participation, with a focus on plan's implications on preliminary stage of nuclear power project development. Last, we introduce China Huaneng Group's work on nuclear power project preliminary development and the experience accumulated during the process. By analyzing the siting philosophy of nuclear power plant and the necessity of building nuclear safety culture at the preliminary stage of nuclear power project development, this study explicates how to fully implement the nuclear safety plan's requirements at the preliminary stage of nuclear power project development. (authors)

  4. RATU - Nuclear power plant structural safety research programme

    International Nuclear Information System (INIS)

    Rintamaa, R.

    1992-07-01

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

  5. Nuclear accidents and safety measures of domestic nuclear power plants

    International Nuclear Information System (INIS)

    Song Zurong; Che Shuwei; Pan Xiang

    2012-01-01

    Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

  6. 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.)

  7. Current developments in mechanized non-destructive testing in nuclear power plants; Aktuelle Entwicklungen bei mechanisierten, zerstoerungsfreien Pruefungen in Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Zeilinger, R. [intelligeNDT System und Services GmbH und Co. KG, Erlangen (Germany)

    2008-01-15

    Nuclear power plants require frequent in-service activities to be carried out conscientiously in areas potentially hazardous to human operators (because of the associated radiation exposure), such as non-destructive testing of pressurized components of the steam system. Locations to be inspected in this way include the reactor pressure vessel, core internals, steam generators, pressurizers, and pipes. The codes to be used as a basis of these inspections demand high absolute positioning and repeating accuracy. These requirements can be met by mechanized test procedures. Accordingly, many new applications of, mostly mobile, robots have been developed over the past few years. The innovative control and sensor systems for stationary and mobile robots now on the market offer a potential for economic application in a large number of new areas in inspection, maintenance and service in nuclear power plants. More progress in this area is expected for the near future. Areva NP founded the new NDT Center, NETEC (Non-destructive Examination Technical Center), as a global technical center for non-destructive materials testing. NETEC is to advance research and development of all basic NDT technologies, robotics included. For many years, intelligeNDT has offered solutions and products for a variety of inspection and testing purposes and locations in nuclear power plants and is involved in continuous further development of the experience collected in nuclear power plants on the spot. (orig.)

  8. Development of new CAD system for steel structures of nuclear power plants

    International Nuclear Information System (INIS)

    Morii, Yasuhiro; Kudou, Takashi; Kouno, Kenichi; Yamada, Koutarou

    2000-01-01

    IHI has developed a new Three-Dimensional Computer-Aided Design (3D-CAD) system to improve the design efficiency and quality of the steel structure of nuclear power plants. This system covers every design phase from the initial arrangement of structure to the production design sharing the same database. The system incorporates the design rules and professional expertise of designers, and enable easy and efficient design. The system can easily generate the three-dimensional data for structures, model data for stress analyses and composite arrangement data. The system has already been applied to several plants under construction and has achieved excellent results. The outline of the new CAD system is introduced. (author)

  9. Off-shore nuclear power plant

    International Nuclear Information System (INIS)

    Nakanishi, T.

    1980-01-01

    In order to avoid losses of energy and seawater pollution an off-shore nuclear power plant is coupled with a power plant which utilizes the temperature difference between seawater and hot reactor cooling water. According to the invention the power plant has a working media loop which is separated from the nuclear power plant. The apparative equipment and the operational characteristics of the power plant are the subject of the patent. (UWI) [de

  10. Plant life management optimized utilization of existing nuclear power plants

    International Nuclear Information System (INIS)

    Watzinger, H.; Erve, M.

    1999-01-01

    For safe, reliable and economical nuclear power generation it is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

  11. The Development of a Snubber Management System for Welds in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Hyun Ju; Cho, Yong-Bae; Kim, Yoo Sung [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    There are snubbers, spring hanger, anchors, rigid supports for the structures which support the static and/or dynamic loads such as thermal load, pressure, impact and vibration from components and pipings of nuclear power plants. Snubbers constrain the displacements generated by loads transmitted to components and systems abruptly. When the loss of function of snubber during normal operation, the thermal load and pressure transmit directly to structures such as pipings and components, and additional loads, which were not considered during the design stage, act on the structures. Therefore, according to regulatory requirement to confirm the stability of supporting system, the inspection for the snubber is reflected to in-service inspection (ISI) and in-service test (IST) plans. In order to comply with the regulatory requirement, KHNP has performed the ISI and IST and inspected the snubbers. As the increment of operating year of nuclear power plants in Korea, the possibility of deterioration of equipment is higher. Therefore, the security related to the integrity of equipment becomes more important. The snubber takes an important role related to the structural integrity equipped on principal pipings. 100% snubbers are inspected during pre-service inspection and 10% snubbers are inspected during in-service inspection as a sample in nuclear power plants in Korea. KHNP has been developed a snubber management system because there was no management tool for snubbers to show the inspection and maintenance results systematically. The inspection and maintenance results of snubbers can be easily reached by plants, head office and CRI. Moreover, the information related to inspection history and condition of snubber can be effectively inquired.

  12. Distributing radiation management system of nuclear power plants

    International Nuclear Information System (INIS)

    Mihoya, Eiichi; Akashi, Michio

    1999-01-01

    The importance of radiation management for nuclear facilities including nuclear power plants has increased as the general public understanding has progressed, and necessary information for management must be processed exactly and quickly. In nuclear power plants, radiation management is performed by each individual operation, and collected information is managed by the system of each operation. The distributing radiation management system has been developed aiming to use a general-purpose LAN and make quick and efficient use of information managed by individual operations. This paper describes the system configuration and functions. (author)

  13. Utility survey on nuclear power plant siting and nuclear energy centers

    International Nuclear Information System (INIS)

    Cope, D.F.; Bauman, H.F.

    1977-01-01

    Most of the large U.S. utilities were surveyed by telephone and mail on questions concerning nuclear power plant siting and nuclear energy centers (NECs). The main purpose of the survey was for guidance of ERDA's NEC program. The questions covered the following topics: availability of sites; impact of environmental and other restraints; plans for development of multi-unit sites; interest in NEC development; interest in including fuel-cycle facilities in NECs; and opinions on the roles desired for the state and Federal governments in power plant siting. The main conclusion of the survey was that, while many utilities were considering multiple-unit sites of 2 to 5 units, none were planning larger energy centers at the present time. However, several expressed interest in NECs as a long-range future development

  14. Building of nuclear power plant

    International Nuclear Information System (INIS)

    Saito, Takashi.

    1997-01-01

    A first nuclear plant and a second nuclear power plant are disposed in adjacent with each other in a building for a nuclear reactor. A reactor container is disposed in each of the plants, and each reactor container is surrounded by a second containing facility. A repairing chamber capable of communicating with the secondary containing facilities for both of the secondary containing facilities is disposed being in contact with the second containing facility of each plant for repairing control rod driving mechanisms or reactor incorporated-type recycling pumps. Namely, the repairing chamber is in adjacent with the reactor containers of both plants, and situated between both of the plants as a repairing chamber to be used in common for both plants. Air tight inlet/exit doors are formed to the inlets/exits of both plants of the repairing chamber. Space for the repairing chamber can be reduced to about one half compared with a case where the repairing chamber is formed independently on each plant. (I.N.)

