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Sample records for reliable treatment plant

  1. Analysis and assessment of water treatment plant reliability

    Directory of Open Access Journals (Sweden)

    Szpak Dawid

    2017-03-01

    Full Text Available The subject of the publication is the analysis and assessment of the reliability of the surface water treatment plant (WTP. In the study the one parameter method of reliability assessment was used. Based on the flow sheet derived from the water company the reliability scheme of the analysed WTP was prepared. On the basis of the daily WTP work report the availability index Kg for the individual elements included in the WTP, was determined. Then, based on the developed reliability scheme showing the interrelationships between elements, the availability index Kg for the whole WTP was determined. The obtained value of the availability index Kg was compared with the criteria values.

  2. Collection and treatment of reliability data for nuclear plants

    International Nuclear Information System (INIS)

    McHugh, B.

    1973-09-01

    This paper describes some of the results achieved with the Argus data bank at the Institution of Thermal Power Engineering at the Chalmers University of Technology. This data bank, or rather data collection system, has been established to cover nuclear activities the world over. The system comprises in essence a number of data files. The prime files are those containing the basic data on the various plants - plant size and type, country and NSSS supplier and an indication of plantstatus. Further files contain plant design data and parameters and all available information on construction as commissioning timetables. To cover the operation of plant two files have been established. One file, which is updated on a monthly basis, contains power production statistics. The other file contains failure data. In this file are recorded the time and duration of plant shutdown together with the primary reason (s) for this. (M.S.)

  3. Problems of reliability and economy work of thermal power plants water treatment based on baromembrane technologies

    Science.gov (United States)

    Chichirova, N. D.; Chichirov, A. A.; Saitov, S. R.

    2017-11-01

    The introduction of baromembrane water treatment technologies for water desalination at Russian thermal power plants was beganed more than 25 years ago. These technologies have demonstrated their definite advantage over the traditional technologies of additional water treatment for steam boilers. However, there are problems associated with the reliability and economy of their work. The first problem is a large volume of waste water (up to 60% of the initial water). The second problem a expensive and unique chemical reagents complex (biocides, antiscalants, washing compositions) is required for units stable and troublefree operation. Each manufacturer develops his own chemical composition for a certain membrane type. This leads to a significant increase in reagents cost, as well as creates dependence of the technology consumer on the certain supplier. The third problem is that the reliability of the baromembrane units depends directly on the water preliminary treatment. The popular pre-cleaning technology with coagulation of aluminum oxychloride proves to be unacceptable during seasonal changes in the quality of the source water at a number of stations. As a result, pollution, poisoning and lesion of the membrane structure or deterioration of their mechanical properties are observed. The report presents ways to solve these problems.

  4. Of plants and reliability

    International Nuclear Information System (INIS)

    Schneider Horst

    2009-01-01

    Behind the political statements made about the transformer event at the Kruemmel nuclear power station (KKK) in the summer of 2009 there are fundamental issues of atomic law. Pursuant to Articles 20 and 28 of its Basic Law, Germany is a state in which the rule of law applies. Consequently, the aspects of atomic law associated with the incident merit a closer look, all the more so as the items concerned have been known for many years. Important aspects in the debate about the Kruemmel nuclear power plant are the fact that the transformer is considered part of the nuclear power station under atomic law and thus a ''plant'' subject to surveillance by the nuclear regulatory agencies, on the one hand, and the reliability under atomic law of the operator and the executive personnel responsible, on the other hand. Both ''plant'' and ''reliability'' are terms focusing on nuclear safety. Hence the question to what extent safety was affected in the Kruemmel incident. The classification of the event as 0 = no or only a very slight safety impact on the INES scale (INES = International Nuclear Event Scale) should not be used to put aside the safety issue once and for all. Points of fact and their technical significance must be considered prior to any legal assessment. Legal assessments and regulations are associated with facts and circumstances. Any legal examination is based on the facts as determined and elucidated. Any other procedure would be tantamount to an inadmissible legal advance conviction. Now, what is the position of political statements, i.e. political assessments and political responsibility? If everything is done the correct way, they come at the end, after exploration of the facts and evaluation under applicable law. Sometimes things are handled differently, with consequences which are not very helpful. In the light of the provisions about the rule of law as laid down in the Basic Law, the new federal government should be made to observe the proper sequence of

  5. Reliability Characteristics of Power Plants

    Directory of Open Access Journals (Sweden)

    Zbynek Martinek

    2017-01-01

    Full Text Available This paper describes the phenomenon of reliability of power plants. It gives an explanation of the terms connected with this topic as their proper understanding is important for understanding the relations and equations which model the possible real situations. The reliability phenomenon is analysed using both the exponential distribution and the Weibull distribution. The results of our analysis are specific equations giving information about the characteristics of the power plants, the mean time of operations and the probability of failure-free operation. Equations solved for the Weibull distribution respect the failures as well as the actual operating hours. Thanks to our results, we are able to create a model of dynamic reliability for prediction of future states. It can be useful for improving the current situation of the unit as well as for creating the optimal plan of maintenance and thus have an impact on the overall economics of the operation of these power plants.

  6. Reliability analysis techniques in power plant design

    International Nuclear Information System (INIS)

    Chang, N.E.

    1981-01-01

    An overview of reliability analysis techniques is presented as applied to power plant design. The key terms, power plant performance, reliability, availability and maintainability are defined. Reliability modeling, methods of analysis and component reliability data are briefly reviewed. Application of reliability analysis techniques from a design engineering approach to improving power plant productivity is discussed. (author)

  7. Análise da confiabilidade de estações de tratamento de esgotos Reliability analysis of wastewater treatment plants

    Directory of Open Access Journals (Sweden)

    Sílvia Corrêa Oliveira

    2007-12-01

    Full Text Available Este artigo apresenta uma análise da confiabilidade de 166 estações de tratamento de esgotos em operação no Brasil, considerando seis processos de tratamento mais usualmente adotados. Foi utilizada uma metodologia desenvolvida por Niku et al (1979 para determinação de coeficientes de confiabilidade (CDC, considerando o alcance a metas de lançamento para concentrações efluentes de DBO, DQO, SST, NT, PT e CF. A partir dos CDC obtidos, foram calculadas as concentrações de projeto necessárias para o cumprimento das metas de lançamento e os percentuais de atendimento esperados. Os resultados mostraram que poucas ETEs, nas condições de operação observadas, conseguiriam apresentar desempenhos confiáveis, em termos de cumprimento dos padrões. Para todos os constituintes e sistemas de tratamento, a variabilidade da qualidade do efluente foi muito grande.This article presents a reliability analysis of 166 full-scale wastewater treatment plants operating in Brazil, comprising six different treatment processes usually adopted. A methodology developed by Niku et al (1979 is used for the determination of the coefficients of reliability (COR, in terms of the compliance of effluent BOD, COD, TSS, TN, TP and FC to discharge standards. The design concentrations necessary to meet the prevailing discharge standards and the expected compliance percentages have been calculated from the coefficients of reliability obtained. The results showed that few plants, under the observed operating conditions, would be able to present reliable performances in terms of compliance with the analyzed standards. For all constituents and systems, the variability of the effluent quality was very large.

  8. Increase of hydroelectric power plant operation reliability

    International Nuclear Information System (INIS)

    Koshumbaev, M.B.

    2006-01-01

    The new design of the turbine of hydroelectric power plant (HPP) is executed in the form of a pipe with plates. Proposed solution allows increasing the hydroelectric power plant capacity at existing head and water flow. At that time the HPP turbine reliability is increase, its operation performances are improving. Design efficiency is effective mostly for small-scale and micro-HPP due to reliable operation, low-end technology, and harmless ecological application. (author)

  9. Reliability of PWR type nuclear power plants

    International Nuclear Information System (INIS)

    Ribeiro, A.A.T.; Muniz, A.A.

    1978-12-01

    Results of the analysis of factors influencing the reliability of international nuclear power plants of the PWR type are presented. The reliability factor is estimated and the probability of its having lower values than a certain specified value is discussed. (Author) [pt

  10. Nuclear power plant reliability database management

    International Nuclear Information System (INIS)

    Meslin, Th.; Aufort, P.

    1996-04-01

    In the framework of the development of a probabilistic safety project on site (notion of living PSA), Saint Laurent des Eaux NPP implements a specific EDF reliability database. The main goals of this project at Saint Laurent des Eaux are: to expand risk analysis and to constitute an effective local basis of thinking about operating safety by requiring the participation of all departments of a power plant: analysis of all potential operating transients, unavailability consequences... that means to go further than a simple culture of applying operating rules; to involve nuclear power plant operators in experience feedback and its analysis, especially by following up behaviour of components and of safety functions; to allow plant safety managers to outline their decisions facing safety authorities for notwithstanding, preventive maintenance programme, operating incident evaluation. To hit these goals requires feedback data, tools, techniques and development of skills. The first step is to obtain specific reliability data on the site. Raw data come from plant maintenance management system which processes all maintenance activities and keeps in memory all the records of component failures and maintenance activities. Plant specific reliability data are estimated with a Bayesian model which combines these validated raw data with corporate generic data. This approach allow to provide reliability data for main components modelled in PSA, to check the consistency of the maintenance program (RCM), to verify hypothesis made at the design about component reliability. A number of studies, related to components reliability as well as decision making process of specific incident risk evaluation have been carried out. This paper provides also an overview of the process management set up on site from raw database to specific reliability database in compliance with established corporate objectives. (authors). 4 figs

  11. Nuclear power plant reliability database management

    Energy Technology Data Exchange (ETDEWEB)

    Meslin, Th [Electricite de France (EDF), 41 - Saint-Laurent-des-Eaux (France); Aufort, P

    1996-04-01

    In the framework of the development of a probabilistic safety project on site (notion of living PSA), Saint Laurent des Eaux NPP implements a specific EDF reliability database. The main goals of this project at Saint Laurent des Eaux are: to expand risk analysis and to constitute an effective local basis of thinking about operating safety by requiring the participation of all departments of a power plant: analysis of all potential operating transients, unavailability consequences... that means to go further than a simple culture of applying operating rules; to involve nuclear power plant operators in experience feedback and its analysis, especially by following up behaviour of components and of safety functions; to allow plant safety managers to outline their decisions facing safety authorities for notwithstanding, preventive maintenance programme, operating incident evaluation. To hit these goals requires feedback data, tools, techniques and development of skills. The first step is to obtain specific reliability data on the site. Raw data come from plant maintenance management system which processes all maintenance activities and keeps in memory all the records of component failures and maintenance activities. Plant specific reliability data are estimated with a Bayesian model which combines these validated raw data with corporate generic data. This approach allow to provide reliability data for main components modelled in PSA, to check the consistency of the maintenance program (RCM), to verify hypothesis made at the design about component reliability. A number of studies, related to components reliability as well as decision making process of specific incident risk evaluation have been carried out. This paper provides also an overview of the process management set up on site from raw database to specific reliability database in compliance with established corporate objectives. (authors). 4 figs.

  12. Structural reliability of atomic power plant

    International Nuclear Information System (INIS)

    Klemin, A.I.; Polyakov, E.F.

    1980-01-01

    In 1978 the first specialized technical manual ''Technique of Calculating the Structural Reliability of an Atomic Power Plant and Its Systems in the Design Stage'' was developed. The present article contains information about the main characteristics and capabilities of the manual. The manual gives recommendations concerning the calculations of the reliability of such specific systems as the reactor control and safety system, the system of instrumentation and automatic control, and safety systems. 2 refs

  13. Reliability of nuclear power plants and equipment

    International Nuclear Information System (INIS)

    1985-01-01

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

  14. Improvement of plant reliability in PT. Badak LNG plant

    International Nuclear Information System (INIS)

    Achmad, S.; Somantri, A.

    1997-01-01

    PT. Badak's LNG sales commitment has been steadily increasing, therefore, there has been more emphasis to improve and maintain the LNG plant reliability. From plant operation historical records, Badak LNG plant experienced a high number of LNG process train trips and down time for 1977 through 1988. The highest annual number of LNG plant trips (50 times) occurred in 1983 and the longest LNG process train down time (1259 train-hours) occurred in 1988. Since 1989, PT. Badak has been able to reduce the number of LNG process train trips and down time significantly. In 1994 the number of LNG process train trips and was 18 times and the longest LNG process train down time was 377 train-hours. This plant reliability improvement was achieved by implementing plant reliability improvement programs beginning with the design of the new facilities and continuing with the maintenance and modification of the existing facilities. To improve reliability of the existing facilities, PT. Badak has been implementing comprehensive maintenance programs, to reduce the frequency and down time of the plant, such as Preventive and Predictive Maintenance as well as procurement material improvement since PT. Badak location is in a remote area. By implementing the comprehensive reliability maintenance, PT. Badak has been able to reduce the LNG process train trips to 18 and down time to 337 train hours in 1994 with the subsequent maintenance cost reduction. The average PT. Badak plant availability from 1985 to 1995 is 94.59%. New facilities were designed according to the established PT. Badak design philosophy, master plan and specification. Design of new facilities was modified to avoid certain problems from past experience. (au)

  15. Reliability allocation in nuclear power plants

    International Nuclear Information System (INIS)

    Bari, R.A.; Cho, N.Z.; Papazoglou, I.A.

    1985-01-01

    The technical feasibility of allocating reliability and risk to reactor systems, subsystems, components, operations, and structures is investigated. A methodology is discussed which identifies top level risk indices as objective functions and plant-specific performance variables as decision variables. These are related by a risk model which includes cost as a top level risk index. A multiobjective optimization procedure is used to find non-inferior solutions in terms of the objective functions and the decision variables. The approach is illustrated for a boiling water reactor plant. The use of the methodology for both operating reactors and for advanced designs is briefly discussed. 16 refs., 1 fig

  16. Using wind plant data to increase reliability.

    Energy Technology Data Exchange (ETDEWEB)

    Peters, Valerie A. (Sandia National Laboratories, Livermore, CA); Ogilvie, Alistair B.; McKenney, Bridget L.

    2011-01-01

    Operators interested in improving reliability should begin with a focus on the performance of the wind plant as a whole. To then understand the factors which drive individual turbine performance, which together comprise the plant performance, it is necessary to track a number of key indicators. Analysis of these key indicators can reveal the type, frequency, and cause of failures and will also identify their contributions to overall plant performance. The ideal approach to using data to drive good decisions includes first determining which critical decisions can be based on data. When those required decisions are understood, then the analysis required to inform those decisions can be identified, and finally the data to be collected in support of those analyses can be determined. Once equipped with high-quality data and analysis capabilities, the key steps to data-based decision making for reliability improvements are to isolate possible improvements, select the improvements with largest return on investment (ROI), implement the selected improvements, and finally to track their impact.

  17. Reliability of microcircuits in nuclear power plants

    International Nuclear Information System (INIS)

    Cross, P.M.; Taplin, R.C.

    1986-06-01

    The reliability problems associated with modernizing control systems in nuclear power plants, particularly by using new technology microcircuits, are discussed and twelve problem areas identified. These are: new technology introduction; variability in manufacture; derating necessities; distributed systems; use of redundancy; electrostatic discharge damage; electromagnetic interference; nuclear radiation; thermal effects; contamination, including humidity; mechanical effects, including vibration; and testing. Recommendations for the AECB are given in each area. Guidelines are given for the design, procurement, installation, operation and maintenance stages of use. Recommendations for further work are given

  18. 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)

  19. Reliable control system for nuclear power plant

    International Nuclear Information System (INIS)

    Okamoto, Tetsuo; Miyazaki, Shiro

    1980-01-01

    The System 1100 for nuclear power plants is the measuring and control system which utilizes the features of the System 1100 for electric power market in addition to the results of nuclear instrumentation with EBS-ZN series, and it has the following features. The maintenance and inspection in operation are easy. The construction of control loops is made flexibly by the combination of modules. The construction of multi-variable control system using mainly feed forward control is easy. Such functions as the automatic switching of control modes can be included. The switching of manual and automatic operations is easy, and if some trouble occurred in a module, the manual operation can be made. The aseismatic ability is improved by rigid structure cubicles. Nonflammable materials are used for wires, multi-core cables, paints and printed boards. The anti-noise characteristics are improved, and the reliability is high. The policy of developing the System 1100 for nuclear power plants, the type approval tests on modules and units and the type approval test on the system are described. The items of the system type approval test were standard performance test, earthquake test, noise isolation test, temperature and humidity test, and drift test. The aseismatic cubicle showed good endurance in its vibration test. (Kako, I.)

  20. Reliability Analysis Techniques for Communication Networks in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lim, T. J.; Jang, S. C.; Kang, H. G.; Kim, M. C.; Eom, H. S.; Lee, H. J.

    2006-09-01

    The objectives of this project is to investigate and study existing reliability analysis techniques for communication networks in order to develop reliability analysis models for nuclear power plant's safety-critical networks. It is necessary to make a comprehensive survey of current methodologies for communication network reliability. Major outputs of this study are design characteristics of safety-critical communication networks, efficient algorithms for quantifying reliability of communication networks, and preliminary models for assessing reliability of safety-critical communication networks

  1. Problem of nuclear power plant reliability

    International Nuclear Information System (INIS)

    Popyrin, L.S.; Nefedov, Yu.V.