  15. AP1000 plant construction in China: Ansaldo Nucleare contribution

    International Nuclear Information System (INIS)

    Frogheri, Monica; Saiu, Gianfranco

    2009-01-01

    On 24th of July 2007 Westinghouse Electric Co. signed landmark contracts with China's State Nuclear Power Technology Corporation (SNPTC), to provide four AP1000 nuclear power plants in China. The AP1000 is a two-loop 1117 MWe Pressurized Water Reactor (PWR). It is based on proven technology, but with an emphasis on safety features that rely on natural driving forces, such as pressurized gas, gravity flow, natural circulation flow and convection. Ansaldo Nucleare has provided a significant support to the passive plant technology development and, starting from 2000, is cooperating with Westinghouse to development of the AP1000 Plant. In the frame of the AP1000 Chinese agreement, Ansaldo Nucleare, in Joint Venture with Mangiarotti Nuclear, has signed a contract with Westinghouse for the design and the supply of innovative components to be installed in the first AP1000 unit to be constructed at the Sanmen site. The contract includes: the design of the steel containment vessel, preparation of construction and fabrication, specifications, design and supply of SCV mechanical penetrations, air locks and equipment hatches. Moreover, Ansaldo Nucleare is in charge of the final design of the AP1000 PRHR-HX and together with Mangiarotti Nuclear will supply the component for the Sanmen Unit 1 NPP. The paper presents an overview of the design and manufacturing activities performed by Ansaldo Nucleare and its partners for the AP1000 plant in China. (authors)

  16. Operational characteristics of nuclear power plants - modelling of operational safety

    International Nuclear Information System (INIS)

    Studovic, M.

    1984-01-01

    By operational experience of nuclear power plants and realize dlevel of availability of plant, systems and componenst reliabiliuty, operational safety and public protection, as a source on nature of distrurbances in power plant systems and lessons drawn by the TMI-2, in th epaper are discussed: examination of design safety for ultimate ensuring of safe operational conditions of the nuclear power plant; significance of the adequate action for keeping proess parameters in prescribed limits and reactor cooling rquirements; developed systems for measurements detection and monitoring all critical parameters in the nuclear steam supply system; contents of theoretical investigation and mathematical modeling of the physical phenomena and process in nuclear power plant system and components as software, supporting for ensuring of operational safety and new access in staff education process; program and progress of the investigation of some physical phenomena and mathematical modeling of nuclear plant transients, prepared at faculty of mechanical Engineering in Belgrade. (author)

  17. 75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2010-10-29

    ... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Notice of Withdrawal of...) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC, the licensee, to withdraw its... for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, located in Calvert County, MD. The...

  18. Development of automatic pipe welder for nuclear power plant

    International Nuclear Information System (INIS)

    Iwamoto, Taro; Ando, Shimon; Omae, Tsutomu; Ito, Yoshitoshi; Araya, Takeshi.

    1978-01-01

    Numerous pipings are installed in nuclear power plants, and of course, the reliability of these pipings are very important to preserve the safety of the plants. These pipings undergo periodic inspection yearly, and when some defects are found or some reconstructions to superior systems are made, field welding in the plants is required. When the places to be welded are in containment vessels, the works must be carried out in radiation environment. In order to maintain the highest quality of welding and to reduce the radiation exposure of workers, many skilled workers are required. This automatic pipe welder was developed to solve these problems, aiming at carrying out welding works by remote control at the safe places outside containment vessels. Especially in order to obtain the highest quality of welding, it was not perfectly automated, but the man-machine system so as to enable to utilize the delicate sense of workers was adopted. The visual and contact detecting systems to monitor welding works, remote control system, computer control, light, small and easily installed welding head, grinding and supersonic flow detecting equipments, the power source of transistor switching type, air cooling equipment, and the function for setting welding conditions according to algorithm were added to the welding machine. The outline and main components of this automatic pipe welder are explained. (Kako, I.)

  19. Electromagnetic compatibility of nuclear power plants

    International Nuclear Information System (INIS)

    Cabayan, H.S.

    1983-01-01

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

  20. Nuclear power plants in populated areas

    International Nuclear Information System (INIS)

    Wachsmann, F.

    1973-01-01

    The article first deals with the permanently increasing demand for electical power. Considering the ever growing energy demand which can no longer be covered by conventional power plants, it has become necessary to set up nuclear power plants of larger range. The author presents in a survey the basic function of nuclear power plants as well as the resulting risks and safety measures. The author concludes that according to present knowledge there is no more need to erect nuclear power plants outside densely populated urban areas but there is now the possibility of erecting nuclear power plants in densely populated areas. (orig./LH) [de

  1. Safety evaluation of nuclear power plant against the virtual tsunami

    International Nuclear Information System (INIS)

    Chin, S. B.; Imamura, Fumihiko

    2004-01-01

    The main scope of this study is the numerical analysis of virtual tsunami event near the Ulchin Nuclear Power Plants. In the numerical analysis, the maximum run-up height and draw-down are estimated at the Ulchin Nuclear Power Plants. The computer program developed in this study describes the propagation and associated run-up process of tsunamis by solving linear and nonlinear shallow-water equations with finite difference methods. It can be used to check the safety of a nuclear power plant against tsunami attacks. The program can also be used to calculate run-up height of wave and provide proper design criteria for coastal facilities and structures. A maximum inundation zone along the coastline can be developed by using the moving boundary condition. As a result, it is predicted that the Ulchin Nuclear Power Plants might be safe against the virtual tsunami event. Although the Ulchin Nuclear Power Plants are safe against the virtual tsunami event, the occurrence of a huge tsunami in the seismic gap should be investigated in detail. Furthermore, the possibility of nearshore tsunamis around the Korean Peninsula should also be studied and monitored continuously

  2. Loss of benefits resulting from mandated nuclear plant shutdowns

    International Nuclear Information System (INIS)

    Peerenboom, J.P.; Buehring, W.A.