    1989-01-01

    The problem of substantiation of rational and methods of ensurance of NPP reliability at the stage of its designing has been studied. It is shown that the optimal level of NPP reliability is determined by coordinating solution of the proiblems for optimization of reliability of power industry, heat and power supply and nuclear power generation systems comprising NPP, and problems of reliability optimization of NPP proper, as a complex engineering system. The conclusion is made that the greatest attention should be paid to the development of mathematical models of reliability, taking into account different methods of equipment redundancy, as well as dependence of failures on barious factors, improvement of NPP reliability indices, development of data base, working out of the complec of consistent standards of reliability. 230 refs.; 2 figs.; 1 tab

  2. 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

  3. Notes on human factors problems in process plant reliability and safety prediction

    International Nuclear Information System (INIS)

    Rasmussen, J.; Taylor, J.R.

    1976-09-01

    The basis for plant operator reliability evaluation is described. Principles for plant design, necessary to permit reliability evaluation, are outlined. Five approaches to the plant operator reliability problem are described. Case stories, illustrating operator reliability problems, are given. (author)

  4. Weibull distribution in reliability data analysis in nuclear power plant

    International Nuclear Information System (INIS)

    Ma Yingfei; Zhang Zhijian; Zhang Min; Zheng Gangyang

    2015-01-01

    Reliability is an important issue affecting each stage of the life cycle ranging from birth to death of a product or a system. The reliability engineering includes the equipment failure data processing, quantitative assessment of system reliability and maintenance, etc. Reliability data refers to the variety of data that describe the reliability of system or component during its operation. These data may be in the form of numbers, graphics, symbols, texts and curves. Quantitative reliability assessment is the task of the reliability data analysis. It provides the information related to preventing, detect, and correct the defects of the reliability design. Reliability data analysis under proceed with the various stages of product life cycle and reliability activities. Reliability data of Systems Structures and Components (SSCs) in Nuclear Power Plants is the key factor of probabilistic safety assessment (PSA); reliability centered maintenance and life cycle management. The Weibull distribution is widely used in reliability engineering, failure analysis, industrial engineering to represent manufacturing and delivery times. It is commonly used to model time to fail, time to repair and material strength. In this paper, an improved Weibull distribution is introduced to analyze the reliability data of the SSCs in Nuclear Power Plants. An example is given in the paper to present the result of the new method. The Weibull distribution of mechanical equipment for reliability data fitting ability is very strong in nuclear power plant. It's a widely used mathematical model for reliability analysis. The current commonly used methods are two-parameter and three-parameter Weibull distribution. Through comparison and analysis, the three-parameter Weibull distribution fits the data better. It can reflect the reliability characteristics of the equipment and it is more realistic to the actual situation. (author)

  5. Power plant reliability calculation with Markov chain models

    International Nuclear Information System (INIS)

    Senegacnik, A.; Tuma, M.

    1998-01-01

    In the paper power plant operation is modelled using continuous time Markov chains with discrete state space. The model is used to compute the power plant reliability and the importance and influence of individual states, as well as the transition probabilities between states. For comparison the model is fitted to data for coal and nuclear power plants recorded over several years. (orig.) [de

  6. Process plant equipment operation, control, and reliability

    CERN Document Server

    Holloway, Michael D; Onyewuenyi, Oliver A

    2012-01-01

    "Process Plant Equipment Book is another great publication from Wiley as a reference book for final year students as well as those who will work or are working in chemical production plants and refinery…" -Associate Prof. Dr. Ramli Mat, Deputy Dean (Academic), Faculty of Chemical Engineering, Universiti Teknologi Malaysia "…give[s] readers access to both fundamental information on process plant equipment and to practical ideas, best practices and experiences of highly successful engineers from around the world… The book is illustrated throughout with numerous black & white p

  7. Digital Processor Module Reliability Analysis of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lee, Sang Yong; Jung, Jae Hyun; Kim, Jae Ho; Kim, Sung Hun

    2005-01-01

    The system used in plant, military equipment, satellite, etc. consists of many electronic parts as control module, which requires relatively high reliability than other commercial electronic products. Specially, Nuclear power plant related to the radiation safety requires high safety and reliability, so most parts apply to Military-Standard level. Reliability prediction method provides the rational basis of system designs and also provides the safety significance of system operations. Thus various reliability prediction tools have been developed in recent decades, among of them, the MI-HDBK-217 method has been widely used as a powerful tool for the prediction. In this work, It is explained that reliability analysis work for Digital Processor Module (DPM, control module of SMART) is performed by Parts Stress Method based on MIL-HDBK-217F NOTICE2. We are using the Relex 7.6 of Relex software corporation, because reliability analysis process requires enormous part libraries and data for failure rate calculation

  8. Waste treatment plant

    International Nuclear Information System (INIS)

    Adesanmi, C.A

    2009-01-01

    Waste Treatment Plant (WTP) is designed to provide appropriate systems for processing, immobilization and storage of low and medium radioactive waste arising from the operation of the research facilities of the Nuclear Technology Centre (NTC). It will serve as central collection station processing active waste generated through application of radionuclide in science, medicine and industry in the country. WTP building and structures will house the main waste processing systems and supporting facilities. All facilities will be interconnected. The interim storage building for processed waste drums will be located separately nearby. The separate interim storage building is located near the waste treatment building. Considering the low radiation level of the waste, storage building is large with no solid partitioning walls and with no services or extra facilities other than lighting and smoke alarm sensors. The building will be designed such that drums(200-1)are stacked 3 units high using handling by fork lift truck. To prevent radiation exposure to on-site personnel, the interim storage building will be erected apart from waste treatment plant or other buildings. The interim storage building will also be ready for buffer storage of unconditioned waste waiting for processing or decay and for storage material from the WTP

  9. Operational experience, availability and reliability of nuclear power plants

    International Nuclear Information System (INIS)

    Kueffer, K.

    1981-01-01

    This lecture presents a survey on nuclear power production and plant performance in the Western World covering all reactor types and light-water reactors in particular and discusses key parameters such as load factors and non-availability analysis, outlines the main reasons for the reliable performance of Swiss nuclear power plants and explains the management function as applied at the Beznau Nuclear Power Station to ensure high power productivity and reliability. (orig./RW)

  10. Future of structural reliability methodology in nuclear power plant technology

    Energy Technology Data Exchange (ETDEWEB)

    Schueeller, G I [Technische Univ. Muenchen (Germany, F.R.); Kafka, P [Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)

    1978-10-01

    This paper presents the authors' personal view as to which areas of structural reliability in nuclear power plant design need most urgently to be advanced. Aspects of simulation modeling, design rules, codification and specification of reliability, system analysis, probabilistic structural dynamics, rare events and particularly the interaction of systems and structural reliability are discussed. As an example, some considerations of the interaction effects between the protective systems and the pressure vessel are stated. The paper concludes with recommendation for further research.

  11. 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

  12. Reliability of reactor plant water cleanup pumps

    International Nuclear Information System (INIS)

    Pearson, J.L.

    1979-01-01

    Carolina Power and Light Company's Brunswick 2 nuclear plant experienced a high reactor water cleanup pump-failure rate until inlet temperature and flow were reduced and mechanical modifications were implemented. Failures have been zero for about one year, and water cleanup efficiency has increased

  13. Reliability evaluation of nuclear power plants

    International Nuclear Information System (INIS)

    Rondiris, I.L.

    1978-10-01

    The research described in this thesis is concerned with the reliability/safety analysis of complex systems, such as nuclear power stations, basically using the event tree methodology. The thesis introduces and assesses a computational technique which applies the methodology to complex systems by simulating their topology and operational logic. The technique develops the system event tree and relates each branch of this tree to its qualitative and quantitative impact on specified system outcomes following an abnormal operating condition. Then, the thesis aims at deducing the critical failure modes of complex systems. This is achieved by a new technique for deducing the minimal cut or tie sets of various system outcomes. The technique is, furthermore, expanded to identify potential common mode failures and cut or tie sets containing dependent failures of some components. After dealing with the qualitative part of a reliability study, the thesis introduces two methods for calculating the probability of a component being either in the failure or in the partial failure state. The first method deals with revealed faults and makes use of the concept of Markov processes. The second one deals with unrevealed faults and can be used to calculate the relevant probability of component taking into account its inspection and replacement process. (author)

  14. Reliability study: maintenance facilities Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Post, B.E.; Sikorski, P.A.; Fankell, R.; Johnson, O.; Ferryman, D.S.; Miller, R.L.; Gearhart, E.C.; Rafferty, M.J.

    1981-08-01

    A reliability study of the maintenance facilities at the Portsmouth Gaseous Diffusion Plant has been completed. The reliability study team analyzed test data and made visual inspections of each component contributing to the overall operation of the facilities. The impacts of facilities and equipment failures were given consideration with regard to personnel safety, protection of government property, health physics, and environmental control. This study revealed that the maintenance facilities are generally in good condition. After evaluating the physical condition and technology status of the major components, the study team made several basic recommendations. Implementation of the recommendations proposed in this report will help assure reliable maintenance of the plant through the year 2000

  15. 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

  16. Component aging and reliability trends in Loviisa Nuclear Power Plant

    International Nuclear Information System (INIS)

    Jankala, K.E.; Vaurio, J.K.

    1989-01-01

    A plant-specific reliability data collection and analysis system has been developed at the Loviisa Nuclear Power Plant to perform tests for component aging and analysis of reliability trends. The system yields both mean values an uncertainty distribution information for reliability parameters to be used in the PSA project underway and in living-PSA applications. Several different trend models are included in the reliability analysis system. Simple analytical expressions have been derived from the parameters of these models, and their variances have been obtained using the information matrix. This paper is focused on the details of the learning/aging models and the estimation of their parameters and statistical accuracies. Applications to the historical data of the Loviisa plant are presented. The results indicate both up- and down-trends in failure rates as well as individuality between nominally identical components

  17. Improvement on reliability of control system in power plant

    International Nuclear Information System (INIS)

    Taguchi, S.; Mizumoto, T.; Hirose, Y.; Kashiwai, J.; Takami, I.; Shono, M.; Roji, Y.; Kizaki, S.

    1985-01-01

    Studies made of Japanese PWR operating experiences have revealed that failures in the control system are the primary causes of unscheduled shutdowns. An attempt has, therefore, been made to improve the reliability of the control system in order to raise the plant reliability. The following are the procedures applied to solve the issue; study of operating experiences, fault tree analysis and failure mode and effects analysis. Improvement measures are developed for the control system whose failure threatens to cause the plant trip during the plant life. These systems are the main feedwater control system, rod control system, pressurizer control system and main steam control system in the primary control system. As a result, the plant unavailability is expected to be reduced significantly by applying the improvements. The improvements are applied to the plants under construction and the operating plants in co-operation with utilities and vendors. (author)

  18. Reliability and risk treatment centered maintenance

    International Nuclear Information System (INIS)

    Pexa, Martin; Hladik, Tomas; Ales, Zdenek; Legat, Vaclav; Muller, Miroslav; Valasek, Petr; Havlu, Vit

    2014-01-01

    We propose a new methodology for application of well-known tools - RCM, RBI and SIF pro - with the aim to treat risks by means of suitable maintenance. The basis of the new methodology is the complex application of all three methods at the same time and not separately as is typical today. The proposed methodology suggests having just one managing team for reliability and risk treatment centred maintenance (RRTCM), employing existing RCM, RBI, and SIFpro tools concurrently. This approach allows for significant reduction of engineering activities' duration. In the proposed methodology these activities are staged into five phases and structured to eliminate all duplication resulting from separate application of the three tools. The newly proposed methodology saves 45% to 50% of the engineering workload and dequate significant financial savings.

  19. Reliability and risk treatment centered maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Pexa, Martin; Hladik, Tomas; Ales, Zdenek; Legat, Vaclav; Muller, Miroslav; Valasek, Petr [Czech University of Life Sciences Prague, Kamycka (Czech Republic); Havlu, Vit [Unipetrol A. S, Prague (Czech Republic)

    2014-10-15

    We propose a new methodology for application of well-known tools - RCM, RBI and SIF pro - with the aim to treat risks by means of suitable maintenance. The basis of the new methodology is the complex application of all three methods at the same time and not separately as is typical today. The proposed methodology suggests having just one managing team for reliability and risk treatment centred maintenance (RRTCM), employing existing RCM, RBI, and SIFpro tools concurrently. This approach allows for significant reduction of engineering activities' duration. In the proposed methodology these activities are staged into five phases and structured to eliminate all duplication resulting from separate application of the three tools. The newly proposed methodology saves 45% to 50% of the engineering workload and dequate significant financial savings.

  20. Electricity supply. Older plants' impact on reliability and air quality

    International Nuclear Information System (INIS)

    England-Joseph, Judy A.; Adams, Charles M.; Wood, David G.; Feehan, Daniel J.; Veal, Howard F.; Skeen, John H. III; Koenigs, Melvin J.; Lichtenfeld, David I.; Seretakis, Pauline J.

    1990-09-01

    Life extension of fossil fuel plants is a relatively recent phenomenon; thus, utilities have little experience to demonstrate the longer-term operating reliability of plants with an extended service life. While utility industry officials and government and industry studies express optimism that these plants will continue to operate reliably, the officials and the studies also caution that it is too soon to determine how pursuing life extension will affect the reliability of the nation's electricity supply. According to DOE, the number of fossil fuel generating units' 30 years old or older is expected to increase from about 2,500 in 1989 to roughly 3,700 in 1998, increasing such plants' share of overall generating capacity from 13 percent in 1989 to 27 percent in 1998. EPA estimates that with existing air quality requirements, fossil fuel plant emissions will increase steadily during the coming decade. Proposed acid rain control legislation, which would affect many plants that may have their service life extended, would require utilities to significantly reduce emissions by the year 2000 but would allow utilities flexibility in deciding how and where to achieve the reductions. If such legislation is enacted, utilities generally are expected to find reducing emissions from existing plants more cost-effective than replacing them and to continue extending plants' service life. Officials of DOE and utility organizations expressed concern, however, that EPA could decide, as it did for one plant in 1988, that alterations made in extending the service life of plants exempted from the Clean Air Act would result in increased emissions and thus cause the altered plants to lose their exemption. According to the officials, the additional costs of achieving the Clean Air Act's standards could discourage some life extension projects. However, such decisions by EPA could also reduce the nation's total power plant emissions by eliminating an existing incentive to retain exempt

  1. Research on reliability management systems for Nuclear Power Plant

    International Nuclear Information System (INIS)

    Maki, Nobuo

    2000-01-01

    Investigation on a reliability management system for Nuclear Power Plants (NPPs) has been performed on national and international archived documents as well as on current status of studies at Idaho National Engineering and Environmental Laboratory (INEEL), US NPPs (McGuire, Seabrook), a French NPP (St. Laurent-des-Eaux), Japan Atomic Energy Research Institute (JAERI), Central Research Institute of Electric Power Industries (CRIEPI), and power plant manufacturers in Japan. As a result of the investigation, the following points were identified: (i) A reliability management system is composed of a maintenance management system to inclusively manage maintenance data, and an anomalies information and reliability data management system to extract data from maintenance results stored in the maintenance management system and construct a reliability database. (ii) The maintenance management system, which is widely-used among NPPs in the US and Europe, is an indispensable system for the increase of maintenance reliability. (iii) Maintenance management methods utilizing reliability data like Reliability Centered Maintenance are applied for NPP maintenance in the US and Europe, and contributing to cost saving. Maintenance templates are effective in the application process. In addition, the following points were proposed on the design of the system: (i) A detailed database on specifications of facilities and components is necessary for the effective use of the system. (ii) A demand database is indispensable for the application of the methods. (iii) Full-time database managers are important to maintain the quality of the reliability data. (author)

  2. 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.)

  3. 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.)

  4. Technology success: Integration of power plant reliability and effective maintenance

    International Nuclear Information System (INIS)

    Ferguson, K.

    2008-01-01

    The nuclear power generation sector has a tradition of utilizing technology as a key attribute for advancement. Companies that own, manage, and operate nuclear power plants can be expected to continue to rely on technology as a vital element of success. Inherent with the operations of the nuclear power industry in many parts of the world is the close connection between efficiency of power plant operations and successful business survival. The relationship among power plant availability, reliability of systems and components, and viability of the enterprise is more evident than ever. Technology decisions need to be accomplished that reflect business strategies, work processes, as well as needs of stakeholders and authorities. Such rigor is needed to address overarching concerns such as power plant life extension and license renewal, new plant orders, outage management, plant safety, inventory management etc. Particular to power plant reliability, the prudent leveraging of technology as a key to future success is vital. A dominant concern is effective asset management as physical plant assets age. Many plants are in, or are entering in, a situation in which systems and component design life and margins are converging such that failure threats can come into play with increasing frequency. Wisely selected technologies can be vital to the identification of emerging threats to reliable performance of key plant features and initiating effective maintenance actions and investments that can sustain or enhance current reliability in a cost effective manner. This attention to detail is vital to investment in new plants as well This paper and presentation will address (1) specific technology success in place at power plants, including nuclear, that integrates attention to attaining high plant reliability and effective maintenance actions as well as (2) complimentary actions that maximize technology success. In addition, the range of benefits that accrue as a result of

  5. Basic research on human reliability in nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Li; Deng Zhiliang

    1996-10-01

    Human reliability in nuclear power plants is one of key factors in nuclear safety and economic operation. According to cognitive science, behaviour theory and ergonomic and on the bases of human cognitive behaviour characteristics, performance shaping factors, human error mechanisms and organization management, the project systematically studied the human reliability in nuclear power plant systems, established the basic theory and methods for analyzing human factor accidents and suggested feasible approaches and countermeasures for precaution against human factor accidents and improving human reliability. The achievement has been applied in operation departments, management departments and scientific research institutions of nuclear power, and has produced guiding significance and practical value to design, operation and management in nuclear power plants. (11 refs.)