    1982-01-01

    This paper identifies and discusses some of the important consequences of nuclear power plant unavailability, and quantifies a number of technical measures of loss of benefits that result from regulatory actions such as licensing delays and mandated nuclear plant outages. The loss of benefits that accompany such regulatory actions include increased costs of systems generation, increased demand for nonnuclear and often scarce fuels, and reduced system reliability. This paper is based on a series of case studies, supplemented by sensitivity studies, on hypothetical nuclear plant shutdowns. These studies were developed by Argonne in cooperation with four electric utilities

  3. Basic Study of Establishment of Quality Assurance Processes to Develop an Integrated Quality Assurance System for Nuclear Power Plant Construction

    International Nuclear Information System (INIS)

    Lim, Byungki; Moon, Byeongsuk; Lee, Jae Kyoung

    2014-01-01

    An integrated quality assurance system has necessitated carrying out quality assurance programs in a systematic manner because the opportunities to expand business in overseas markets have increased since the export of a nuclear power plant to UAE in 2009. In this study, we use PDCA method to systematically analyze the quality assurance procedures that were used in previous projects for constructing nuclear power plants. We reached a classification system of quality assurance processes at each phase of nuclear power plant construction by integrating similar work related to quality such as planning, design, equipment manufacturing, construction and start-up. We also established a hierarchy of quality assurance processes to develop an integrated quality assurance system as a technology goal to be developed later. To obtain most updated quality assurance activities, a quality assurance process is structured by integrating similar works analyzed from quality assurance procedures through PDCA cycle method. At the implementation phase of Hierarchy of quality processes and sequence of processes for constructing nuclear power plant are established in this study. Integrated quality assurance system is to be developed by connecting organizations as well as stakeholders such as owners, Architect engineering, suppliers, contractors, and sub-contractors to carry out assigned work efficiently

  4. Basic Study of Establishment of Quality Assurance Processes to Develop an Integrated Quality Assurance System for Nuclear Power Plant Construction

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Byungki; Moon, Byeongsuk; Lee, Jae Kyoung [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

    2014-05-15

    An integrated quality assurance system has necessitated carrying out quality assurance programs in a systematic manner because the opportunities to expand business in overseas markets have increased since the export of a nuclear power plant to UAE in 2009. In this study, we use PDCA method to systematically analyze the quality assurance procedures that were used in previous projects for constructing nuclear power plants. We reached a classification system of quality assurance processes at each phase of nuclear power plant construction by integrating similar work related to quality such as planning, design, equipment manufacturing, construction and start-up. We also established a hierarchy of quality assurance processes to develop an integrated quality assurance system as a technology goal to be developed later. To obtain most updated quality assurance activities, a quality assurance process is structured by integrating similar works analyzed from quality assurance procedures through PDCA cycle method. At the implementation phase of Hierarchy of quality processes and sequence of processes for constructing nuclear power plant are established in this study. Integrated quality assurance system is to be developed by connecting organizations as well as stakeholders such as owners, Architect engineering, suppliers, contractors, and sub-contractors to carry out assigned work efficiently.

  5. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  6. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  7. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  8. Understanding and managing corrosion in nuclear power plants

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Jarrell, D.B.; Sinha, U.P.; Shah, V.N.

    1991-03-01

    The main theme of this paper is a concept: understanding and managing corrosion in nuclear power plants. The concept is not new--in various forms the concept has been applied throughout the development and maturing of nuclear technology. However, the concept has frequently not been well conceived and applied. Too often, understanding corrosion has been based on reaction rather than on anticipation. Regulatory and utility industry initiatives are creating a climate and framework for more effective application of the concept. This paper characterizes the framework and provides some illustrations of how the concept is being applied, drawing from work conducted under the Nuclear Plant Aging Research (NPAR) Program, sponsored by the Nuclear Regulatory Commission's (NRCs) Office of Research. Nuclear plants are becoming an increasingly important factor in the national electrical grid. Initiatives are currently underway to extend the operating licenses beyond the current 40-year period and to evaluate advanced reactor designs the feature higher safety factors. Corrosion has not caused a major nuclear accident, but numerous corrosion mechanisms, have degraded nuclear systems and components. New corrosion phenomena continue to appear, and occasionally corrosion phenomena cause reactor shutdowns. Effective application of understanding and managing corrosion is important to safe and economic operation of the nuclear plants and also to public perception of a soundly operated technology. 53 refs., 11 figs., 5 tabs

  9. Computer simulation of nuclear pollutant diffusion from Shimane nuclear power plants and development of an evacuation strategy in the event of a nuclear incident

    International Nuclear Information System (INIS)

    Yakura, Haruna; Kurimasa, Akihiro

    2012-01-01

    Beginning from Tohoku (northeastern) Earthquake on March 11, an accident at the Fukushima Dai-ichi Nuclear Power Plant resulted in a substantial release of radioactivity to the environment. The accident forced a large number of residents to evacuate from surrounding areas. Moreover, the nuclear incident was life-threatening for the elderly and for people with serious illnesses who were confined in hospital or nursing homes. Strikingly, the causes of death were not directly attributed to radiation exposure but to problems encountered during evacuation. Using nuclear diffusion data from the Fukushima incident, we simulated nuclear pollutant dispersion using computer software A2C in an area of Tottori and Shimane Prefectures surrounding the Shimane Nuclear Power Plant. We generated a model for the spread of nuclear pollutants around the Emergency Planning Zone, id est (i.e.) EPZ. From these findings, we proposed evacuation strategies for residents near the power plant to ensure a safe and reliable escape from nuclear pollutants. Our recommendations include: immediate evacuation from PAZ area (within 5 km), securing indoor shelter in the area of the UPZ (from 5 km to 30 km) and preparations to evacuate further outwards from the nuclear plant site, daytime evacuation within a 30 km area after considering wind direction and velocity, and preparation of a planned evacuation strategy that identifies secure facilities for weaker people in the event of a disaster. (author)

  10. Education, training and work experience among nuclear power plant workers

    International Nuclear Information System (INIS)

    Blair, L.M.; Doggette, J.

    1980-01-01

    This paper uses a unique data set to examine the prior work experience, training, and education of skilled and technical workers in United States nuclear power plants. The data were collected in the latter half of 1977 by the International Brotherhood of Electrical Workers (IBEW) in a survey of union locals in nuclear power plants. The survey results provided substantial evidence that workers in United States nuclear power plants have a relatively high level of education, training, and skill development. Analysis of average education by age did not reveal any significant differences in years of schooling between younger and older workers. Very high rates of participation in formal training programmes were reported by all types of workers. The most common type of training programme was held on-site at the power plant and was provided by utility personnel. The majority of workers reported previous work experience related to nuclear power plant activities. Almost one-third of the workers had been directly involved in nuclear energy in a previous job, the majority of these through the United States Navy nuclear programme. However, the newer plants are hiring relatively fewer persons with previous nuclear experience. (author)

  11. Advance in study of intelligent diagnostic method for nuclear power plant

    International Nuclear Information System (INIS)

    Zhou Gang; Yang Li

    2008-01-01

    The advance of research on the application of three types of intelligent diagnostic approach based on neural network (ANN), fuzzy logic and expert system to the operation status monitoring and fault diagnosis of nuclear power plant (NPP) was reviewed. The research status and characters on status monitoring and fault diagnosis approaches based on neural network, fuzzy logic and expert system for nuclear power plant were analyzed. The development trend of applied research on intelligent diagnostic approaches for nuclear power plant was explored. The analysis results show that the research achievements on intelligent diagnostic approaches based on fuzzy logic and expert system for nuclear power plant are not much relatively. The research of intelligent diagnostic approaches for nuclear power plant concentrate on the aspect of operation status monitoring and fault diagnosis based on neural networks for nuclear power plant. The advancing tendency of intelligent diagnostic approaches for nuclear power plant is the combination of various intelligent diagnostic approaches, the combination of neural network diagnostic approaches and other diagnostic approaches as well as multiple neural network diagnostic approaches. (authors)

  12. Licensing the First Nuclear Power Plant. INSAG-26. A report by the International Nuclear Safety Group (Russian Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This report is primarily addressed to policy makers and nuclear safety regulatory bodies in IAEA Member States planning to establish their first nuclear power plant. It outlines the key challenges with suggestions on how the regulator and policy makers might address them and also prepare for further development of nuclear power in the country. INSAG believes that development of technical competence of the national regulatory body is a necessary condition for the safe development of nuclear power. Therefore, regulatory infrastructure development should be a national policy requirement, as opposed to being a challenge only for the regulator. A major challenge in the deployment of the first nuclear power plant is the development of the underlying nuclear safety infrastructure and knowledge base. Since an independent regulatory body is an important part of such infrastructure, its establishment and development must be addressed at an early stage and adequate resources must be made available for this purpose. This is to ensure smooth and efficient conduct of the licensing process and regulatory oversight of the first nuclear power plant through an informed decision making process. It is essential that the legal framework starts to be implemented with a main component being the issuance of a nuclear law establishing fundamental principles and defining the responsibilities of the principal organizations, particularly the operating organization and the regulatory body. The regulatory body on its part should develop the regulatory framework that includes the establishment of regulations against which the nuclear power project will be assessed, definition of the licensing steps and corresponding documentation to be submitted by the applicant, and the implementation of a quality management system. It is expected that the 'reference plant' concept will be employed whereby the country's first nuclear power plant would have essentially the same design and safety

  13. 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

  14. Managing the first nuclear power plant project

    International Nuclear Information System (INIS)

    2007-05-01

    Energy is essential for national development. Nearly every aspect of development - from reducing poverty and raising living standards to improving health care, industrial and agricultural productivity - requires reliable access to modern energy resources. States may have different reasons for considering starting a nuclear power project to achieve their national energy needs, such as: lack of available indigenous energy resources, the desire to reduce dependence upon imported energy, the need to increase the diversity of energy resources and/or mitigation of carbon emission increases. The start of a nuclear power plant project involves several complex and interrelated activities with long duration. Experience shows that the time between the initial policy decision by a State to consider nuclear power up to the start of operation of its first nuclear power plant is about 10 to 15 years and that before specific project management can proceed, several key infrastructure issues have to be in place. The proper management of the wide scope of activities to be planned and implemented during this period represents a major challenge for the involved governmental, utility, regulatory, supplier and other supportive organizations. The main focus is to ensure that the project is implemented successfully from a commercial point of view while remaining in accordance with the appropriate engineering and quality requirements, safety standards and security guides. This publication is aimed at providing guidance on the practical management of a first nuclear power project in a country. There are many other issues, related to ensuring that the infrastructure in the country has been prepared adequately to ensure that the project will be able to be completed, that are only briefly addressed in this publication. The construction of the first nuclear power plant is a major undertaking for any country developing a nuclear power programme. Worldwide experience gained in the last 50 years

  15. Proceedings of the 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santoso; Lasman, As Natio

    2003-08-01

    The ninth proceedings of seminar safety and technology of nuclear power plant and nuclear facilities held by National Nuclear Energy Agency and PLN-JTK. 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 Sustainable and High Technology. This seminar cover all aspects Technology, Power Reactor, Research Reactor High Temperature Reactor and Nuclear Facilities. There are 20 articles have separated index

  16. An Embalse nuclear power plant basic principles simulator

    International Nuclear Information System (INIS)

    Fernandez, Oscar; Galdoz, Erwin; Flury, Celso; Fontanini, Horacio

    1989-01-01

    A nuclear power plant basic principles simulator is a package of programs that numerically solve the dynamic equations of the simulated plant. This kind of tools is mainly used in the first step of training of operational personnel, to allow mental representation of physical phenomena governing the plant. They are also used for students or professional training, and experienced operators can also improve there performance under abnormal operation situations using the simulator. For the Embalse nuclear power plant, mainly the thermohydraulic behaviour, is simulated. The mathematical model was adapted from MANUVR, a code developed at the Electric Systems and Control Department of the National Atomic Energy Commission (CNEA). (Author) [es

  17. Industry based performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    Connelly, E.M.; Van Hemel, S.B.; Haas, P.M.

    1990-07-01

    This report presents the results of the first phase of a two-phase study, performed with the goal of developing indirect (leading) indicators of nuclear power plant safety, using other industries as a model. It was hypothesized that other industries with similar public safety concerns could serve as analogs to the nuclear power industry. Many process industries have many more years of operating experience, and many more plants than the nuclear power industry, and thus should have accumulated much useful safety data. In Phase 1, the investigators screened a variety of potential industry analogs and chose the chemical/petrochemical manufacturing industry as the primary analog for further study. Information was gathered on safety programs and indicators in the chemical industry, as well as in the nuclear power industry. Frameworks were selected for the development of indicators which could be transferred from the chemical to the nuclear power environment, and candidate sets of direct and indirect safety indicators were developed. Estimates were made of the availability and quality of data in the chemical industry, and plans were developed for further investigating and testing these candidate indicators against safety data in both the chemical and nuclear power industries in Phase 2. 38 refs., 4 figs., 7 tabs

  18. Nuclear power plant maintenance optimisation SENUF network activity

    Energy Technology Data Exchange (ETDEWEB)

    Ahlstrand, R.; Bieth, M.; Pla, P.; Rieg, C.; Trampus, P. [Inst. for Energy, EC DG Joint Research Centre, Petten (Netherlands)

    2004-07-01

    During providing scientific and technical support to TACIS and PHARE nuclear safety programs a large amount of knowledge related to Russian design reactor systems has accumulated and led to creation of a new Network concerning Nuclear Safety in Central and Eastern Europe called ''Safety of Eastern European type Nuclear Facilities'' (SENUF). SENUF contributes to bring together all stakeholders of TACIS and PHARE: beneficiaries, end users, Eastern und Western nuclear industries, and thus, to favour fruitful technical exchanges and feedback of experience. At present the main focus of SENUF is the nuclear power plant maintenance as substantial element of plant operational safety as well as life management. A Working Group has been established on plant maintenance. One of its major tasks in 2004 is to prepare a status report on advanced strategies to optimise maintenance. Optimisation projects have an interface with the plant's overall life management program. Today, almost all plants involved in SENUF network have an explicit policy to extend their service life, thus, component ageing management, modernization and refurbishment actions became much more important. A database is also under development, which intends to help sharing the available knowledge and specific equipment and tools. (orig.)

  19. Construction plant requirements for nuclear sites

    International Nuclear Information System (INIS)

    Tatum, C.B.; Harris, J.A.