  6. Waste Treatment & Immobilization Plant Project

    Data.gov (United States)

    Federal Laboratory Consortium — In southeastern Washington State, Bechtel National, Inc. is designing, constructing and commissioning the world's largest radioactive waste treatment plant for the...

  7. Plant and control system reliability and risk model

    International Nuclear Information System (INIS)

    Niemelae, I.M.

    1986-01-01

    A new reliability modelling technique for control systems and plants is demonstrated. It is based on modified boolean algebra and it has been automated into an efficient computer code called RELVEC. The code is useful for getting an overall view of the reliability parameters or for an in-depth reliability analysis, which is essential in risk analysis, where the model must be capable of answering to specific questions like: 'What is the probability of this temperature limiter to provide a false alarm', or 'what is the probability of air pressure in this subsystem to drop below lower limit'. (orig./DG)

  8. The reliability of nuclear power plant safety systems

    International Nuclear Information System (INIS)

    Susnik, J.

    1978-01-01

    A criterion was established concerning the protection that nuclear power plant (NPP) safety systems should afford. An estimate of the necessary or adequate reliability of the total complex of safety systems was derived. The acceptable unreliability of auxiliary safety systems is given, provided the reliability built into the specific NPP safety systems (ECCS, Containment) is to be fully utilized. A criterion for the acceptable unreliability of safety (sub)systems which occur in minimum cut sets having three or more components of the analysed fault tree was proposed. A set of input MTBF or MTTF values which fulfil all the set criteria and attain the appropriate overall reliability was derived. The sensitivity of results to input reliability data values was estimated. Numerical reliability evaluations were evaluated by the programs POTI, KOMBI and particularly URSULA, the last being based on Vesely's kinetic fault tree theory. (author)

  9. Cost benefit justification of nuclear plant reliability improvement

    International Nuclear Information System (INIS)

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

    1986-01-01

    Nuclear power costs are evaluated on the bases of general ground rules (a) vary from time to time (b) vary from country to another (c) even vary from one reactor type to another. The main objective of an electric utility is to provide the electric energy to the different consummers at the lowest possible cost with reasonable reliability level. Rapid increase of the construction costs and fuel prices in recent years have stimulated a great deal of interest in improving the reliability and productivity of new and existing power plants. One of the most important areas is the improvement of the secondary steam loop and the reactor cooling system. The method for evaluating the reliability of steam loop and cooling system 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. The cost reliability trade-off analysis is used to evaluate alternative schemes in the design with a view towards meeting a high reliability goal. Based on historical or estimated failure and repair rate, the reliability of the alternate scheme can be calculated

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

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.

    1983-07-01

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

  11. Designing reliable wireless sensor network for nuclear power plant

    International Nuclear Information System (INIS)

    Fujiwara, Takeshi; Takahashi, Hiroyuki

    2007-01-01

    This study proposes an innovative method for the monitoring the nuclear power plant. In this field, false detection of the trouble, both 'false negative' and 'false positive' will become a serious problem. In the other hand, since nuclear power plant is such a complicated system, wireless is required for implementing into real field. Considering these backgrounds, we propose a new reliable health monitoring system for nuclear power plant. This is based on an idea, 'a network on a network', such as 'wireless global network' on 'local network with self-maintenance function.' (author)

  12. Reliability Centered Maintenance as a tool for plant life extension

    International Nuclear Information System (INIS)

    Elliott, J.O.; Mulay, J.N.; Nakahara, Y.

    1991-01-01

    Currently in the nuclear industry there is a growing interest in lowering the cost and complexity of maintenance activities while at the same time improving plant reliability and safety in an effort to prepare for the technical and regulatory challenges of life extension. This seemingly difficult task is being aided by the introduction of a maintenance philosophy developed originally by the airline industry and subsequently applied with great success both in that industry and the U.S. military services. Reliability Centered Maintenance (RCM), in its basic form, may be described as a consideration of reliability and maintenance problems from a systems level approach, allowing a focus on preservation of system function as the aim of a maintenance program optimized for both safety and economics. It is this systematic view of plant maintenance, with the emphasis on overall functions rather than individual parts and components which sets RCM apart from past nuclear plant maintenance philosophies. It is also the factor which makes application of RCM an ideal first step in development of strategies for life extension, both for aging plants, and for plants just beginning their first license term. (J.P.N.)

  13. Operational experience, availability and reliability of nuclear power plants

    International Nuclear Information System (INIS)

    Kueffer, K.

    1980-01-01

    This lecture - presents a survey on nuclear power production and plant performance in the Western World covering all reactor types and light-water reactors in particular and discusses key parameters such as load factors and non-availability analysis. - outlines the main reasons for the reliable performance of Swiss nuclear power plants - quality equipment - operator qualification and training - engineering know how on site - maintenance philosophy and outage planning - information system and feedback of experience - explains the management functions as applied at the Beznau Nuclear Power Station to ensure high power productivity and reliability - improvement - a feedback control system - analysis of production losses - optimization in shut-down planning - minimizing disturbances during plant operation - optimizing personnel qualification and efficiency. (orig.)

  14. Wastewater Treatment Plants

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — The actual treatment areas for municipal, industrial, and semi-public wastewater treatment facilities in Iowa for the National Pollutant Discharge Elimination System...

  15. Waste Treatment Plant - 12508

    Energy Technology Data Exchange (ETDEWEB)

    Harp, Benton; Olds, Erik [US DOE (United States)

    2012-07-01

    The Waste Treatment Plant (WTP) will immobilize millions of gallons of Hanford's tank waste into solid glass using a proven technology called vitrification. The vitrification process will turn the waste into a stable glass form that is safe for long-term storage. Our discussion of the WTP will include a description of the ongoing design and construction of this large, complex, first-of-a-kind project. The concept for the operation of the WTP is to separate high-level and low-activity waste fractions, and immobilize those fractions in glass using vitrification. The WTP includes four major nuclear facilities and various support facilities. Waste from the Tank Farms is first pumped to the Pretreatment Facility at the WTP through an underground pipe-in-pipe system. When construction is complete, the Pretreatment Facility will be 12 stories high, 540 feet long and 215 feet wide, making it the largest of the four major nuclear facilities that compose the WTP. The total size of this facility will be more than 490,000 square feet. More than 8.2 million craft hours are required to construct this facility. Currently, the Pretreatment Facility is 51 percent complete. At the Pretreatment Facility the waste is pumped to the interior waste feed receipt vessels. Each of these four vessels is 55-feet tall and has a 375,000 gallon capacity, which makes them the largest vessels inside the Pretreatment Facility. These vessels contain a series of internal pulse-jet mixers to keep incoming waste properly mixed. The vessels are inside the black-cell areas, completely enclosed behind thick steel-laced, high strength concrete walls. The black cells are designed to be maintenance free with no moving parts. Once hot operations commence the black-cell area will be inaccessible. Surrounded by black cells, is the 'hot cell canyon'. The hot cell contains all the moving and replaceable components to remove solids and extract liquids. In this area, there is ultrafiltration

  16. Reliability evaluation of nuclear power plants by fault tree analysis

    International Nuclear Information System (INIS)

    Iwao, H.; Otsuka, T.; Fujita, I.

    1993-01-01

    As a work sponsored by the Ministry of International Trade and Industry, the Safety Information Research Center of NUPEC, using reliability data based on the operational experience of the domestic LWR Plants, has implemented FTA for the standard PWRs and BWRs in Japan with reactor scram due to system failures being at the top event. Up to this point, we have obtained the FT chart and minimal cut set for each type of system failure for qualitative evaluation, and we have estimated system unavailability, Fussell-Vesely importance and risk worth for components for quantitative evaluation. As the second stage of a series in our reliability evaluation work, another program was started to establish a support system. The aim of this system is to assist foreign and domestic plants in creating countermeasures when incidents occur, by providing them with the necessary information using the above analytical method and its results. (author)

  17. Reliability centred maintenance of nuclear power plant facilities

    International Nuclear Information System (INIS)

    Kovacs, Zoltan; Novakova, Helena; Hlavac, Pavol; Janicek, Frantisek

    2011-01-01

    A method for the optimization of preventive maintenance nuclear power plant equipment, i.e. reliability centred maintenance, is described. The method enables procedures and procedure schedules to be defined such as allow the maintenance cost to be minimized without compromising operational safety or reliability. Also, combinations of facilities which remain available and ensure reliable operation of the reactor unit during the maintenance of other pieces of equipment are identified. The condition-based maintenance concept is used in this process, thereby preventing unnecessary operator interventions into the equipment, which are often associated with human errors. Where probabilistic safety assessment is available, the most important structures, systems and components with the highest maintenance priority can be identified. (orig.)

  18. System 80+ Design and Licensing : Improving Plant Reliability

    International Nuclear Information System (INIS)

    Newman, Robert E.

    1989-01-01

    The U. S. nuclear industry is striving to improve plant reliability and availability through improved plant design, component designs and plant maintenance. In an effort to improve safety and to demonstrate that commercial nuclear power is economically competitive with other energy sources, the utilities, nuclear vendors, architect engineers and constructors, and component suppliers are all participating in an industry-wide effort to develop improved Light Water Reactor (LWR) designs that are based upon the many years of successful LWR operation. In an age when the world faces the environmental pressures of the greenhouse effect and acid rain, electricity generated from nuclear energy must play an increasing role in the energy picture of Korea, the United States and the rest of the world. This paper discusses the plant availability requirement that has been established by the industry-wide effort mentioned above. After briefly describing Combustion Engineering's program for development of the System 80 Plus standard design and the participation of the Korea Advanced Energy Research Institute (KAERI) in the program, the paper then describes the design features that are being incorporated into System 80+. The industry ALRR Program has established a very ambitious criterion of 87% for the plant availability of future nuclear units. To satisfy such a requirement, the next generation of nuclear plants will include a great many design improvements that reflect the hundreds of years of operating experience that we have accrued. C-ESA's System 80+ will include a number of design changes that improve operating margins and make the plant easier to operate and maintain. Not surprisingly, there is a great deal of overlap between improved safety and improved reliability. In the end, our design will satisfy the future needs of the utilities, the regulators, and the public. C-E is very pleased that KAERI is working with US to achieve these important goals

  19. Insights from a reliability review of digital plant protection system

    International Nuclear Information System (INIS)

    Kim, I.S.; Hwang, S.W.; Kim, B.S.; Jeong, C.H.; Oh, S.H.

    2001-01-01

    The full text follows: As part of the design efforts for Ulchin nuclear power plant units 5 and 6 of Korea, a reliability analysis of digital plant protection system (DPPS) was performed by ABB-CE. An independent review of the DPPS reliability analysis was undertaken by Hanyang University to assist Korea Institute of Nuclear Safety (KINS), the nuclear regulatory body of Korea, in evaluating the design acceptability of the digital system. The DPPS is designed to encompass both reactor trip function and ESFAS (engineered safety feature actuation system) initiation function. The major methods used by the ABB-CE to assess the Ulchin 5-6 DPPS reliability are failure mode and effect analysis (FMEA) and fault tree analysis. Hence, our independent review was conducted focusing on: -) the establishment of review criteria based on various sources, such as the standard review plan of KINS, 10CFR50 Appendix A, IEEE standards 279, 577, and 603; -) the suitability of the FMEA and fault tree analysis for the Ulchin 5-6 DPPS, including the specific methods used (e.g., for human reliability analysis and common-cause failure analysis), the assumptions made (e.g., with respect to test frequency and watchdog timer coverage), and the data employed (e.g., CCF parameter, human error probability, and processor failure rate); and -) the design acceptability of the DPPS especially as compared to the analog plant protection system from a reliability and safety perspective. The paper shall also discuss key issues requiring further in-depth investigation, such as reliability of programmable logic controllers (PLCs), coverage factor of watchdog timers, and susceptibility of redundant digital units to common cause failure. Sensitivity analyses were carried out to investigate the impact of several parameters of special interest, like the coverage factor of watchdog timer and human error probability (e.g. an operator error to manually trip the reactor, or to mis-calibrate the trip parameters) on

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

    International Nuclear Information System (INIS)

    Mitra, S.P.

    1979-01-01

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

  1. Relativity evaluation of reliability on operation in nuclear power plant

    International Nuclear Information System (INIS)

    Inata, Takashi

    1987-01-01

    The report presents a quantitative method for evaluating the reliability of operations conducted in nuclear power plants. The quantitative reliability evaluation method is based on the 'detailed block diagram analysis (De-BDA)'. All units of a series of operations are separately displayed for each block and combined sequentially. Then, calculation is performed to evaluate the reliability. Basically, De-BDA calculation is made for pairs of operation labels, which are connected in parallel or in series at different subordination levels. The applicability of the De-BDA method is demonstrated by carrying out calculation for three model cases: operations in the event of malfunction of the control valve in the main water supply system for PWR, switching from an electrically-operated water supply pump to a turbin-operated water supply pump, and isolation and water removal operation for a low-pressure condensate pump. It is shown that the relative importance of each unit of a series of operations can be evaluated, making it possible to extract those units of greater importance, and that the priority among the factors which affect the reliability of operations can be determined. Results of the De-BDA calculation can serve to find important points to be considered in developing an operation manual, conducting education and training, and improving facilities. (Nogami, K.)

  2. Effluent from Wastewater Treatment Plants

    DEFF Research Database (Denmark)

    Kristensen, Jannie Munk; Nierychlo, Marta; Albertsen, Mads

    Incoming microorganisms to wastewater treatment plants (WWTPs) are usually considered to be removed in the treatment process. Analyses of the effluent generally show a very high degree of reduction of pathogens supporting this assumption. However, standard techniques for detecting bacteria......-independent 16SrRNA gene amplicon sequencing was applied for the identification and quantification of the microorganisms. In total 84 effluent samples from 14 full-scale Danish wastewater treatment plants were investigated over a period of 3 months. The microbial community composition was investigated by 16S r...... contain pathogenic species. One of these was Arcobacter (Campylobacteraceae) which was found in up to 16% relative abundance. This indicates that Arcobacter, and perhaps other pathogenic genera, are not being removed efficiently in full-scale plants and may pose a potential health safety problem. Further...

  3. Enrichment planting without soil treatment

    Energy Technology Data Exchange (ETDEWEB)

    Hagner, Mats

    1998-12-31

    Where enrichment planting had been carried out with either of the two species Picea abies and Pinus contorta, the survival of the planted seedlings was at least as good as after planting in a normal clear cut area treated with soil scarification. This was in spite of the fact that the seedlings were placed shallow in the humus layer without any soil treatment. However, they were sheltered from insects by treatment before planting. Where enrichment planting was carried out with Pinus sylvestris the survival in dense forest was poor, but in open forest the survival was good. The growth of planted seedlings was enhanced by traditional clearing and soil treatment. However, this was for Pinus sylvestris not enough to compensate for the loss of time, 1-2 years, caused by arrangement of soil scarification. The growth of seedlings planted under crown cover was directly related to basal area of retained trees. However, the variation in height growth among individual seedlings was very big, which meant that some seedlings grow well also under a fairly dense forest cover. The pioneer species Pinus sylvestris reacted more strongly to basal area of retained trees than did the shade tolerant species Picea abies. Enrichment planting seems to be a necessary tool for preserving volume productivity, at places where fairly intensive harvest of mature trees has been carried out in stands of ordinary forest type in central Sweden. If double seedlings, with one Picea abies and one Pinus sylvestris, are used, the probability for long term establishment is enhanced 13 refs, 20 figs, 4 tabs

  4. Plant Reliability - an Integrated System for Management (PR-ISM)

    International Nuclear Information System (INIS)

    Aukeman, M.C.; Leininger, E.G.; Carr, P.

    1984-01-01

    The Toledo Edison Company, located in Toledo, Ohio, United States of America, recently implemented a comprehensive maintenance management information system for the Davis-Besse Nuclear Power Station. The system is called PR-ISM, meaning Plant Reliability - An Integrated System for Management. PR-ISM provides the tools needed by station management to effectively plan and control maintenance and other plant activities. The PR-ISM system as it exists today consists of four integrated computer applications: equipment data base maintenance, maintenance work order control, administrative activity tracking, and technical specification compliance. PR-ISM is designed as an integrated on-line system and incorporates strong human factors features. PR-ISM provides each responsible person information to do his job on a daily basis and to look ahead towards future events. It goes beyond 'after the fact' reporting. In this respect, PR-ISM is an 'interactive' control system which: captures work requirements and commitments as they are identified, provides accurate and up-to-date status immediately to those who need it, simplifies paperwork and reduces the associated time delays, provides the information base for work management and reliability analysis, and improves productivity by replacing clerical tasks and consolidating maintenance activities. The functional and technical features of PR-ISM, the experience of Toledo Edison during the first year of operation, and the factors which led to the success of the development project are highlighted. (author)

  5. Reliability analysis of common hazardous waste treatment processes

    International Nuclear Information System (INIS)

    Waters, R.D.