    1981-01-01

    Planning and developing the temporary construction plant facilities for a nuclear project is equivalent to providing utility services for a small city. Provision of adequate facilities is an important factor in the productivity of both the manual and non-manual work force. This paper summarizes construction facility requirements for a two unit (1300 MWe each) nuclear project. Civil, mechanical and electrical facilities are described, including design, installation and operation. Assignment of responsibility for specific work tasks regarding the construction plant is also discussed. In presenting this data, the authors seek to transfer experience and assist in the provision of adequate facilities on future projects

  20. Owners of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-11-01

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

  1. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2000-01-01

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

  2. Advanced plant design recommendations from Cook Nuclear Plant experience

    International Nuclear Information System (INIS)

    Zimmerman, W.L.

    1993-01-01

    A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

  3. Feasibility of risk-informed technology for japanese nuclear power plants

    International Nuclear Information System (INIS)

    Yoshida, Tomoo; Fujioka, Terutaka; Kirimoto, Yorihiro; Ueda, Nobuyuki; Kinoshita, Izumi; Kashima, Koichi

    2000-01-01

    Risk-informed technology utilizes Probabilistic Safety Assessment for streamlining the maintenance of nuclear power plants. With this technology, plant components are categorized as either high or low-safety-significant components. The Maintenance requirements focuses on high safety-significant components and are relieved for low safety significant ones. This is expected to reduce plant cost while maintaining safety. We investigated especially risk-informed inservice inspection of piping in U.S. nuclear power plants in the interest of determining its feasibility for Japanese plants. Quantitative and qualitative RI-ISI methods were developed by the ASME/Westinghouse Owners Group and EPRI, respectively. These methods have been incorporated in the ASME Section 11 Code Cases and endorsed by the U.S. Nuclear Regulatory Commission. The quantitative method evaluates component segment risks in terms of pipe failure probability calculated with a probabilistic fracture mechanics(PFM) model and pipe failure impact categorization on core damage frequency(CDF) calculated with PSA. The qualitative method uses pipe failure potential categorization derived from the plant service experiences and pipe failure impact on CDF derived from the PSA insight. The PFM model is applicable only to failures from initial welding defects and stress corrosion cracking, therefore it does not cover such significant failure mechanisms found in nuclear power plants as corrosion or high-cycle fatigue, etc.. Thus, a qualitative failure potential categorization method was developed on the basis of the service experiences of the U.S. nuclear power plants, so that appropriate categorization rules must be developed on the service experiences in Japanese plants. Accordingly, we have devised a software framework with a computer-aided system for the selection of risk significant elements. This system consists of a piping failure database module, a piping failure analysis module, and a piping failure potential

  4. Refueling outage services in Spanish Nuclear Power Plants

    International Nuclear Information System (INIS)

    Landete, J. L.; Soto, M.; Nunuez, A.

    2007-01-01

    DOMINGUIS Group, through its 75 years of business development, has positioned as the Spanish leader Group in Services for the Nuclear Energy and Petrochemical Sectors. In this article, we present the most significant services summary that, through the companies that constitute DOMINGUIS Group, we have developed in Refueling Outage in Spanish Nuclear Power Plants. (Author)

  5. Development of new construction technologies for nuclear power plant

    International Nuclear Information System (INIS)

    Kawamata, Susumu; Itoh, Daisuke; Ichizono, Katsuyuki

    1995-01-01

    In order to proceed rationally with the construction of a nuclear power station, the followings are the subject to solve beside reducing the construction cost: shortening the construction period, improving the quality, and securing safety in the construction work. As a measure to solve the matters, we correctly construct the plant mainly applying 'all-weather proof construction method' and 'pre-assembled large-block construction method'. Furthermore, as the plant construction control system, we perform a construction work applying the design change management system, pre-assessment for safety, and the whole facility check. As a result of our effort, it was attained that when we compare the matured plant with the first unit, the construction cost is reduced by 30%, the construction period is shortened by 12 months, site manpower is decreased by 30%, and the plant had no sudden shutdowns even during the trial operation period. (author)

  6. Some aspects of nuclear power development in Czechoslovakia

    International Nuclear Information System (INIS)

    Simandl, S.; Stefec, V.

    1986-01-01

    Some technical and economic aspects of the development of nuclear power in Czechoslovakia are discussed. Specific conditions include the high population density of the territory and related factors as well as the shortage of raw materials for the construction of technological equipment and for the construction of buildings. It is stated that projects of future nuclear power plants should use reserves, such as are available in the standard project of a WWER-1000 nuclear power plant now being used in Temelin, as against foreign nuclear power plants. This mainly includes a bigger built-up area per installed megawatt of power and a greater number of personnel for operation and maintenance. Also discussed is the world-wide growth of capital costs, of construction time and of the number of workers needed for the construction of nuclear power plants. With the exception of the V-2 nuclear power plant the construction time of Czechoslovak nuclear power plants does not exceed world average. The maximum number of workers required for construction, however, compares unfavourably with advanced capitalist countries. Operating costs in Czechoslovakia are more favourable for nuclear power plants than for coal burning power plants and pumped-storage hydroelectric plants. (Z.M.)

  7. Vibration control and monitoring in nuclear power plants

    International Nuclear Information System (INIS)

    Theodor, P.

    1989-01-01

    Nuclear Power Plants are operated with a computer system support. The computer system for a nuclear power plant is designed to reliably monitor plant parameters and perform a series of operations and calculations designed to allow increased plant operation efficiency. Rotating machinery surveillance methods for the recognition of damage are particularly important in Nuclear Power Plants. Deviation of the vibration behavior from normal conditions is an indicator of the development of incipient faults and can be reliably recognized by the use of vibration monitoring systems. Machinery Condition Monitoring is defined as a method or methods of surveillance designed to recognize changes from a norm and is also a warning or it initiates an automatic shutdown when the changes exceed limiting values or safety limits. This paper reports that it is important to distinguish between surveillance and diagnostics. Whereas the former is necessary for protection, the latter is not generally required until it becomes necessary to identify the source of a known anomaly

  8. Aspects of nuclear safety at power plants and fuel cycle plants in the USSR

    International Nuclear Information System (INIS)

    Kozlov, N.I.; Efimov, E.; Dubovskij, B.G.; Dikarev, V.; Lyubchenko, V.; Kruglov, A.K.

    1977-01-01

    The paper discusses the problems of organizing inspection monitoring of power plants including the development of some regulations and norms and the interaction between the USSR State Nuclear Safety Organization, scientific and designing organizations and power plants. The principles of computer use to work out advice for operational staff and warning signals and commands for the reactor control and protection system are discussed. Some attention is turned to the importance of using high-speed computers to calculate prompt reactivity values and to determine impurity concentrations in the coolant and margins to permissible operational limits. In particular, reactimeters are considered as signal generators in monitor and protection systems. Some problems of nuclear safety inspection, the issue and inculcation of some regulations and operational documents on nuclear safety, and instrumentation of plants reprocessing or processing fuel elements are presented. Methods of determining the critical parameters of technological units are described, together with the fundamental principles of fuel cycle plant nuclear safety, providing margin coefficients, accounting for deviations from the normal operational process and other problems, as well as methods of keeping the restrictions on nuclear safety requirements at fuel cycle plants. (author)

  9. Development of Structural Health Monitoring System for pipes in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Eom, H. S.; Choi, Y. C.; Shin, S. H.; Youn, D. B.; Park, J. H.