    1993-05-01

    Five hazardous waste treatment processes are analyzed probabilistically using Monte Carlo simulation to elucidate the relationships between process safety factors and reliability levels. The treatment processes evaluated are packed tower aeration, reverse osmosis, activated sludge, upflow anaerobic sludge blanket, and activated carbon adsorption

  6. Reliability analysis of common hazardous waste treatment processes

    Energy Technology Data Exchange (ETDEWEB)

    Waters, Robert D. [Vanderbilt Univ., Nashville, TN (United States)

    1993-05-01

    Five hazardous waste treatment processes are analyzed probabilistically using Monte Carlo simulation to elucidate the relationships between process safety factors and reliability levels. The treatment processes evaluated are packed tower aeration, reverse osmosis, activated sludge, upflow anaerobic sludge blanket, and activated carbon adsorption.

  7. Developing Predictive Maintenance Expertise to Improve Plant Equipment Reliability

    International Nuclear Information System (INIS)

    Wurzbach, Richard N.

    2002-01-01

    On-line equipment condition monitoring is a critical component of the world-class production and safety histories of many successful nuclear plant operators. From addressing availability and operability concerns of nuclear safety-related equipment to increasing profitability through support system reliability and reduced maintenance costs, Predictive Maintenance programs have increasingly become a vital contribution to the maintenance and operation decisions of nuclear facilities. In recent years, significant advancements have been made in the quality and portability of many of the instruments being used, and software improvements have been made as well. However, the single most influential component of the success of these programs is the impact of a trained and experienced team of personnel putting this technology to work. Changes in the nature of the power generation industry brought on by competition, mergers, and acquisitions, has taken the historically stable personnel environment of power generation and created a very dynamic situation. As a result, many facilities have seen a significant turnover in personnel in key positions, including predictive maintenance personnel. It has become the challenge for many nuclear operators to maintain the consistent contribution of quality data and information from predictive maintenance that has become important in the overall equipment decision process. These challenges can be met through the implementation of quality training to predictive maintenance personnel and regular updating and re-certification of key technology holders. The use of data management tools and services aid in the sharing of information across sites within an operating company, and with experts who can contribute value-added data management and analysis. The overall effectiveness of predictive maintenance programs can be improved through the incorporation of newly developed comprehensive technology training courses. These courses address the use of

  8. Ejectors of power plants turbine units efficiency and reliability increasing

    Science.gov (United States)

    Aronson, K. E.; Ryabchikov, A. Yu.; Kuptsov, V. K.; Murmanskii, I. B.; Brodov, Yu. M.; Zhelonkin, N. V.; Khaet, S. I.

    2017-11-01

    The functioning of steam turbines condensation systems influence on the efficiency and reliability of a power plant a lot. At the same time, the condensation system operating is provided by basic ejectors, which maintain the vacuum level in the condenser. Development of methods of efficiency and reliability increasing for ejector functioning is an actual problem of up-to-date power engineering. In the paper there is presented statistical analysis of ejector breakdowns, revealed during repairing processes, the influence of such damages on the steam turbine operating reliability. It is determined, that 3% of steam turbine equipment breakdowns are the ejector breakdowns. At the same time, about 7% of turbine breakdowns are caused by different ejector malfunctions. Developed and approved design solutions, which can increase the ejector functioning indexes, are presented. Intercoolers are designed in separated cases, so the air-steam mixture can’t move from the high-pressure zones to the low-pressure zones and the maintainability of the apparatuses is increased. By U-type tubes application, the thermal expansion effect of intercooler tubes is compensated and the heat-transfer area is increased. By the applied nozzle fixing construction, it is possible to change the distance between a nozzle and a mixing chamber (nozzle exit position) for operating performance optimization. In operating conditions there are provided experimental researches of more than 30 serial ejectors and also high-efficient 3-staged ejector EPO-3-80, designed by authors. The measurement scheme of the designed ejector includes 21 indicator. The results of experimental tests with different nozzle exit positions of the ejector EPO-3-80 stream devices are presented. The pressure of primary stream (water steam) is optimized. Experimental data are well-approved by the calculation results.

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

    International Nuclear Information System (INIS)

    Eisenhut, D.G.

    1978-01-01

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

  10. Fuel Cell Balance-of-Plant Reliability Testbed Project

    Energy Technology Data Exchange (ETDEWEB)

    Sproat, Vern [Stark State College of Technology, North Canton, OH (United States); LaHurd, Debbie [Lockheed Martin Corp., Oak Ridge, TN (United States)

    2016-10-29

    Reliability of the fuel cell system balance-of-plant (BoP) components is a critical factor that needs to be addressed prior to fuel cells becoming fully commercialized. Failure or performance degradation of BoP components has been identified as a life-limiting factor in fuel cell systems.1 The goal of this project is to develop a series of test beds that will test system components such as pumps, valves, sensors, fittings, etc., under operating conditions anticipated in real Polymer Electrolyte Membrane (PEM) fuel cell systems. Results will be made generally available to begin removing reliability as a roadblock to the growth of the PEM fuel cell industry. Stark State College students participating in the project, in conjunction with their coursework, have been exposed to technical knowledge and training in the handling and maintenance of hydrogen, fuel cells and system components as well as component failure modes and mechanisms. Three test beds were constructed. Testing was completed on gas flow pumps, tubing, and pressure and temperature sensors and valves.

  11. Hybrid biomass-wind power plant for reliable energy generation

    International Nuclear Information System (INIS)

    Perez-Navarro, A.; Alfonso, D.; Alvarez, C.; Ibanez, F.; Sanchez, C.; Segura, I.

    2010-01-01

    Massive implementation of renewable energy resources is a key element to reduce CO 2 emissions associated to electricity generation. Wind resources can provide an important alternative to conventional electricity generation mainly based on fossil fuels. However, wind generators are greatly affected by the restrictive operating rules of electricity markets because, as wind is naturally variable, wind generators may have serious difficulties on submitting accurate generation schedules on a day ahead basis, and on complying with scheduled obligations in real-time operation. In this paper, an innovative system combining a biomass gasification power plant, a gas storage system and stand-by generators to stabilize a generic 40 MW wind park is proposed and evaluated with real data. The wind park power production model is based on real data about power production of a Spanish wind park and a probabilistic approach to quantify fluctuations and so, power compensation needs. The hybrid wind-biomass system is analysed to obtain main hybrid system design parameters. This hybrid system can mitigate wind prediction errors and so provide a predictable source of electricity. An entire year cycle of hourly power compensations needs has been simulated deducing storage capacity, extra power needs of the biomass power plant and stand-by generation capacity to assure power compensation during critical peak hours with acceptable reliability. (author)

  12. Overview of plant reliability and aging in Sweden

    International Nuclear Information System (INIS)

    Eckered, T.

    1985-01-01

    In a wide sense aging includes all the phenomena that cause properties of a system to deviate from those existing at the time of start of operation of the system. Such phenomena are of course those well known ones as corrosion, erosion, fatigue and wear. But other phenomena can be included like technological development making original designs obsolete or the learning or forgetting of operators. In this presentation the Swedish nuclear power programme will be briefly described, especially as concerns different generations of nuclear reactors and their operation history. Operating experience, including scram statistics and trends, will be covered as well as availability and reliability as functions of plant age and plant generation. Specific aging phenomena which have been experienced in Sweden, will be described as well as the actions taken or planned for coping with them. The means and tools used in Sweden for tracking aging phenomena will also be covered. The question is posed whether we need an international data bank for aging, maintenance and repair information similar to the already existing, successful incident data banks

  13. Reliability research to nuclear power plant operators based on several methods

    International Nuclear Information System (INIS)

    Fang Xiang; Li Fu; Zhao Bingquan

    2009-01-01

    The paper utilizes many kinds of international reliability research methods, and summarizes the review of reliability research of Chinese nuclear power plant operators in past over ten years based on the simulator platform of nuclear power plant. The paper shows the necessity and feasibility of the research to nuclear power plant operators from many angles including human cognition reliability, fuzzy mathematics model and psychological research model, etc. It will be good to the safe operation of nuclear power plant based on many kinds of research methods to the reliability research of nuclear power plant operators. (authors)

  14. The reliability evaluation of reclaimed water reused in power plant project

    Science.gov (United States)

    Yang, Jie; Jia, Ru-sheng; Gao, Yu-lan; Wang, Wan-fen; Cao, Peng-qiang

    2017-12-01

    The reuse of reclaimed water has become one of the important measures to solve the shortage of water resources in many cities, But there is no unified way to evaluate the engineering. Concerning this issue, it took Wanneng power plant project in Huai city as a example, analyzed the reliability of wastewater reuse from the aspects of quality in reclaimed water, water quality of sewage plant, the present sewage quantity in the city and forecast of reclaimed water yield, in particular, it was necessary to make a correction to the actual operation flow rate of the sewage plant. the results showed that on the context of the fluctuation of inlet water quality, the outlet water quality of sewage treatment plants is basically stable, and it can meet the requirement of circulating cooling water, but suspended solids(SS) and total hardness in boiler water exceed the limit, and some advanced treatment should be carried out. In addition, the total sewage discharge will reach 13.91×104m3/d and 14.21×104m3/d respectively in the two planning level years of the project. They are greater than the normal collection capacity of the sewage system which is 12.0×104 m3/d, and the reclaimed water yield can reach 10.74×104m3/d, which is greater than the actual needed quantity 8.25×104m3/d of the power plant, so the wastewater reuse of this sewage plant are feasible and reliable to the power plant in view of engineering.

  15. OPERATION OF THE HOUSEHOLD SEWAGE TREATMENT PLANTS IN POLAND

    Directory of Open Access Journals (Sweden)

    Marcelina Pryszcz

    2015-01-01

    Full Text Available In many rural communities the building of sewage collection and treatment system is still current and important problem of water and wastewater management. Besides the collection of sewage in the septic tank, the solution for wastewater treatment from individual buildings without access to sewerage system is the construction of household sewage treatment plants. Construction of household sewage treatment plant poses a number of challenges for municipalities and potential investors. The existing plants should be analyzed, so that in the future the selected systems would be characterized by high performance, simple operation and reliable exploitation. In the paper, the assessment of selection criteria of adopted technical solution and the functioning of household sewage treatment plants is carried out.

  16. Demonstration test for reliability of valves for atomic power plants

    International Nuclear Information System (INIS)

    Hosaka, Shiro

    1978-01-01

    The demonstration test on the reliability of valves for atomic power plants being carried out by the Nuclear Engineering Test Center is reported. This test series is conducted as six-year project from FY 1976 to FY 1981 at the Isogo Test Center. The demonstration test consists of (1) environmental test, (2) reaction force test, (3) vibration test, (4) stress measurement test, (5) operational characteristic test, (6) flow resistance coefficient measuring test, (7) leakage test and (8) safety valve and relief valve test. These contents are explained about the special requirements for nuclear use, for example, the enviornmental condition after the design base accident of PWRs and BWRs, the environmental test sequence for isolation valves of containment vessels under the emergency condition, the seismic test condition for valves of nuclear use, the various stress measurements under thermal transient conditions, the leak test after 500 cycles between the normal operating conditions for PWRs and BWRs and the start up conditions and so on. As for the testing facilities, the whole flow diagram is shown, in which the environmental test section, the vibration test section, the steam test section, the hot water test section, the safety valve test section and main components are included. The specifications of each test section and main components are presented. (Nakai, Y.)

  17. Human performance and reliability studies on nuclear power plant

    International Nuclear Information System (INIS)

    Miyaoka, S.

    1988-01-01

    The TMI accident in USA, the Chernobyl accident in USSR and other major accidents overseas have shown that it is necessary to investigate and research human factor problems related to operation, maintenance and others in order to increase the safety and reliability of nuclear power plants. Although a variety of countermeasures have been devised, the accidents and failures due to human factors still occur. So far, the problems related to human factors have not been fundamantally and systematically investigated. Also the data base related to this problem has not been developed. Therefore, the government and electric utility industry began the research on the prevention of the accidents caused by human errors. The basic research is carried out by the government, and the applied research is done by electric utility industry. The Central Research Institute of Electric Power Industry established the Human Factors Research Center on July 1, 1987. The research program in the Human Factors Research Center is divided into the basic research to clarity fundamental human characteristics, the systematic research to apply this information and the analytical research on human error experience. These research activities are reported. (Kako, I.)

  18. The experiences to improve plant performance and reliability of Ko-Ri nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Ho Weon [Korea Electric Power Corp. Ko-Ri nuclear power division, Ko-Ri (Korea, Republic of)

    1998-07-01

    This paper provides a discussion of the lessons learned from operational experience and the future plans to improve performance of the Ko-Ri plant. To operate nuclear power plants safely with good performance is the only way to mitigate the negative image of nuclear power generation to the public and to enhance the economical benefit compared to other electrical generation method. Therefore, in a continuous effort to overcome a negative challenge from outside, we have driven an aggressive 'OCTF' campaign as part of safety. As a result of our efforts, the following remarkable achievements have been accomplished. (1) 3 times of OCTF during recent three years (2) Selected twice as a top notch power plant on the list of NEI magazine in terms of plant capacity factor (3) No scram recorded in 1997 for all 4 units at Ko-Ri site. Ko-Ri is now undergoing the large scale plant betterment projects for retaking-off our operating performance to the level of new challenge target. Such improvement of critical components in the reactor coolant system and turbine system greatly contribute to increase the safety and reliability of the plant and to shortening of the planned outage period as well as to reduction of radiation exposure and radwaste. (Cho, G. S.). 5 tabs., 10 figs.

  19. The experiences to improve plant performance and reliability of Ko-Ri nuclear power plants

    International Nuclear Information System (INIS)

    Kang, Ho Weon

    1998-01-01

    This paper provides a discussion of the lessons learned from operational experience and the future plans to improve performance of the Ko-Ri plant. To operate nuclear power plants safely with good performance is the only way to mitigate the negative image of nuclear power generation to the public and to enhance the economical benefit compared to other electrical generation method. Therefore, in a continuous effort to overcome a negative challenge from outside, we have driven an aggressive 'OCTF' campaign as part of safety. As a result of our efforts, the following remarkable achievements have been accomplished. (1) 3 times of OCTF during recent three years (2) Selected twice as a top notch power plant on the list of NEI magazine in terms of plant capacity factor (3) No scram recorded in 1997 for all 4 units at Ko-Ri site. Ko-Ri is now undergoing the large scale plant betterment projects for retaking-off our operating performance to the level of new challenge target. Such improvement of critical components in the reactor coolant system and turbine system greatly contribute to increase the safety and reliability of the plant and to shortening of the planned outage period as well as to reduction of radiation exposure and radwaste. (Cho, G. S.). 5 tabs., 10 figs

  20. Summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Choi, S. Y.; Han, S. H.

    2004-01-01

    The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA of Korean nuclear power plants. We have performed a study to develop the component reliability DB and S/W for component reliability analysis. Based on the system, we had have collected the component operation data and failure/repair data during plant operation data to 1998/2000 for YGN 3,4/UCN 3,4 respectively. Recently, we have upgraded the database by collecting additional data by 2002 for Korean standard nuclear power plants and performed component reliability analysis and Bayesian analysis again. In this paper, we supply the summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant and describe the plant specific characteristics compared to the generic data

  1. Theory model and experiment research about the cognition reliability of nuclear power plant operators

    International Nuclear Information System (INIS)

    Fang Xiang; Zhao Bingquan

    2000-01-01

    In order to improve the reliability of NPP operation, the simulation research on the reliability of nuclear power plant operators is needed. Making use of simulator of nuclear power plant as research platform, and taking the present international reliability research model-human cognition reliability for reference, the part of the model is modified according to the actual status of Chinese nuclear power plant operators and the research model of Chinese nuclear power plant operators obtained based on two-parameter Weibull distribution. Experiments about the reliability of nuclear power plant operators are carried out using the two-parameter Weibull distribution research model. Compared with those in the world, the same results are achieved. The research would be beneficial to the operation safety of nuclear power plant

  2. The reliability data acquisition system in PWR nuclear power plants

    International Nuclear Information System (INIS)

    Lienart, P.

    1984-01-01

    In April 1978, Electricite de France put a reliability data acquisition system (SRDF) into operation at its two nuclear power plant sites: Fessenheim and Bugey. In the light of the experience acquired and the advantages offered by such a data bank, this system has been progressively extended since 1982 to cover the entire PWR network. The SRDF was originally designed for the follow-up of 4000 items of equipment per pair of units. However, the various difficulties encountered in gathering data made it necessary - in order to safeguard the quality of the information - to reduce this number initially to 800 major mechanical or electromechanical items of equipment designed to ensure the safety or availability of the units. Subsequently, an increase to 1100 was possible. The SRDF consists of a centralized information bank linked by telephone to the various nuclear sites. The software enables the data-acquisition cards to be introduced, modified or deleted. Any user can gain access to the bank by simply making queries in real time. The quality of the acquisition and processing of the data depend on a list of equipment confined to essential operational systems and on a card design combining, as far as possible, the precision and accessibility of the data. A method of logical failure analysis has also been devised, its main purposes being to provide the following: (1) aid to card instruction; (2) an easier way of checking the uniformity of information concerning a failure; and (3) compatibility between the instructions and analysis of data, thereby facilitating development of the data-processing program. (author)

  3. Science Based Human Reliability Analysis: Using Digital Nuclear Power Plant Simulators for Human Reliability Research

    Science.gov (United States)

    Shirley, Rachel Elizabeth

    Nuclear power plant (NPP) simulators are proliferating in academic research institutions and national laboratories in response to the availability of affordable, digital simulator platforms. Accompanying the new research facilities is a renewed interest in using data collected in NPP simulators for Human Reliability Analysis (HRA) research. An experiment conducted in The Ohio State University (OSU) NPP Simulator Facility develops data collection methods and analytical tools to improve use of simulator data in HRA. In the pilot experiment, student operators respond to design basis accidents in the OSU NPP Simulator Facility. Thirty-three undergraduate and graduate engineering students participated in the research. Following each accident scenario, student operators completed a survey about perceived simulator biases and watched a video of the scenario. During the video, they periodically recorded their perceived strength of significant Performance Shaping Factors (PSFs) such as Stress. This dissertation reviews three aspects of simulator-based research using the data collected in the OSU NPP Simulator Facility: First, a qualitative comparison of student operator performance to computer simulations of expected operator performance generated by the Information Decision Action Crew (IDAC) HRA method. Areas of comparison include procedure steps, timing of operator actions, and PSFs. Second, development of a quantitative model of the simulator bias introduced by the simulator environment. Two types of bias are defined: Environmental Bias and Motivational Bias. This research examines Motivational Bias--that is, the effect of the simulator environment on an operator's motivations, goals, and priorities. A bias causal map is introduced to model motivational bias interactions in the OSU experiment. Data collected in the OSU NPP Simulator Facility are analyzed using Structural Equation Modeling (SEM). Data include crew characteristics, operator surveys, and time to recognize

  4. Nuclear plant reliability data system. 1979 annual reports of cumulative system and component reliability

    International Nuclear Information System (INIS)

    1979-01-01

    The primary purposes of the information in these reports are the following: to provide operating statistics of safety-related systems within a unit which may be used to compare and evaluate reliability performance and to provide failure mode and failure rate statistics on components which may be used in failure mode effects analysis, fault hazard analysis, probabilistic reliability analysis, and so forth

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

    International Nuclear Information System (INIS)

    Zheng Wei; Li He

    2006-03-01

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

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

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  7. Reliability

    OpenAIRE

    Condon, David; Revelle, William

    2017-01-01

    Separating the signal in a test from the irrelevant noise is a challenge for all measurement. Low test reliability limits test validity, attenuates important relationships, and can lead to regression artifacts. Multiple approaches to the assessment and improvement of reliability are discussed. The advantages and disadvantages of several different approaches to reliability are considered. Practical advice on how to assess reliability using open source software is provided.

  8. Reliability of the emergency AC power system at nuclear power plants

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.; Baranowsky, P.W.

    1983-01-01

    The reliability of the emergency ac power systems typical of most nuclear power plants was estimated, and the cost and increase in reliability for several improvements were estimated. Fault trees were constructed based on a detailed design review of the emergency ac power systems of 18 nuclear plants. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports (LERs) and from operating experience information obtained from nuclear plant licensees. No one or two improvements can be made at all plants to significantly increase the industry-average emergency ac power system reliability; rather the most beneficial improvements are varied and plant specific. Improvements in reliability and the associated costs are estimated using plant specific designs and failure probabilities

  9. The importance of the reliability study for the safety operation of chemical plants. Application in heavy water plants

    International Nuclear Information System (INIS)

    Dumitrescu, Maria; Lazar, Roxana Elena; Preda, Irina Aida; Stefanescu, Ioan

    1999-01-01

    Heavy water production in Romania is based on H 2 O-H 2 S isotopic exchange process followed by vacuum isotopic distillation. The heavy water plant are complex chemical systems, characterized by an ensemble of static and dynamic equipment, AMC components, enclosures. Such equipment must have a high degree of reliability, a maximum safety in technological operation and a high availability index. Safety, reliable and economical operation heavy water plants need to maintain the systems and the components at adequate levels of reliability. The paper is a synthesis of the qualitative and quantitative assessment reliability studies for heavy water plants. The operation analysis on subsystems, each subsystems being a well-defined unit, is required by the plant complexity. For each component the reliability indicators were estimated by parametric and non-parametric methods based on the plant operation data. Also, the reliability qualitative and quantitative assessment was done using the fault tree technique. For the dual temperature isotopic exchange plants the results indicate an increase of the MTBF after the first years of operation, illustrating both the operation experience increasing and maintenance improvement. Also a high degree of availability was illustrated by the reliability studies of the vacuum distillation plant. The establishment of the reliability characteristics for heavy water plant represents an important step, a guide for highlighting the elements and process liable to failure being at the same time a planning modality to correlate the control times with the maintenance operations. This is the way to minimise maintenance, control and costs. The main purpose of the reliability study was the safety increase of the plant operation and the support for decision making. (authors)

  10. Reliability analysis of digital safety systems at nuclear power plants

    International Nuclear Information System (INIS)

    Sopira Vladimir; Kovacs, Zoltan

    2015-01-01

    Reliability analysis of digital reactor protection systems built on the basis of TELEPERM XS is described, and experience gained by the Slovak RELKO company during the past 20 years in this domain is highlighted. (orig.)

  11. On estimation of reliability of a nuclear power plant with tokamak reactor

    International Nuclear Information System (INIS)

    Klemin, A.I.; Smetannikov, V.P.; Shiverskij, E.A.

    1982-01-01

    The results of the analysis of INTOR plant reliability are presented. The first stage of the analysis consists in the calculation of the INTOR plant structural reliability factors (15 ibs main systems have been considered). For each system the failure flow parameter (W(1/h)) and operational readiness Ksub(r) have been determined which for the plant as a whole besides these factors-technological utilization coefficient Ksub(TU) and mean-cycles-between failures Tsub(o). The second stage of the reliability analysis consists in investigating methods of improving its reliability factors reratively to the one calculated at the first level stage. It is shown that the reliability of the whole plant to the most essential extent is determined by the power supply system reliability. The following as to the influence extent on the INTOR plant reliability is the cryogenic system. Calculations of the INTOR plant reliability factors have given the following values: W=4,5x10 -3 1/h. Tsub(o)=152 h, Ksub(r)=0,71, Ksub(TU)=o,4 g

  12. 'Living PRA' concept for plant risk: Reliability and availability tracking

    International Nuclear Information System (INIS)

    Sancaktar, S.; Sharp, D.R.

    1985-01-01

    The 'Living PRA' (Probabilistic Risk Assessment) is based on placing a PRA plant model on an interactive computer. This model consists of fault tree analyses for plant systems, event tree analyses for abnormal events and site specific consequence analysis for public and/or financial risks, for a nuclear power plant. A living PRA allows updates and sensitivity analyses by the plant owner throughout the lifetime of a plant. Recently, event and fault trees from two major PRAs were placed in a computerized format. The BYRON PRA study and the Living PRA and Economic Risk examples for Indian Point Unit-3 enabled analysts to gain experience and insight into the problems of plant operation. The above concept is well established for the Nuclear Power Plant evaluation. It has been also used for evaluation of processing facilities. In these studies, systems modeling was carried out by using the GRAFTER system for automated fault tree construction. Presently both the tools and the experience exists to set up useful and viable living PRA models for nuclear and chemical processing plants to enhance risk management by the plant owners through in-house use of micro computer based models

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  14. Reliability Analysis Study of Digital Reactor Protection System in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Guo, Xiao Ming; Liu, Tao; Tong, Jie Juan; Zhao, Jun

    2011-01-01

    The Digital I and C systems are believed to improve a plants safety and reliability generally. The reliability analysis of digital I and C system has become one research hotspot. Traditional fault tree method is one of means to quantify the digital I and C system reliability. Review of advanced nuclear power plant AP1000 digital protection system evaluation makes clear both the fault tree application and analysis process to the digital system reliability. One typical digital protection system special for advanced reactor has been developed, which reliability evaluation is necessary for design demonstration. The typical digital protection system construction is introduced in the paper, and the process of FMEA and fault tree application to the digital protection system reliability evaluation are described. Reliability data and bypass logic modeling are two points giving special attention in the paper. Because the factors about time sequence and feedback not exist in reactor protection system obviously, the dynamic feature of digital system is not discussed

  15. Is biomass a reliable estimate of plant fitness?

    Czech Academy of Sciences Publication Activity Database

    Younginger, B.S.; Sirová, Dagmara; Cruzan, M.B.; Ballhorn, D.J.

    2017-01-01

    Roč. 5, č. 2 (2017), č. článku 1600094. ISSN 2168-0450 Institutional support: RVO:60077344 Keywords : biomass * fecundity * fitness * plant performance * selection Subject RIV: EH - Ecology, Behaviour OBOR OECD: Plant sciences, botany Impact factor: 1.492, year: 2016

  16. Verification of practicability of quantitative reliability evaluation method (De-BDA) in nuclear power plants

    International Nuclear Information System (INIS)

    Takahashi, Kinshiro; Yukimachi, Takeo.

    1988-01-01

    A variety of methods have been applied to study of reliability analysis in which human factors are included in order to enhance the safety and availability of nuclear power plants. De-BDA (Detailed Block Diagram Analysis) is one of such mehtods developed with the objective of creating a more comprehensive and understandable tool for quantitative analysis of reliability associated with plant operations. The practicability of this method has been verified by applying it to reliability analysis of various phases of plant operation as well as evaluation of enhanced man-machine interface in the central control room. (author)

  17. 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)

  18. Reliability of the emergency ac-power system at nuclear power plants

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.; Baranowsky, P.W.

    1982-01-01

    The reliability of the emergency ac-power systems typical of several nuclear power plants was estimated, the costs of several possible improvements was estimated. Fault trees were constructed based on a detailed design review of the emergency ac-power systems of 18 nuclear plants. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports (LERs) and from operating experience information obtained from nuclear plant licensees. It was found that there are not one or two improvements that can be made at all plants to significantly increase the industry-average emergency ac-power-system reliability, but the improvements are varied and plant-specific. Estimates of the improvements in reliability and the associated cost are estimated using plant-specific designs and failure probabilities

  19. 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

  20. Optimization of redundancy by using genetic algorithm for reliability of plant protection system

    International Nuclear Information System (INIS)

    Yoo, D. W.; Seong, S. H.; Kim, D. H.; Park, H. Y.; Gu, I. S.

    2000-01-01

    The design and development of a reliable protection system has been becoming a key issue in industry field because the reliability of system is considered as an important factor to perform the system's function successfully. Plant Protection System(PPS) guarantees the safety of plant by accident detection and control action against the transient conditions of plant. This paper presents the analysis of PPS reliability and the formal problem statement about optimal redundancy based on the reliability of PPS. And the optimization problem is solved by genetic algorithm. The genetic algorithm is a useful tool to solve the problems, in the case of large searching, complex gradient, existence local minimum. The effectiveness of the proposed optimization technique is proved by the target reliability of one channel of PPS, using the failure rate based on the MIL-HDBK-217

  1. Nuclear power plants. Guidelines to ensure quality of collected data on reliability

    International Nuclear Information System (INIS)

    1983-01-01

    This international standard lays down guidelines to be followed in the collection of data relative to nuclear power plants so as to ensure the reliability and completeness of the data and its insertion in a computerized system

  2. The impact of reliability centered maintenance on plant prospects for license renewal

    International Nuclear Information System (INIS)

    Elliott, J.O.; Nakahara, Y.

    1991-01-01

    Much attention has been directed in recent years to means of extending nuclear power plant life. As many plants enter their third decade of service, the questions loom large of how to keep aging plants reliable, as well as how to assure reliability and safety to an extent sufficient to warrant license renewal at the end of the current licensing term. Concurrently the nuclear industry has seen a growing interest in reducing the cost and complexity of maintenance activities while at the same time improving plant reliability and availability. Attainment of these seemingly contradictory aims is being aided by the introduction of a maintenance philosophy developed originally by the airline industry and subsequently applied with great success both in that industry and the U.S. military services. Reliability Centered Maintenance (RCM), in its basic form, may be described as a consideration of reliability and maintenance problems from a systems level approach, allowing a focus on preservation of system functions as the aim of a maintenance program optimized for both safety and economics. It is this systematic view of plant maintenance, with the emphasis on preservation of overall functions rather than individual parts and components which sets RCM apart from past nuclear plant maintenance philosophies. It is also the factor which makes application of RCM an ideal first step in development of strategies for life extension and license renewal, both for aging plants, and for plants just beginning their first license term

  3. Uprading of existing treatment plants in Poland

    OpenAIRE

    Stene-Johansen, S.; Paulsrud, B.

    1994-01-01

    During the first Phase, diagnostic studies have been carried out at selected treatment plants in order to identify problems and how to improve treatment efficiency (Report 1 st. Phase). The report in hand (2nd. Phase) gives recommendations for upgrading/rehabilitation and other improvements based on full scale experiments at selected treatment plants. State Pollution Control Authority (SFT) The Royal Norwegian Ministry of Environment (MD)

  4. Reliability of diesel generators at the Finnish and Swedish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Pulkkinen, Urho [Technical Research Centre of Finland, Vuorimiehentie 5, SF-02150, Espoo (Finland)

    1986-02-15

    The operating experiences of 40 stand-by diesel generators at the Finnish and Swedish nuclear power plants have been analysed with special emphasis on the impact of the frequency of surveillance testing and of the test procedure on diesel generator reliability, the contribution of design, manufacturing, testing and maintenance errors and the potential and actual common cause failures, The results pf the analyses consisted both practical recommendations and mathematical reliability models and useful reliability data. (author)

  5. On estimation of reliability for pipe lines of heat power plants under cyclic loading

    International Nuclear Information System (INIS)

    Verezemskij, V.G.

    1986-01-01

    One of the possible methods to obtain a quantitative estimate of the reliability for pipe lines of the welded heat power plants under cyclic loading due to heating-cooling and due to vibration is considered. Reliability estimate is carried out for a common case of loading by simultaneous cycles with different amplitudes and loading asymmetry. It is shown that scattering of the breaking number of cycles for the metal of welds may perceptibly decrease reliability of the welded pipe line

  6. HTGR plant availability and reliability evaluations. Volume II. Appendices

    International Nuclear Information System (INIS)

    Cadwallader, G.J.; Hannaman, G.W.; Jacobsen, F.K.; Stokely, R.J.

    1976-12-01

    Information is presented in the following areas: methodology of identifying components and systems important for availability studies, failure modes and effects analyses, quantitative evaluations, comparison with experience, estimated cost of plant unavailability, and probabilistic use of interest formulas for rare events

  7. Radiotracer Applications in Wastewater Treatment Plants

    International Nuclear Information System (INIS)

    2011-01-01

    Wastewater containing pollutants resulting from municipal and industrial activities are normally collected in wastewater treatment plants (WWTPs) for processing before discharge to the environment. The WWTPs are the last barrier against contamination of downstream surface waters such as rivers, lakes and sea. Treated wastewater is reused for irrigation, particularly in arid and semi-arid countries. Therefore, it is very important to maintain optimal operating conditions of WWTPs to eliminate or reduce environmental pollution. Wastewater treatment plants are complicated systems, where the processes of mixing, separation, aeration, biological and chemical reactions occur. A WWTP is basically a multiphase system, and the efficiency of an installation strongly depends on liquid, solid and gas phase flow structures and their residence time distributions (RTDs). However, the fluid dynamic properties of such systems are not yet completely understood, rendering difficult the theoretical prediction of important process parameters such as flow rates, phase distributions, mixing and sediment characteristics. Tracer techniques are very useful tools to investigate the efficiency of purification in WWTPs, aiding both their design and performance optimization. There are many kinds of tracers. Radioactive tracers are the most sensitive and are largely used for on-line diagnosis of various operations in WWTPs. The success of radiotracer applications rests upon their extremely high detection sensitivity, and the strong resistance against severe process conditions. During the last few decades, many radiotracer studies have been conducted worldwide for investigation of various installations for wastewater treatment, such as mixer, aeration tank, clarifiers, digester, filter, wetland and oxidation units. Various radiotracer methods and techniques have been developed by individual tracer groups. However, the information necessary for the preservation of knowledge and transfer of

  8. Nuclear Power Plant Operator Reliability Research Based on Fuzzy Math

    Directory of Open Access Journals (Sweden)

    Fang Xiang

    2011-01-01

    Full Text Available This paper makes use of the concept and theory of fuzzy number in fuzzy mathematics, to research for the response time of operator in accident of Chinese nuclear power plant. Through the quantitative analysis for the performance shape factors (PSFs which influence the response time of operators, the formula of the operator response time is obtained based on the possibilistic fuzzy linear regression model which is used for the first time in this kind of research. The research result shows that the correct research method can be achieved through the analysis of the information from a small sample. This method breaks through the traditional research method and can be used not only for the reference to the safe operation of nuclear power plant, but also in other areas.