    2010-01-01

    Structural health monitoring (SHM) has becoming an important issue in the maintenance of various structures such as large steel plates, vessels, and pipes in nuclear power plants. There are important factors to be considered in developing an SHM system. With consideration of these factors, we have developed a computerized multi-channel ultrasonic system that can handle array transducers and generate a high-power pulse for online SHM of the plates and pipes. The proposed system is compact but has all the necessary functions for SHM of important structure such as pipes and plates in a NPP

  10. IAEA activity on operator support systems in nuclear power plants

    International Nuclear Information System (INIS)

    Dounaev, V.; Fujita, Y.; Juslin, K.; Haugset, K.; Lux, I.; Naser, J.

    1994-01-01

    Various operator support systems for nuclear power plants are already operational or under development in the IAEA Member States. Operator support systems are based on intelligent data processing and, in addition to plant operation, they are also becoming more important for safety. A key feature of operator support systems is their availability to restructure data to increase its relevance for a given situation. This can improve the user's ability to identify plant mode, system state, and component state and to identify and diagnose faults. Operator support systems can also assist the user in planning and implementing corrective actions to improve the nuclear power plant's availability and safety. In September 1991, the IAEA Committee for Contractual Scientific Services approved the Co-ordinated Research Programme (CRP) on ''Operator Support Systems in Nuclear Power Plants'' in the framework of the Project ''Man-Machine Interface Studies''. The main objective of this programme is to provide guidance and technology transfer for the development and implementation of operator support systems. This includes the experience with human-machine interfaces and closely related issues such as instrumentation and control, the use of computers in nuclear power plants, and operator qualification. (author)

  11. Expert system for nuclear power plant feedwater system diagnosis

    International Nuclear Information System (INIS)

    Meguro, R.; Kinoshita, Y.; Sato, T.; Yokota, Y.; Yokota, M.

    1987-01-01

    The Expert System for Nuclear Power Plant Feedwater System Diagnosis has been developed to assist maintenance engineers in nuclear power plants. This system adopts the latest process computer TOSBAC G8050 and the expert system developing tool TDES2, and has a large scale knowledge base which consists of the expert knowledge and experience of engineers in many fields. The man-machine system, which has been developed exclusively for diagnosis, improves the man-machine interface and realizes the graphic displays of diagnostic process and path, stores diagnostic results and searches past reference

  12. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-02-01

    During the third quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. The annual maintenance outages of the Loviisa plant units were held during the report period. All events during this quarter are classified as Level hero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were below authorised limits. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  13. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-08-01

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

  14. Public perception toward information and knowledge of nuclear power plant development; A Malaysian case study

    Science.gov (United States)

    Misnon, Fauzan Amin; Rahman, Irman Abd.; Hu, Yeoh Siong; Yasir, Muhamad Samudi

    2018-04-01

    Knowledge has been known as a key element in developing support and perception by the public towards any new policy by the government, including the development of nuclear energy. The success of the policy is mainly dependent on public support which is related to the perception cultivated by the knowledge that is already held by the people. A public survey was conducted between 14 March 2016 to 10 May 2016 focusing on the Malaysian public acceptance and perception towards the implementation of nuclear energy in Malaysia (n=1438). This research was aimed on the research question which is `Does the level of general knowledge and education regarding nuclear energy in Malaysia influence the acceptance and support of the people to develop nuclear technology?'. These finding suggest that open discourse is a must even at the initial stages of developing a Nuclear Power Plant (NPP) program, which will touch on a few points that will assist to society's knowledge and understanding towards nuclear energy from the aspects of management, safety, radioactive waste, impact on economic competitiveness as well as the benefits and risks regarding the development of NPP. By increasing the knowledge regarding nuclear power and radioactive waste, perception towards the pros of NPP as well as the conviction towards its safety can be increased. It is suggested for the parties involved to use the latest approach of information technology as a way to provide the most effective medium of information dissemination to the public.

  15. TOSHIBA CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    Machiba, Hiroshi; Sasaki, Norio

    1990-01-01

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

  16. Cost-effective instrumentation and control upgrades for commercial nuclear power plants surety principles developed at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Rochau, G.E.; Dalton, L.J.

    1998-01-01

    Many nuclear power plants use instrument and control systems based on analog electronics. The state of the art in process control and instrumentation has advanced to use digital electronics and incorporate advanced technology. This technology includes: distributed microprocessors, fiber optics, intelligent systems (neutral networks), and advanced displays. The technology is used to optimize processes and enhance the man-machine interface while maintaining control and safety of the processes. Nuclear power plant operators have been hesitant to install this technology because of the cost and uncertainty in the regulatory process. This technology can be directly applied in an operating nuclear power plant provided a surety principle-based 'administrator' hardware system is included in parallel with the upgrade. Sandia National Laboratories has developed a rigorous approach to High Consequence System Surety (HCSS). This approach addresses the key issues of safety, security, and control while satisfying requirements for reliability and quality. We believe that HCSS principles can be applied to nuclear power plants in a manner that allows the off-the-shelf use of process control instrumentation while maintaining a high level of safety and enhancing the plant performance. We propose that an HCSS Administrator be constructed as a standardized approach to address regulatory issues. Such an administrator would allow a plant control system to be constructed with commercially available, state-to-the-art equipment and be customized to the needs of the individual plant operator. (author)

  17. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  18. 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

  19. Study on optimization of normal plant outage work plan for nuclear power plants

    International Nuclear Information System (INIS)

    Aoki, Takayuki; Kodama, Noriko; Takase, Kentaro; Miya, Kenzo

    2011-01-01

    This paper discusses maintenance optimization in maintenance implementation stage following maintenance planning stage in nuclear power plants and proposes a methodology to get an optimum maintenance work plan. As a result of consideration, the followings were obtained. (1) The quantitative evaluation methodology for optimizing maintenance work plan in nuclear power plants was developed. (2) Utilizing the above methodology, a simulation analysis of maintenance work planning for BWR's PLR and RHR systems in a normal plant outage was performed. Maintenance cost calculation in several cases was carried out on the condition of smoothening man loading over the plant outage schedule as much as possible. (3) As a result of the simulation, the economical work plans having a flat man loading over the plant outage schedule were obtained. (author)

  20. Human factors engineering plan for reviewing nuclear plant modernization programs

    International Nuclear Information System (INIS)

    O'Hara, John; Higgins, James

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation

  1. Human factors engineering plan for reviewing nuclear plant modernization programs

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

  2. Current status and future prospects of Korean standardized nuclear power plant design

    International Nuclear Information System (INIS)

    Rieh, C.-H.; Park, S.-K.; Lee, B.-R.