  9. Research on cognitive reliability model for main control room considering human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Jiang Jianjun; Zhang Li; Wang Yiqun; Zhang Kun; Peng Yuyuan; Zhou Cheng

    2012-01-01

    Facing the shortcomings of the traditional cognitive factors and cognitive model, this paper presents a Bayesian networks cognitive reliability model by taking the main control room as a reference background and human factors as the key points. The model mainly analyzes the cognitive reliability affected by the human factors, and for the cognitive node and influence factors corresponding to cognitive node, a series of methods and function formulas to compute the node cognitive reliability is proposed. The model and corresponding methods can be applied to the evaluation of cognitive process for the nuclear power plant operators and have a certain significance for the prevention of safety accidents in nuclear power plants. (authors)

  10. ORNL process waste treatment plant modifications

    International Nuclear Information System (INIS)

    Bell, J.P.

    1982-01-01

    The ORNL Process Waste Treatment Plant removes low levels of radionuclides (primarily Cs-137 and Sr-90) from process waste water prior to discharge. The previous plant operation used a scavenging precipitaton - ion exchange process which produced a radioactive sludge. In order to eliminate the environmental problems associated with sludge disposal, the plant is being converted to a new ion exchange process without the precipitation process

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

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

    International Nuclear Information System (INIS)

    Ochrana, L.

    1997-01-01

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

  13. Reliability of diesel generators in the Finnish and Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Pulkkinen, U.; Huovinen, T.; Norros, L.; Vanhala, J.

    1989-10-01

    Diesel generators are used as emergency AC-power sources in nuclear power plants and they produce electric power for other emergency systems during accidents in which offsite power is lost. The reliability of diesel generators is thus of major concern for overall safety of nuclear power plants. In this study we consider the reliability of diesel generators in the Swedish and Finnish nuclear power plants on the basis of collected operational experience. We classify the occurred failures according to their functional criticality, type and cause. The failures caused by human errors in maintenance and testing are analysed in detail. We analyse also the reliability of the diesel generator subsystems. Further, we study the effect of surveillance test and the type of test on the reliability. Finally we construct an unavailability model for single diesel generator unit and discuss the findings of the study giving some practical recommendations

  14. Development of reliability program for emergency diesel generators in domestic nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Young Ho; Jung, Hyun Jong; Choi, Kwang Hee; Hong, Seoung Yeul

    2001-01-01

    Surveillance tests of Emergency Diesel Generators (EDGs) in Nuclear Power Plants (NPPs) have been conducted periodically to verify the reliability and integrity of the EDGs, however, it was found that these surveillance methods were so conservative and severe as to accelerate the degradation of the EDGs. Hence, new regulatory guideline, Reg. Guide 1.9 Rev. 3, was established by the U.S. NRC to resolve these problems. But it requires the additional implementation of reliability program of the EDGs to improve the actual reliability of them. In Korea, the EDGs of Yonggwang nuclear units 3 and 4 were the first plant applying new Reg. guide 1.9 rev.3 and implementing EDG reliability program. Furthermore it is expected that new guideline for the EDGs will be applied to other EDGs of Korean NPPs. In this paper, this reliability program is described, and it can be used as a reference for other EDGs in Korean NPPs

  15. Procedure for conducting a human-reliability analysis for nuclear power plants. Final report

    International Nuclear Information System (INIS)

    Bell, B.J.; Swain, A.D.

    1983-05-01

    This document describes in detail a procedure to be followed in conducting a human reliability analysis as part of a probabilistic risk assessment when such an analysis is performed according to the methods described in NUREG/CR-1278, Handbook for Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications. An overview of the procedure describing the major elements of a human reliability analysis is presented along with a detailed description of each element and an example of an actual analysis. An appendix consists of some sample human reliability analysis problems for further study

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

    International Nuclear Information System (INIS)

    Araujo, Jefferson Borges

    1998-01-01

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

  17. Improving nuclear power plant reliability through predictive maintenance

    International Nuclear Information System (INIS)

    Geilhausen, R.; Kunze, U.

    1996-01-01

    Maintenance strategies can be assigned to one of three categories: failure maintenance, periodic maintenance or condition-oriented maintenance. The optimum maintenance scheme can be selected on the basis of a cost-benefit analysis but the safety of life and limb or the political climate for NPP can hardly expressed in numbers. The implementation of preventive maintenance needs two preconditions: high-performance instrumentation in the form of stationary and mobile monitoring systems for the determination of the condition of the nuclear power plant components and provision of a tool that can handle both the organization of the work and the evaluation of the results obtained. (authors)

  18. Estimation of reliability on digital plant protection system in nuclear power plants using fault simulation with self-checking

    International Nuclear Information System (INIS)

    Lee, Jun Seok; Kim, Suk Joon; Seong, Poong Hyun

    2004-01-01

    Safety-critical digital systems in nuclear power plants require high design reliability. Reliable software design and accurate prediction methods for the system reliability are important problems. In the reliability analysis, the error detection coverage of the system is one of the crucial factors, however, it is difficult to evaluate the error detection coverage of digital instrumentation and control system in nuclear power plants due to complexity of the system. To evaluate the error detection coverage for high efficiency and low cost, the simulation based fault injections with self checking are needed for digital instrumentation and control system in nuclear power plants. The target system is local coincidence logic in digital plant protection system and a simplified software modeling for this target system is used in this work. C++ based hardware description of micro computer simulator system is used to evaluate the error detection coverage of the system. From the simulation result, it is possible to estimate the error detection coverage of digital plant protection system in nuclear power plants using simulation based fault injection method with self checking. (author)

  19. Method of reliability allocation based on fault tree analysis and fuzzy math in nuclear power plants

    International Nuclear Information System (INIS)

    Chen Zhaobing; Deng Jian; Cao Xuewu

    2005-01-01

    Reliability allocation is a kind of a difficult multi-objective optimization problem. It can not only be applied to determine the reliability characteristic of reactor systems, subsystem and main components but also be performed to improve the design, operation and maintenance of nuclear plants. The fuzzy math known as one of the powerful tools for fuzzy optimization and the fault analysis deemed to be one of the effective methods of reliability analysis can be applied to the reliability allocation model so as to work out the problems of fuzzy characteristic of some factors and subsystem's choice respectively in this paper. Thus we develop a failure rate allocation model on the basis of the fault tree analysis and fuzzy math. For the choice of the reliability constraint factors, we choose the six important ones according to practical need for conducting the reliability allocation. The subsystem selected by the top-level fault tree analysis is to avoid allocating reliability for all the equipment and components including the unnecessary parts. During the reliability process, some factors can be calculated or measured quantitatively while others only can be assessed qualitatively by the expert rating method. So we adopt fuzzy decision and dualistic contrast to realize the reliability allocation with the help of fault tree analysis. Finally the example of the emergency diesel generator's reliability allocation is used to illustrate reliability allocation model and improve this model simple and applicable. (authors)

  20. Industrial plant electrical systems: Simplicity, reliability, cost savings, redundancies

    International Nuclear Information System (INIS)

    Silvestri, A.; Tommazzolli, F.; Pavia Univ.

    1992-01-01

    This article represents a compact but complete design and construction manual for industrial plant electrical systems. It is to be used by design engineers having prior knowledge of local power supply routes and voltages and regards principally the optimum choice of internal distribution systems which can be radial or single, double ringed or with various network configurations, and with single or multiple supplies, and many or few redundancies. After giving guidelines on the choosing of these options, the manual deals with problematics relevant to suitable cable sizing. A cost benefit benefit analysis method is suggested for the choice of the number of redundancies. Recommendations are given for the choice of transformers, motorized equipment, switch boards and circuit breakers. Reference is made to Italian electrical safety and building codes

  1. Medicinal plants in the treatment of cancer

    Directory of Open Access Journals (Sweden)

    Nenad M. Zlatić

    2015-07-01

    Full Text Available The purpose of this paper is to present a review of highly developed medicinal usages of plants in the treatment of cancer. In the last decades, the cancer treatment has been included in this range of plant use, due to plant active substances. Active substances or secondary metabolites are generally known for their widespread application. When it comes to the cancer treatment, these substances affect the uncontrolled cell division. Therefore, the plants which are the source of these substances are proved to be irreplaceable in this field of medicine. This paper deals with some of the most significant plants well known for their multiple aspects of beneficial medicinal influence. The group of the plants described is comprised of the following species: Taxus brevifolia (Taxaceae, Catharanthus roseus (Apocynaceae, Podophyllum peltatum (Berberidaceae, Camptotheca accuminata (Cornaceae, and Cephalotaxus harringtonia (Cephalotaxaceae. The comprehensive description of the plants in this paper includes the morphological characteristics, the features and the representation of the molecular structures of active substances, the particular influence that these active substances have and the general importance of the substances as seen from the aspect of cancer treatment mostly with reference to the impacts on cell cycle.

  2. Conceptual Software Reliability Prediction Models for Nuclear Power Plant Safety Systems

    International Nuclear Information System (INIS)

    Johnson, G.; Lawrence, D.; Yu, H.

    2000-01-01

    The objective of this project is to develop a method to predict the potential reliability of software to be used in a digital system instrumentation and control system. The reliability prediction is to make use of existing measures of software reliability such as those described in IEEE Std 982 and 982.2. This prediction must be of sufficient accuracy to provide a value for uncertainty that could be used in a nuclear power plant probabilistic risk assessment (PRA). For the purposes of the project, reliability was defined to be the probability that the digital system will successfully perform its intended safety function (for the distribution of conditions under which it is expected to respond) upon demand with no unintended functions that might affect system safety. The ultimate objective is to use the identified measures to develop a method for predicting the potential quantitative reliability of a digital system. The reliability prediction models proposed in this report are conceptual in nature. That is, possible prediction techniques are proposed and trial models are built, but in order to become a useful tool for predicting reliability, the models must be tested, modified according to the results, and validated. Using methods outlined by this project, models could be constructed to develop reliability estimates for elements of software systems. This would require careful review and refinement of the models, development of model parameters from actual experience data or expert elicitation, and careful validation. By combining these reliability estimates (generated from the validated models for the constituent parts) in structural software models, the reliability of the software system could then be predicted. Modeling digital system reliability will also require that methods be developed for combining reliability estimates for hardware and software. System structural models must also be developed in order to predict system reliability based upon the reliability

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  4. Water chemistry - one of the key technologies for safe and reliable nuclear power plant operation

    International Nuclear Information System (INIS)

    Uchida, S.; Otoha, K.; Ishigure, K.

    2006-01-01

    Full text: Full text: Water chemistry control is one of the key technologies to establish safe and reliable operation of nuclear power plants. Continuous and collaborative efforts of plant manufacturers and plant operator utilities have been focused on optimal water chemistry control, for which, a trio of requirements for water chemistry, a) better reliability of reactor structures and fuels, b) lower occupational exposure, and c) fewer radwaste sources, should be simultaneously satisfied. The research committee related to water chemistry of the Atomic Energy Society of Japan has played important roles to enhance improvement in water chemistry control, to share knowledge and experience with water chemistry among plant operators and manufacturers, to establish common technological bases for plant water chemistry and then to transfer them to the next generation related to water chemistry. Furthermore, the committee has tried to contribute to arranging R and D proposals for further improvement in water chemistry control through road map planning

  5. On the reliability of steam generator performance at nuclear power plants with WWER type reactors

    International Nuclear Information System (INIS)

    Styrikovich, M.A.; Margulova, T.Kh.

    1974-01-01

    The problem of ensuring reliable operation of steam generators in a nuclear power plant with a water-cooled, water-moderated reactor (WWER) was studied. At a nuclear power plant with a vertical steam generator (specifically, a Westinghouse product) the steam generator tubes were found to have been penetrated. Shutdown was due to corrosion disintegration of the austenitic stainless steel, type 18/8, used as pipe material for the heater surface. The corrosion was the result of the action of chlorine ions concentrated in the moisture contained in the iron oxide films deposited in low parts of the tube bundle, directly at the tube plate. Blowing through did not ensure complete removal of the film, and in some cases the construction features of the steam generator made removal of the film practically impossible. Replacement of type 18/8 stainless steel by other construction material, e.g., Inconel, did not give good results. To ensure reliable operation of vertical steam generators in domestic practice, the generators are designed without a low tube plate (a variant diagram of the vertical steam generator of such construction for the water-cooled, water-moderated reactor 1000 is presented). When low tube plates are used the film deposition is intolerable. For organization of a non-film regime a complex treatment of the feed water is used, in which the amount of complexion is calculated from the stoichmetric ratios with the composition of the feed water. It is noted that, if 100% condensate purification is used with complexon processing of the feed water to the generator, we can calculate the surface of the steam-generator heater without considering the outer placement on the tubes. In this the cost of the steam generator and all the nuclear power plants with WWER type reactors is decreased even with installation of a 100% condensate purification. It is concluded that only simultaneous solution of construction and water-regime problems will ensure relaible operation of

  6. A study in the reliability analysis method for nuclear power plant structures (I)

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Byung Hwan; Choi, Seong Cheol; Shin, Ho Sang; Yang, In Hwan; Kim, Yi Sung; Yu, Young; Kim, Se Hun [Seoul, Nationl Univ., Seoul (Korea, Republic of)

    1999-03-15

    Nuclear power plant structures may be exposed to aggressive environmental effects that may cause their strength and stiffness to decrease over their service life. Although the physics of these damage mechanisms are reasonably well understood and quantitative evaluation of their effects on time-dependent structural behavior is possible in some instances, such evaluations are generally very difficult and remain novel. The assessment of existing steel containment in nuclear power plants for continued service must provide quantitative evidence that they are able to withstand future extreme loads during a service period with an acceptable level of reliability. Rational methodologies to perform the reliability assessment can be developed from mechanistic models of structural deterioration, using time-dependent structural reliability analysis to take loading and strength uncertainties into account. The final goal of this study is to develop the analysis method for the reliability of containment structures. The cause and mechanism of corrosion is first clarified and the reliability assessment method has been established. By introducing the equivalent normal distribution, the procedure of reliability analysis which can determine the failure probabilities has been established. The influence of design variables to reliability and the relation between the reliability and service life will be continued second year research.

  7. Treatment of wastewaters from manufactured gas plants

    Energy Technology Data Exchange (ETDEWEB)

    Cocheci, V.; Bogatu, C.; Radovan, C. [Technical University of Timisoara, Timisoara (Romania)

    1995-12-31

    The treatment of wastewaters with high concentrations of organic compounds often represents a difficult problem. In some cases, for the destruction and removal of toxic compounds using processes like biological and chemical oxidation were proposed. Wastewaters from manufactured gas plants contain high concentrations of organic pollutants and ammonia. In this paper a technology for the treatment of these wastewaters is proposed. The experiments were realized with wastewaters from two Romanian manufactured gas plants. The process consists of the following steps: polycondensation-settling-stripping-biological treatment-electrocoagulation-electrochemical oxidation, or chemical oxidation. 6 refs., 4 tabs.

  8. 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)

  9. The contribution of quality assurance to safety and reliability in nuclear power plants

    International Nuclear Information System (INIS)

    Raisic, N.

    1978-01-01

    The potential contribution of quality assurance to nuclear power plant safety and reliability is analysed. An attempt is made to establish a relationship between quality and reliability. The reliability may be expressed in quantitative terms as ''the probability that an item will perform a required function for a stated period of time''. Quality, however, cannot be expressed in simple quantitative terms but only as a set of required properties which an item should have for a specific application. The achievement of quality and additional reliability objectives is a task of project activities such as design, construction, installation, operation, etc. The elements of a quality assurance system and its functions in nuclear power projects are presented in some detail. Confidence in plant quality, which should be a basis for the regulatory body issuing the construction permit or operation licence, should be based on the capability of quality assurance activities to prevent errors and correct deficiencies in nuclear power plants. An analysis is made of those errors in plant design, manufacture, construction and operation which contribute most frequently to plant outages. It is concluded that these errors can be avoided or corrected by strict adherence to quality assurance principles and by the efficient functioning of quality assurance systems. In fact, quality assurance may be considered an effective defence against common cause failures originating in errors in the design, manufacture, installation or operation of a nuclear power plant

  10. In-plant application of industry experience to enhance human reliability

    International Nuclear Information System (INIS)

    Hannaman, G.W.; Singh, A.

    1993-01-01

    This paper describes the way that modern data-base computer tools can enhance the ability to collect, organize, evaluate, and use industry experience. By combining the computer tools with knowledge from human reliability assessment tools, data, and frameworks, the data base can become a tool for collecting and assessing the lessons learned from past events. By integrating the data-base system with plant risk models, engineers can focus on those activities that can enhance over-all system reliability. The evaluation helps identify technology and tools to reduce human errors during operations and maintenance. Learning from both in-plant and industry experience can help enhance safety and reduce the cost of plant operations. Utility engineers currently assess events that occur in nuclear plants throughout the world for in-plant applicability. Established computer information networks, documents, bulletins, and other information sources provide a large number of event descriptions to help individual plants benefit from this industry experience. The activities for coordinating reviews of event descriptions from other plants for in-plant applications require substantial engineering time to collect, organize, evaluate, and apply. Data-base tools can help engineers efficiently handle and sort the data so that they can concentrate on understanding the importance of the event, developing cost-effective interventions, and communicating implementation plans for plant improvement. An Electric Power Research Institute human reliability project has developed a classification system with modern data-base software to help engineers efficiently process, assess, and apply information contained in the events to enhance plant operation. Plant-specific classification of industry experience provides a practical method for efficiently taking into account industry when planning maintenance activities and reviewing plant safety

  11. Technology development of maintenance optimization and reliability analysis for safety features in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Woon; Choi, Seong Soo; Lee, Dong Gue; Kim, Young Il

    1999-12-01

    The reliability data management system (RDMS) for safety systems of PHWR type plants has been developed and utilized in the reliability analysis of the special safety systems of Wolsong Unit 1,2 with plant overhaul period lengthened. The RDMS is developed for the periodic efficient reliability analysis of the safety systems of Wolsong Unit 1,2. In addition, this system provides the function of analyzing the effects on safety system unavailability if the test period of a test procedure changes as well as the function of optimizing the test periods of safety-related test procedures. The RDMS can be utilized in handling the requests of the regulatory institute actively with regard to the reliability validation of safety systems. (author)

  12. The development of specific reliability database for a Korean Nuclear Power Plant

    International Nuclear Information System (INIS)

    Park, S.K.; Park, B.L.; Kim, M.R.; Jeong, B.H.; Kwon, J.J.

    2001-01-01

    The object of this study is to develop reliability database for PSA application such as failure rate for safety related components, test and maintenance unavailability and common cause failure factors except for initiating event frequencies during the period of 10 years from 1990 to 1999. In this study we developed plant-specific reliability database for PSA (Probabilistic Safety Assessment) application and compared it with generic reliability database developed in the US such as EPRI-URD, IEEE-500, NUCLARR etc, in the component type basis. We have found that there are some general differences in the component failure rate and test and maintenance unavailability. We described the characteristics of differences for some important component types. We also analyzed the reasons for the differences in the aspect of maintenance terms such as maintenance policy and maintenance practice. We found that maintenance terms are important factors for the numbers of plant-specific reliability database. (author)

  13. Reliability programs for nuclear power plants. Regulatory standard S-98 revision 1

    International Nuclear Information System (INIS)

    2005-07-01

    The purpose of this regulatory standard is to help assure, in accordance with the purpose of the Nuclear Safety and Control Act (NSCA), that a licensee who constructs or operates a nuclear power plant (NPP) develops and implements a reliability program that assures that the systems important to safety at the plant can and will meet their defined design and performance specifications at acceptable levels of reliability throughout the lifetime of the facility. This regulatory standard describes the requirements of a reliability program for a nuclear power plant. The licensee shall implement the requirements described in this regulatory standard when a condition of a licence or other legally enforceable instrument so requires.(author)

  14. Reliability analysis of the automatic control of the A-1 power plant coolant temperature

    International Nuclear Information System (INIS)

    Kuklik, B.; Semerad, V.; Chylek, Z.

    Reliability analysis of the automatic control of the A-1 reactor coolant temperature is performed taking into account the effect of both the dependent failures and the routine maintenance of control system components. In a separate supplement, reliability analysis is reported of coincidence systems of the A-1 power plant reactor. Both safe and unsafe failures are taken into consideration as well as the effect of maintenance of the respective branch elements

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

    Directory of Open Access Journals (Sweden)

    A. L. Starzhinskij

    2015-01-01

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

  16. Reliability of assessment of adherence to an antimicrobial treatment guideline

    NARCIS (Netherlands)

    Mol, PGM; Gans, ROB; Panday, PVN; Degener, JE; Laseur, M; Haaijer-Ruskamp, FM

    Assessment procedures for adherence to a guideline must be reliable and credible. The aim of this study was to explore the reliability of assessment of adherence, taking account of the professional backgrounds of the observers. A secondary analysis explored the impact of case characteristics on

  17. Performance of nuclear power plants and analysis of some factors affecting their operational reliability and economy

    International Nuclear Information System (INIS)

    Kozak, M.; Havel, S.

    1989-09-01

    In Czechoslovakia, there are eight WWER 440 type reactors in operation at present. Since their introduction into operation, nuclear power plants in Czechoslovakia have exhibited high reliability. In the paper, total parameters of reliability with an analysis of causes affecting negatively their annual utilization are presented. Existence of a computerized information system for acquisition, recording and evaluation of reliability-significant data from operation and its feedback to designers and manufacturers of nuclear power plant equipment and components is a basic requirement of a systematic assurance of the needed level of nuclear power plant reliability. The information system is used simultaneously also for realistic evaluation of aging of equipment and systems. Analysis of the state of equipment is important mainly in the final stage of the NPP during consideration of further extension of its service life. Environmental effects of the Czechoslovak NPPs are very low (favourable). It follows from comparison of annual dose equivalents of the Czechoslovak NPPs operational personnel with the foreign NPPs that the values recorded in Czechoslovakia belong to the lowest ones. In conclusion, some ways of assurance of operational safety and reliability of the Czechoslovak nuclear power plants including the role of the State regulatory body are briefly discussed. (author). 3 tabs

  18. Plant lifetime reliability and risk: Addressing today's strategies for making tomorrow's decisions

    International Nuclear Information System (INIS)

    Boccio, J.L.

    1986-01-01

    This paper presents an overview of some of the research projects, conducted for the US Nuclear Regulatory Commission (NRC) that deal with the question: How can an acceptable level of risk of a nuclear power plant be maintained throughout its design life? With a viewpoint that life extension planning for a plant can be viewed as a long-range, strategic maintenance program, the products of this research are discussed from the perspective of being elements that can tie day-to-day, plant operational tactical decisions on component/system reliability with long-range strategic maintenance goals. A common factor in addressing issues associated with design life and life extension is the issue of component aging and the reliability implications of aging. A time-dependent reliability model is described which contains some of the requisite ingredients and is built on a framework from which the component aging/component reliability issue can be addressed. By way of select examples, the additional work needed to further address plant lifetime reliability and risk is indicated

  19. Water chemistry technology. One of the key technologies for safe and reliable nuclear power plant operation

    International Nuclear Information System (INIS)

    Uchida, Shunsuke; Katsumura, Yosuke

    2013-01-01

    Water chemistry control is one of the key technologies to establish safe and reliable operation of nuclear power plants. Continuous and collaborative efforts of plant manufacturers and plant operator utilities have been focused on optimal water chemistry control, for which, a trio of requirements for water chemistry should be simultaneously satisfied: (1) better reliability of reactor structures and fuel rods; (2) lower occupational exposure and (3) fewer radwaste sources. Various groups in academia have carried out basic research to support the technical bases of water chemistry in plants. The Research Committee on Water Chemistry of the Atomic Energy Society of Japan (AESJ), which has now been reorganized as the Division of Water Chemistry (DWC) of AESJ, has played important roles to promote improvements in water chemistry control, to share knowledge about and experiences with water chemistry control among plant operators and manufacturers and to establish common technological bases for plant water chemistry and then to transfer them to the next generation of plant workers engaged in water chemistry. Furthermore, the DWC has tried and succeeded arranging R and D proposals for further improvement in water chemistry control through roadmap planning. In the paper, major achievements in plant technologies and in basic research studies of water chemistry in Japan are reviewed. The contributions of the DWC to the long-term safe management of the damaged reactors at the Fukushima Daiichi Nuclear Power Plant until their decommissioning are introduced. (author)

  20. Reliability study: steam generation and distribution system, Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Baker, F.E.; Davis, E.L.; Dent, J.T.; Walters, D.E.; West, R.M.

    1982-10-01

    A reliability study for determining the ability of the Steam Generation and Distribution System to provide reliable and adequate service through the year 2000 has been completed. This study includes an evaluation of the X-600 Steam Plant and the steam distribution system. The Steam Generation and Distribution System is in good overall condition, but to maintain this condition, the reliability study team made twelve recommendations. Eight of the recommendations are for repair or replacement of existing equipment and have a total estimated cost of $540,000. The other four recommendations are for additional testing, new procedure implementation, or continued investigations

  1. Reliability analysis of microcomputer boards and computer based systems important to safety of nuclear plants

    International Nuclear Information System (INIS)

    Shrikhande, S.V.; Patil, V.K.; Ganesh, G.; Biswas, B.; Patil, R.K.

    2010-01-01

    Computer Based Systems (CBS) are employed in Indian nuclear plants for protection, control and monitoring purpose. For forthcoming CBS, Reactor Control Division has designed and developed a new standardized family of microcomputer boards qualified to stringent requirements of nuclear industry. These boards form the basic building blocks of CBS. Reliability analysis of these boards is being carried out using analysis package based on MIL-STD-217Plus methodology. The estimated failure rate values of these standardized microcomputer boards will be useful for reliability assessment of these systems. The paper presents reliability analysis of microcomputer boards and case study of a CBS system built using these boards. (author)

  2. Human reliability analysis of performing tasks in plants based on fuzzy integral

    International Nuclear Information System (INIS)

    Washio, Takashi; Kitamura, Yutaka; Takahashi, Hideaki

    1991-01-01

    The effective improvement of the human working conditions in nuclear power plants might be a solution for the enhancement of the operation safety. The human reliability analysis (HRA) gives a methodological basis of the improvement based on the evaluation of human reliability under various working conditions. This study investigates some difficulties of the human reliability analysis using conventional linear models and recent fuzzy integral models, and provides some solutions to the difficulties. The following practical features of the provided methods are confirmed in comparison with the conventional methods: (1) Applicability to various types of tasks (2) Capability of evaluating complicated dependencies among working condition factors (3) A priori human reliability evaluation based on a systematic task analysis of human action processes (4) A conversion scheme to probability from indices representing human reliability. (author)

  3. Treatment of some power plant waters

    International Nuclear Information System (INIS)

    Konecny, C.; Vanura, P.; Franta, P.; Marhol, M.; Tejnecky, M.; Fidler, J.

    1987-01-01

    Major results are summed up obtained in 1986 in the development of techniques for the treatment of coolant in the fuel transport and storage tank, of reserve coolant in the primary circuit and of waste water from the special nuclear power plant laundries, containing new washing agent Alfa-DES. A service test of the filter filled with Czechoslovak-made cation exchanger Ostion KSN in the boric acid concentrate filter station showed that the filter can be used in some technological circuits of nuclear power plants. New decontamination agents are also listed introduced in production in Czechoslovakia for meeting the needs of nuclear power plants. (author). 6 refs

  4. Modification of water treatment plant at Heavy Water Plant (Kota)

    International Nuclear Information System (INIS)

    Gajpati, C.R.; Shrivastava, C.S.; Shrivastava, D.C.; Shrivastava, J.; Vithal, G.K.; Bhowmick, A.

    2008-01-01

    Heavy Water Production by GS process viz. H 2 S - H 2 O bi-thermal exchange process requires a huge quantity of demineralized (DM) water as a source of deuterium. Since the deuterium recovery of GS process is only 18-19%, the water treatment plant (WTP) was designed and commissioned at Heavy Water Plant (Kota) to produce demineralized water at the rate of 680 m 3 /hr. The WTP was commissioned in 1980 and till 2005; the plant was producing DM water of required quality. It was having three streams of strong cation resin, atmospheric degasser and strong anion exchange resin with co-current regeneration. In 2001 a new concept of layered bed resin was developed and engineered for water treatment plant. The concept was attractive in terms of saving of chemicals and thus preservation of environment. Being an ISO 9000 and ISO 14000 plant, the modification of WTP was executed in 2005 during major turn around. After modification, a substantial amount of acid and alkali is saved

  5. 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

  6. Advancements in valve technology and industry lessons lead to improved plant reliability and cost savings

    International Nuclear Information System (INIS)

    Sharma, V.; Kalsi, M.S.

    2005-01-01

    Plant reliability and safety hinges on the proper functioning of several valves. Recent advancements in valve technology have resulted in new analytical and test methods for evaluating and improving valve and actuator reliability. This is especially significant in critical service applications in which the economic impact of a valve failure on production, outage schedules and consequential damages far surpasses the initial equipment purchase price. This paper presents an overview of recent advances in valve technology driven by reliability concerns and cost savings objectives without comprising safety in the Nuclear Power Industry. This overview is based on over 27 years of experience in supporting US and International nuclear power utilities, and contributing to EPRI, and NSSS Owners' Groups in developing generic models/methodologies to address industry wide issues; performing design basis reviews; and implementing plant-wide valve reliability improvement programs. Various analytical prediction software and hardware solutions and training seminars are now available to implement valve programs covering power plants' lifecycle from the construction phase through life extension and power up rate. These tools and methodologies can enhance valve-engineering activities including the selection, sizing, proper application, condition monitoring, failure analysis, and condition based maintenance optimization with a focus on potential bad actors. This paper offers two such examples, the Kalsi Valve and Actuator Program (KVAP) and Check Valve Analysis and Prioritization (CVAP) [1-3, 8, 9, 11-13]. The advanced, validated torque prediction models incorporated into KVAP software for AOVs and MOVs have improved reliability of margin predictions and enabled cost savings through elimination of unwarranted equipment modifications. CVAP models provides a basis to prioritize the population of valves recommended for preventive maintenance, inspection and/or modification, allowing

  7. A Chronological Reliability Model to Assess Operating Reserve Allocation to Wind Power Plants: Preprint

    International Nuclear Information System (INIS)

    Milligan, M. R.

    2001-01-01

    As the use of wind power plants increases worldwide, it is important to understand the effect these power sources have on the operations of the grid. This paper focuses on the operating reserve impact of wind power plants. Many probabilistic methods have been applied to power system analysis, and some of these are the basis of reliability analysis. This paper builds on a probabilistic technique to allocate the operating reserve burden among power plants in the grid. The method was originally posed by Strbac and Kirschen[1] and uses an allocation that prorates the reserve burden based on expected energy not delivered. Extending this method to include wind power plants allows the reserve burden to be allocated among different plants using the same method, yet incorporates information about the intermittent nature of wind power plants

  8. 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)

  9. Construction of Industrial Electron Beam Plant for Wastewater Treatment

    International Nuclear Information System (INIS)

    Han, B.; Kim, J.; Kim, Y.; Kim, S.; Lee, M.; Choi, J.; Ahn, S.; Makarov, I.E.; Ponomarev, A.V.

    2004-01-01

    A pilot plant for treating 1,000 m3/day of dyeing wastewater with e-beam has been constructed and operated since 1998 in Daegu, Korea together with the biological treatment facility. The wastewater from various stages of the existing purification process has been treated with electron beam in this plant, and it gave rise to elaborate the optimal technology of the electron beam treatment of wastewater with increased reliability at instant changes in the composition of wastewater. Installation of the e-beam pilot plant resulted in decolorizing and destructive oxidation of organic impurities in wastewater, appreciable to reduction of chemical reagent consumption, in reduction of the treatment time, and in increase in flow rate limit of existing facilities by 30-40%. Industrial plant for treating 10,000 m3/day, based upon the pilot experimental result, is under construction and will be finished by 2005. This project is supported by the International Atomic Energy Agency (IAEA) and Korean Government

  10. THE ANALYSIS OF STRUCTURAL RELIABILITY OF THE MAIN ELECTRIC CONNECTION CIRCUITS OF NUCLEAR POWER PLANTS

    Directory of Open Access Journals (Sweden)

    M. A. Korotkevich

    2017-01-01

    Full Text Available The reliability of the main circuit of electrical connections at a nuclear electric power plant that has two units with a capacity of 1,200 MW each has been determined. Reliability, economical, maneuverable properties of the atomic power plant under study are largely determined by its main circuit, so the choice of the circuit for the design and its status in the process of operation occur to be critical objectives. Main electrical connection circuits in nuclear electric power plants are selected on the basis of the schematic networks of the energy system and the land attached to the plant. The circuit of the connection of a nuclear power plant to the grid in the original normal operating modes at all stages of the construction of such a plant should provide the outcome of the full added capacity of a nuclear power plant and the preservation of its stability in the power system without the influence of the emergency system automatics when any outgoing transmission line is disabled. When selecting the main circuit the individual capacity of the installed units and their number are taken into account as well as the order of development of the plant and power supply system; the voltage on which the power of a plant is delivered; a shortcircuit current for switchgear high voltage and the need for their limitation by circuit means; the most power that can be lost when damage to any switch. A model of reliability of the main circuit of electrical connections is designed to detect all types of accidents that are possible at the coincidence of failures of elements with the repair and operational modes that differs in composition and damageability of the equipment, as well as under conditions of the development of accidents due to failure of operation of devices of relay protection and automation.

  11. Proceedings of the international conference on nuclear power plant aging, availability factor and reliability analysis

    International Nuclear Information System (INIS)

    Goel, V.S.

    1985-01-01

    This book presents the papers given at a conference on nuclear power plant life extension. Topics considered at the conference included availability, accelerated aging techniques, the qualification of electrical equipment, probabilistic risk assessment, reactor maintenance, outages, reliability, computer-aided design, seismic effects, mechanical vibrations, fatigue monitoring, steam generators, and materials degradation by aging and embrittlement

  12. Quality assurance/quality control, reliability and availability of nuclear power plants

    International Nuclear Information System (INIS)

    Kueffer, K.