    1992-01-01

    The authors reviewed a brief history of Korean nuclear industry since the first Kori-1 plant operation in 1978 with special emphasis on the NSSS and BOP design and engineering, and the design approaches for nuclear power plants in the future. Continued effort to enhance plant economy and operational safety has been made by increasing plant size, and improving safety features, systems and component reliability in various design aspects. Korean nuclear industry is now trying to be one of the major contributors to the world nuclear field in sharing nuclear technology gained from past experience and developed through internation technical cooperation programs

  3. Selection of Possible Candidate Area for Nuclear Power Plant in Johor, Malaysia

    International Nuclear Information System (INIS)

    Nor Afifah Basri; Ahmad Termizi Ramli

    2012-01-01

    Nuclear power is considered as one of the best option for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation, commissioning the first nuclear power plant needs tremendous effort in various aspects. Site selection is one of important step in nuclear power plant commissioning process. This paper proposes candidate sites for nuclear power plant in Mersing, Kota Tinggi, Muar and Batu Pahat district in Johor, Malaysia. The candidate selection process uses the IAEA document and AELB guideline as main reference, supported by site selection procedure by various countries. MapInfo Professional software was used to simulate the selection process for candidate areas for the nuclear power plant. This paper concluded that Tenggaroh and Jemaluang area are the most suitable area for nuclear power plant facilities in Johor, Malaysia. (Author)

  4. Problems associated with the export of nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    Full text: Recent forecasts indicate that by the year 2000 there will be more than 1000 nuclear power plants operating in 50 countries and with several countries expecting to derive one-half or more of their electric generation from nuclear power plants At present only six countries are exporters of nuclear power systems, three more currently supply their own domestic markets, while the remainder are importers. It is expected that most of the importers will continue to depend to varying degrees on foreign supply, at least in the near future. If nuclear power is to offer an important benefit to the world, the achievement of this benefit will require co-operation between the supplying and receiving nations in overcoming problems which might inhibit the full development of this energy source. In addition to ensuring safety and reliability, special problem areas include financing, skilled manpower needs, adequate local industrial and engineering infrastructure, access to advanced technology, and an assured supply of nuclear fuel. The symposium had special emphasis on the problems facing many of the developing countries in the initial stages of nuclear power programmes, and was divided into three major topics nuclear safety, domestic contributions, and international aspects In the safety area, emphasis was given to the special considerations that may exist for countries that import nuclear plants. These special considerations can be due to some non-standard features of the exported reactor such as lower power ratings, dissimilar site characteristics that can effect the design, and the evolution and changes in design and safety requirements during construction. This can be complicated by differences in safety philosophy and codified standards of the various suppliers and unique construction problems in the less developed countries. Thus, the ability of the importing country to carry out the regulatory and safety function is obviously important. A number of presentations

  5. 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)

  6. Analysis on capability of load following for nuclear power plants abroad and its enlightenment

    Science.gov (United States)

    Zheng, Kuan; Zhang, Fu-qiang; Deng, Ting-ting; Zhang, Jin-fang; Hao, Weihua

    2017-01-01

    With the acceleration adjustment of China’s energy structure, the development of nuclear power plants in China has been going back to the fast track. While as the trend of slowing electric power demand is now unmistakable, it enforces the power system to face much greater pressure in some coastal zones where the nuclear power plants are of a comparative big proportion, such as Fujian province and Liaoning province. In this paper, the capability of load following of nuclear power plants of some developed countries with high proportion of nuclear power generation such as France, US and Japan are analysed, also from the aspects including the safety, the economy and their practical operation experience is studied. The feasibility of nuclear power plants to participate in the peak regulation of system is also studied and summarized. The results of this paper could be of good reference value for the China’s nuclear power plants to participate in system load following, and also of great significance for the development of the nuclear power plants in China.

  7. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    Neri, Emilio; French, Amanda; Urso, Maria Elena; Deffrennes, Marc; Rothwell, Geoffrey; ); Rehak, Ivan; Weber, Inge; ); Carroll, Simon; Daniska, Vladislav

    2016-01-01

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

  8. Coupling technology for dual-purpose nuclear-desalting plants

    International Nuclear Information System (INIS)

    Jones, J.E. Jr.; Anderson, T.D.; Reed, S.A.

    1976-11-01

    Although the basic technology for the various components of nuclear dual-purpose plants is reasonably well developed, the techniques of coupling the elements together to form a reliable, economical system that will satisfy the diverse operating requirements are not well established. The purpose of the study reported is to examine the technical, economic, and safety considerations in coupling nuclear power plants with distillation units to form a dual-purpose power and water distillation plant. The basic coupling arrangement required to provide a large-scale dual-purpose water plant is to supply steam to the water plant from the exhaust of a back-pressure turbine. The principal component at the interface that may require major research and development is the back-pressure turbine. To satisfy the operational requirements, two major auxiliary systems will be needed. These are: (1) a prime-steam bypass system, and (2) auxiliary condensers. These systems will provide a degree of independence between water and power production and can be justified economically

  9. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  10. Development of a new generation of ion exchange resin for nuclear and fossil power plant

    International Nuclear Information System (INIS)

    Tsuzuki, Shintaro; Tagawa, Hidemi; Yamashita, Futoshi; Okamoto, Ryutaro

    2008-01-01

    It is required to maintain water quality supplied to steam generator to the water designed based on its water chemistry in order to keep the sound operation of nuclear power plants or fossil power plants. Condensate Polishing Plant (CPP) is installed for removing ions in the water which uses a mixed bed of cation exchange resin and anion exchange resin. We have developed new generation of CPP resin. The product is a unique combination of super high exchange capacity cation exchange resin and high fouling resistant anion exchange resin. The CPP resin has been used in many power plants. Amberjet 1006 was developed as a cation exchange resin with high oxidative stability, high operational capacity and New IRA900CP was developed as an anion exchange resin with high fouling resistant to leachables released out of cation exchange resin by oxidative degradation over the service period. The novel CPP resin was first used in 2000 and has now been used in many power plants in Japan. The CPP resin has been giving excellent quality of water. (author)

  11. PWR reactors for BBR nuclear power plants

    International Nuclear Information System (INIS)

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

  12. VISIT - Virtual visits to nuclear power plants

    International Nuclear Information System (INIS)

    Mollaret, Jean-Christophe

    2001-01-01

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

  13. Management of delayed nuclear power plant projects

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    According to the available information at the IAEA PRIS (Power Reactor Information System) at the end of 1998 there were more than 40 nuclear power plant projects with delays of five or more years with respect to the originally scheduled commercial operation. The degree of conformance with original construction schedules showed large variations due to several issues, including financial, economic and public opinion factors. Taking into account the number of projects with several years delay in their original schedules, it was considered useful to identify the subject areas where exchange of experience among Member States would be mutually beneficial in identification of problems and development of guidance for successful management of the completion of these delayed projects. A joint programme of the IAEA Departments of Nuclear Energy (Nuclear Power Engineering Section) and Technical Co-operation (Europe Section, with additional support from the Latin America and West Asia Sections) was set up during the period 1997-1998. The specific aim of the programme was to provide assistance in the management of delayed nuclear power plants regarding measures to maintain readiness for resuming the project implementation schedule when the conditions permit. The integration of IAEA interdepartmental resources enabled the participation of 53 experts from 14 Member States resulting in a wider exchange of experience and dissemination of guidance. Under the framework of the joint programme, senior managers directly responsible for delayed nuclear power plant projects identified several issues or problem areas that needed to be addressed and guidance on management be provided. A work plan for the development of several working documents, addressing the different issues, was established. Subsequently these documents were merged into a single one to produce the present publication. This publication provides information and practical examples on necessary management actions to preserve

  14. Management of delayed nuclear power plant projects

    International Nuclear Information System (INIS)

    1999-09-01

    According to the available information at the IAEA PRIS (Power Reactor Information System) at the end of 1998 there were more than 40 nuclear power plant projects with delays of five or more years with respect to the originally scheduled commercial operation. The degree of conformance with original construction schedules showed large variations due to several issues, including financial, economic and public opinion factors. Taking into account the number of projects with several years delay in their original schedules, it was considered useful to identify the subject areas where exchange of experience among Member States would be mutually beneficial in identification of problems and development of guidance for successful management of the completion of these delayed projects. A joint programme of the IAEA Departments of Nuclear Energy (Nuclear Power Engineering Section) and Technical Co-operation (Europe Section, with additional support from the Latin America and West Asia Sections) was set up during the period 1997-1998. The specific aim of the programme was to provide assistance in the management of delayed nuclear power plants regarding measures to maintain readiness for resuming the project implementation schedule when the conditions permit. The integration of IAEA interdepartmental resources enabled the participation of 53 experts from 14 Member States resulting in a wider exchange of experience and dissemination of guidance. Under the framework of the joint programme, senior managers directly responsible for delayed nuclear power plant projects identified several issues or problem areas that needed to be addressed and guidance on management be provided. A work plan for the development of several working documents, addressing the different issues, was established. Subsequently these documents were merged into a single one to produce the present publication. This publication provides information and practical examples on necessary management actions to preserve

  15. Effects of nuclear electromagnetic pulse (EMP) on nuclear power plants

    International Nuclear Information System (INIS)

    Barnes, P.R.; Manweiler, R.W.; Davis, R.R.

    1977-09-01

    The electromagnetic pulse (EMP) from a high-altitude nuclear detonation consists of a transient pulse of high intensity electromagnetic fields. These intense fields induce current and voltage transients in electrical conductors. Although most nuclear power plant cables are not directly exposed to these fields, the attenuated EMP fields that propagate into the plant will couple some EMP energy to these cables. The report predicts the probable effects of the EMP transients that could be induced in critical circuits of safety-related systems. It was found that the most likely consequence of EMP for nuclear plants is an unscheduled shutdown. EMP could prolong the shutdown period by the unnecessary actuation of certain safety systems. In general, EMP could be a nuisance to nuclear power plants, but it is not considered a serious threat to plant safety

  16. The IAEA's activities in safeguarding nuclear materials and in developing internationally acceptable safety codes and guides for nuclear power plants

    International Nuclear Information System (INIS)

    Rometsch, Rudolf; Specter, Herschel

    1977-01-01

    Promoting the peaceful use of nuclear energy and aiming at the international sharing of its benefits are objectives that guide the activities of the Agency. But this promotional work is carried out on condition that security and safety are provided for. All Agency assistance involving nuclear facilities will be subjected to standards of safety or other standards, which are proposed by a State the Agency finds essentially equivalent. Safeguards are always applied on the basis of agreement. States party to NPT are obligated to negotiate and conclude with the Agency agreements which cover all their peaceful nuclear activities. Safeguards agreements concluded outside NPT are applied to specific supplies of facilities, equipment and material. To assist countries in laying down their nuclear safety regulations the Agency's program for the developing of codesof practice and safety guides for nuclear power plants draws up guidelines for governmental organizations, siting, design, operation and quality assurance. Codes are the fundamental documents laying down the objectives of each field of nuclear safety

  17. Construction of overseas nuclear power plants for first time by Japanese industry

    International Nuclear Information System (INIS)

    Maruyama, Tohru; Naruse, Yoshihiro; Yabuta, Hitoshi

    2010-01-01

    In response to the worldwide demand for stable energy supplies and the reduction of greenhouse gas emissions, nuclear power plant construction projects have been expanding on a global scale. Even in the United States, where no nuclear power plants have been constructed over the past 30 years, there are plans for the construction of more than 30 plants. Toshiba has been awarded a contract for a nuclear power plant construction project in the U.S., the first case of overseas nuclear power plant construction by Japanese industry. Toshiba America Nuclear Energy Corporation (TANE), the first U.S. subsidiary in our nuclear business, located in Charlotte, North Carolina, is engaged in this globally prominent project, applying various technologies and know-how that we have cultivated over many years of experience in developing and constructing nuclear power plants in Japan and adapting them to U.S. business practices, laws, and regulations. (author)

  18. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-09-01

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

  19. Transportable nuclear power plant TEC-M with two reactor plants of improved safety

    International Nuclear Information System (INIS)

    Ogloblin, B.G.; Sazonov, A.G.; Svishchev, A.M.; Gromov, B.F.; Zelensky, V.N.; Komkova, O.I.; Sidorov, V.I.; Tolstopyatov, V.P.; Toshinsky, G.I.

    1993-01-01

    Liquid metals are the best to meet the requirements of inherently safety nuclear power plants among the coolants used. A great experience has been gained in lead coolant power plant development and operation as applied to transportable power set-ups. Low chemical activity of this coolant with respect to air-water interaction is a determining factor for this coolant. The transportable nuclear power plant is described. It is intended to generate electric power for populated areas placed a long distance from the main electric power supply sources where it is difficult or not economical to deliver the conventional types of fuel. There are several remote areas in Siberia, Kamchatka in need of this type of power plant

  20. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-12-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO 1 and II were in operation for almost the whole second quarter of 1991. The load factor average was 87.4 %. In consequence of a fire, which broke out in the switchgear building, connections to both external grids were lost and TVO II relied on power supplied by four back-up diesels for 7.5 hrs. The event is classified as Level 2 on the International Nuclear Event Scale. The process of examining the non-leaking fuel bundles removed from the Loviisa nuclear reactors has continued. The examinations have revealed, so far, that the uppermost spacing lattices of the bundles exhibit deformations similar to those detected in the leaking fuel bundles removed from the reactors. This event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale) on the Scale. The Finnish Centre for Radiation and Nuclear Safety has assessed the safety of the Loviisa and Olkiluoto nuclear power plants based on the new regulations issued on 14.2.1991 by the Council of State. The safety regulations are much more stringent than those in force when the Loviisa and Olkiluoto nuclear power plants were built. The assessment indicated that the TVO nuclear power plant meets these safety regulations. The Loviisa nuclear power plant meets the requirements with the exception of certain requirements related to the ensuring of safety functions and provision for accidents. At the Loviisa nuclear power plant there are several projects under consideration to enhance safety