    1981-01-01

    In a first part this lectures will present a survey on nuclear power production and plant performance in the Western World and discuss key parameters such as load factors and non-availability. Some main reasons for reliable performance of nuclear power plants are given. The second part of this lecture deals with the question how quality assurance and quality control measures do directly influence plant reliability, availability and, thus, economy. Derived from worldwide experience gained from operating nuclear power plants, it may be concluded that the implementation of an overall quality assurance programme does not only satisfy safety requirements set forth by the nuclear regulatory bodies, but has also a considerable impact on plant reliability and availability. A positive effect on these figures will be achieved if the established quality assurance programme provides for a coordinated approach to all activities affecting quality. It is discussed how the quality of a product should be controlled and what kind of quality assurance measures by performed examples are given to demonstrate that the expenditure for maintenance work on components will decrease if planned and systematic quality assurance actions have been implemented during all procurement stages. (orig./RW)

  13. Trade-offs in size, quantity and reliability of generalized nuclear power plants

    International Nuclear Information System (INIS)

    Hill, D.; Mubayi, V.

    1987-01-01

    In the 1960's and 1970's, there was rapid growth in the size of newly started nuclear power plants because of the anticipated advantages of increasing scale. Any such advantages were overwhelmed by the complications that arose with long construction times, and attention is now being given to a ''second generation'' of smaller plants of new design. Providing the same production capacity will require larger numbers of plants if they are smaller. Although it seems to have received little attention previously, there should be compensating economies due to ''learning curve'' effects in the manufacture of multiple units of standardized designs (Hill 1983). Moreover, the use of a large number of smaller units increases the overall system reliability. On balance, however, it is not clear how scale, quantity, and reliability considerations interact to determine optimal plant size. The purpose of this paper is to begin examining the size-quantity tradeoff taking into account scale effects, the manufacturing learning curve, plant availability, and system reliability

  14. Study on evaluation index system of operational performance of municipal wastewater treatment plants in China

    Science.gov (United States)

    Xiaoxin, Zhang; Jin, Huang; Ling, Lin; Yan, Li

    2018-05-01

    According to the undeveloped evaluation method for the operational performance of the municipal wastewater treatment plants, this paper analyzes the policies related to sewage treatment industry based on the investigation of the municipal wastewater treatment plants. The applicable evaluation method for the operational performance was proposed from environmental protection performance, resources and energy consumption, technical and economic performance, production management and main equipment, providing a reliable basis for scientific evaluation of the operation as well as improving the operational performance of municipal wastewater treatment plant.

  15. Beliefs concerning the reliability of nuclear power plant in-service inspections

    International Nuclear Information System (INIS)

    Kettunen, J.

    1997-01-01

    The aim of the study was to investigate belief systems held by the officials responsible for the planning and supervision of NDT operations within the Finnish nuclear industry. They were asked to express their opinions on (1) the reliability of NDT methods in general, (2) the factors influencing the reliability of in-service inspections, and (3) the degree of reliability of the current inspections operations conducted by means of NDT methods in the Finnish nuclear power plants. Another goal of the study was to assess the adequacy of officials' beliefs (or belief systems). The research data was collected by interviewing representatives from Finnish power companies (Imatran Voima Oy and Teollisuuden Voima Oy), independent inspection organisations, and the Finnish Centre for Radiation and Nuclear Safety (STUK). The adequacy of the beliefs expressed was assessed by means of the results obtained from international NDT reliability studies and on the basis of interviewees' own justification. (refs.)

  16. Reliability analyses of safety systems for WWER-440 nuclear power plants

    International Nuclear Information System (INIS)

    Dusek, J.; Hojny, V.

    1985-01-01

    The UJV in Rez near Prague studied the reliability of the system of emergency core cooling and of the system for suppressing pressure in the sealed area of the nuclear power plant in the occurrence of a loss-of-coolant accident. The reliability of the systems was evaluated by failure tree analysis. Simulation and analytical calculation programs were developed and used for the reliability analysis. The results are briefly presented of the reliability analyses of the passive system for the immediate short-term flooding of the reactor core, of the active low-pressure system of emergency core cooling, the spray system, the bubble-vacuum system and the system of emergency supply of the steam generators. (E.S.)

  17. Markov modeling and reliability analysis of urea synthesis system of a fertilizer plant

    Science.gov (United States)

    Aggarwal, Anil Kr.; Kumar, Sanjeev; Singh, Vikram; Garg, Tarun Kr.

    2015-12-01

    This paper deals with the Markov modeling and reliability analysis of urea synthesis system of a fertilizer plant. This system was modeled using Markov birth-death process with the assumption that the failure and repair rates of each subsystem follow exponential distribution. The first-order Chapman-Kolmogorov differential equations are developed with the use of mnemonic rule and these equations are solved with Runga-Kutta fourth-order method. The long-run availability, reliability and mean time between failures are computed for various choices of failure and repair rates of subsystems of the system. The findings of the paper are discussed with the plant personnel to adopt and practice suitable maintenance policies/strategies to enhance the performance of the urea synthesis system of the fertilizer plant.

  18. Information flow a data bank preparation in nuclear power plant reliability information system

    International Nuclear Information System (INIS)

    Kolesa, K.; Vejvodova, I.

    1983-01-01

    In the year 1981 the reliability information system for nuclear power plants (ISS-JE) was established. The objective of the system is to make a statistical evaluation of the operation of nuclear power plants and to obtain information on the reliability of the equipment of nuclear power plants and the transmission of this information to manufacturers with the aim of inducing them to take corrective measures. The HP 1000 computer with the data base system IMAGE 100 is used which allows to process single queries and periodical outputs. The content of periodical outputs designed for various groups of subcontractors is briefly described and trends of the further development of the system indicated. (Ha)

  19. Operation reliability analysis of independent power plants of gas-transmission system distant production facilities

    Science.gov (United States)

    Piskunov, Maksim V.; Voytkov, Ivan S.; Vysokomornaya, Olga V.; Vysokomorny, Vladimir S.

    2015-01-01

    The new approach was developed to analyze the failure causes in operation of linear facilities independent power supply sources (mini-CHP-plants) of gas-transmission system in Eastern part of Russia. Triggering conditions of ceiling operation substance temperature at condenser output were determined with mathematical simulation use of unsteady heat and mass transfer processes in condenser of mini-CHP-plants. Under these conditions the failure probability in operation of independent power supply sources is increased. Influence of environmental factors (in particular, ambient temperature) as well as output electric capability values of power plant on mini-CHP-plant operation reliability was analyzed. Values of mean time to failure and power plant failure density during operation in different regions of Eastern Siberia and Far East of Russia were received with use of numerical simulation results of heat and mass transfer processes at operation substance condensation.

  20. Scapula Fractures: Interobserver Reliability of Classification and Treatment

    NARCIS (Netherlands)

    Neuhaus, Valentin; Bot, Arjan G. J.; Guitton, Thierry G.; Ring, David C.; Abdel-Ghany, Mahmoud I.; Abrams, Jeffrey; Abzug, Joshua M.; Adolfsson, Lars E.; Balfour, George W.; Bamberger, H. Brent; Barquet, Antonio; Baskies, Michael; Batson, W. Arnold; Baxamusa, Taizoon; Bayne, Grant J.; Begue, Thierry; Behrman, Michael; Beingessner, Daphne; Biert, Jan; Bishop, Julius; Alves, Mateus Borges Oliveira; Boyer, Martin; Brilej, Drago; Brink, Peter R. G.; Brunton, Lance M.; Buckley, Richard; Cagnone, Juan Carlos; Calfee, Ryan P.; Campinhos, Luiz Augusto B.; Cassidy, Charles; Catalano, Louis; Chivers, Karel; Choudhari, Pradeep; Cimerman, Matej; Conflitti, Joseph M.; Costanzo, Ralph M.; Crist, Brett D.; Cross, Brian J.; Dantuluri, Phani; Darowish, Michael; de Bedout, Ramon; DeCoster, Thomas; Dennison, David G.; DeNoble, Peter H.; DeSilva, Gregory; Dienstknecht, Thomas; Duncan, Scott F.; Duralde, Xavier A.; Durchholz, Holger; Egol, Kenneth; Ekholm, Carl; Elias, Nelson; Erickson, John M.; Esparza, J. Daniel Espinosa; Fernandes, C. H.; Fischer, Thomas J.; Fischmeister, Martin; Forigua Jaime, E.; Getz, Charles L.; GIlbert, Richard S.; Giordano, Vincenzo; Glaser, David L.; Gosens, Taco; Grafe, Michael W.; Filho, Jose Eduardo Grandi Ribeiro; Gray, Robert R. L.; Gulotta, Lawrence V.; Gummerson, Nigel William; Hammerberg, Eric Mark; Harvey, Edward; Haverlag, R.; Henry, Patrick D. G.; Hobby, Jonathan L.; Hofmeister, Eric P.; Hughes, Thomas; Itamura, John; Jebson, Peter; Jenkinson, Richard; Jeray, Kyle; Jones, Christopher M.; Jones, Jedediah; Jubel, Axel; Kaar, Scott G.; Kabir, K.; Kaplan, F. Thomas D.; Kennedy, Stephen A.; Kessler, Michael W.; Kimball, Hervey L.; Kloen, Peter; Klostermann, Cyrus; Kohut, Georges; Kraan, G. A.; Kristan, Anze; Loebenberg, Mark I.; Malone, Kevin J.; Marsh, L.; Martineau, Paul A.; McAuliffe, John; McGraw, Iain; Mehta, Samir; Merchant, Milind; Metzger, Charles; Meylaerts, S. A.; Miller, Anna N.; Wolf, Jennifer Moriatis; Murachovsky, Joel; Murthi, Anand; Nancollas, Michael; Nolan, Betsy M.; Omara, Timothy; Omid, Reza; Ortiz, Jose A.; Overbeck, Joachim P.; Castillo, Alberto Pérez; Pesantez, Rodrigo; Polatsch, Daniel; Porcellini, G.; Prayson, Michael; Quell, M.; Ragsdell, Matthew M.; Reid, James G.; Reuver, J. M.; Richard, Marc J.; Richardson, Martin; Rizzo, Marco; Rowinski, Sergio; Rubio, Jorge; Guerrero, Carlos G. Sánchez; Satora, Wojciech; Schandelmaier, Peter; Scheer, Johan H.; Schmidt, Andrew; Schubkegel, Todd A.; Schulte, Leah M.; Schumer, Evan D.; Sears, Benjamin W.; Shafritz, Adam B.; Shortt, Nicholas L.; Siff, Todd; Silva, Dario Mejia; Smith, Raymond Malcolm; Spruijt, Sander; Stein, Jason A.; Pemovska, Emilija Stojkovska; Streubel, Philipp N.; Swigart, Carrie; Swiontkowski, Marc; Thomas, George; Tolo, Eric T.; Turina, Matthias; Tyllianakis, Minos; van den Bekerom, Michel P. J.; van der Heide, Huub; van de Sande, M. A. J.; van Eerten, P. V.; Verbeek, Diederik O. F.; Hoffmann, David Victoria; Vochteloo, A. J. H.; Wagenmakers, Robert; Wall, Christopher J.; Wallensten, Richard; Wascher, Daniel C.; Weiss, Lawrence; Wiater, J. Michael; Wills, Brian P. D.; Wint, Jeffrey; Wright, Thomas; Young, Jason P.; Zalavras, Charalampos; Zura, Robert D.; Zyto, Karol

    2014-01-01

    Objectives:There is substantial variation in the classification and management of scapula fractures. The first purpose of this study was to analyze the interobserver reliability of the OTA/AO classification and the New International Classification for Scapula Fractures. The second purpose was to

  1. Reliability analysis of safety systems of nuclear power plant and utility experience with reliability safeguarding of systems during specified normal operation

    International Nuclear Information System (INIS)

    Balfanz, H.P.

    1989-01-01

    The paper gives an outline of the methods applied for reliability analysis of safety systems in nuclear power plant. The main tasks are to check the system design for detection of weak points, and to find possibilities of optimizing the strategies for inspection, inspection intervals, maintenance periods. Reliability safeguarding measures include the determination and verification of the broundary conditions of the analysis with regard to the reliability parameters and maintenance parameters used in the analysis, and the analysis of data feedback reflecting the plant response during operation. (orig.) [de

  2. STUDY ON WASTE WATER TREATMENT PLANTS

    Directory of Open Access Journals (Sweden)

    Mariana DUMITRU

    2015-04-01

    Full Text Available Biogas is more and more used as an alternative source of energy, considering the fact that it is obtained from waste materials and it can be easily used in cities and rural communities for many uses, between which, as a fuel for households. Biogas has many energy utilisations, depending on the nature of the biogas source and the local demand. Generally, biogas can be used for heat production by direct combustion, electricity production by fuel cells or micro-turbines, Combined Hest and Power generation or as vehicle fuel. In this paper we search for another uses of biogas and Anaerobe Digestion substrate, such as: waste water treatment plants and agricultural wastewater treatment, which are very important in urban and rural communities, solid waste treatment plants, industrial biogas plants, landfill gas recovery plants. These uses of biogas are very important, because the gas emissions and leaching to ground water from landfill sites are serious threats for the environment, which increase more and more bigger during the constant growth of some human communities. That is why, in the developed European countries, the sewage sludge is treated by anaerobe digestion, depending on national laws. In Romania, in the last years more efforts were destined to use anaerobe digestion for treating waste waters and management of waste in general. This paper can be placed in this trend of searching new ways of using with maximum efficiency the waste resulted in big communities.

  3. Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Soares, Wellington Antonio; Marques, Raíssa Oliveira; Silva Júnior, Silvério Ferreira da; Raso, Amanda Laureano

    2017-01-01

    Non-destructive inspection (NDI) is one of the key elements in ensuring quality of engineering systems and their safe use. NDI is a very complex task, during which the inspectors have to rely on their sensory, perceptual, cognitive, and motor skills. It requires high vigilance once it is often carried out on large components, over a long period of time, and in hostile environments and restriction of workplace. A successful NDI requires careful planning, choice of appropriate NDI methods and inspection procedures, as well as qualified and trained inspection personnel. A failure of NDI to detect critical defects in safety-related components of nuclear power plants, for instance, may lead to catastrophic consequences for workers, public and environment. Therefore, ensuring that NDI methods are reliable and capable of detecting all critical defects is of utmost importance. Despite increased use of automation in NDI, human inspectors, and thus human factors, still play an important role in NDI reliability. Human reliability is the probability of humans conducting specific tasks with satisfactory performance. Many techniques are suitable for modeling and analyzing human reliability in NDI of nuclear power plant components. Among these can be highlighted Failure Modes and Effects Analysis (FMEA) and THERP (Technique for Human Error Rate Prediction). The application of these techniques is illustrated in an example of qualitative and quantitative studies to improve typical NDI of pipe segments of a core cooling system of a nuclear power plant, through acting on human factors issues. (author)

  4. Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, Vanderley de; Soares, Wellington Antonio; Marques, Raíssa Oliveira; Silva Júnior, Silvério Ferreira da; Raso, Amanda Laureano, E-mail: vasconv@cdtn.br, E-mail: soaresw@cdtn.br, E-mail: raissaomarques@gmail.com, E-mail: silvasf@cdtn.br, E-mail: amandaraso@hotmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Non-destructive inspection (NDI) is one of the key elements in ensuring quality of engineering systems and their safe use. NDI is a very complex task, during which the inspectors have to rely on their sensory, perceptual, cognitive, and motor skills. It requires high vigilance once it is often carried out on large components, over a long period of time, and in hostile environments and restriction of workplace. A successful NDI requires careful planning, choice of appropriate NDI methods and inspection procedures, as well as qualified and trained inspection personnel. A failure of NDI to detect critical defects in safety-related components of nuclear power plants, for instance, may lead to catastrophic consequences for workers, public and environment. Therefore, ensuring that NDI methods are reliable and capable of detecting all critical defects is of utmost importance. Despite increased use of automation in NDI, human inspectors, and thus human factors, still play an important role in NDI reliability. Human reliability is the probability of humans conducting specific tasks with satisfactory performance. Many techniques are suitable for modeling and analyzing human reliability in NDI of nuclear power plant components. Among these can be highlighted Failure Modes and Effects Analysis (FMEA) and THERP (Technique for Human Error Rate Prediction). The application of these techniques is illustrated in an example of qualitative and quantitative studies to improve typical NDI of pipe segments of a core cooling system of a nuclear power plant, through acting on human factors issues. (author)

  5. Trade-offs in size, quantity and reliability of generalized nuclear power plants: a preliminary assessment

    International Nuclear Information System (INIS)

    Hill, D.

    1985-04-01

    An approximate method is used to estimate the effects of system reliability on optimal nuclear plant size, taking into account also scale factors and manufacturing learning curve slopes. The method is used to estimate the additional effective capability gained by adding units of different sizes to an existing electrical system. The number of additional units proves to be sensitive to forced outrage rate, estimated here from trends in US light-water reactors from 1971 to 1980. The relative cost of added units ranging in size from 200 to 800 MW is determined as a function of the parameters: scale factor and learning curve slope. The results generally corrobate the trends found in an earlier study in which the effect of reliability on required installed capacity was not explicitly considered. Optimal plant size decreases with weaker scale effects and stronger learning curve effects. Reliability considerations further reduce the optimal plant size, but the relative reduction is apparently not as great with steeper learning curves. This is a plausible finding inasmuch as the reduction in numbers of additional units due to reliability considerations will affect cost most where the learning curve is steepest. 9 refs., 4 figs., 3 tabs

  6. Improving human reliability through better nuclear power plant system design. Progress report

    International Nuclear Information System (INIS)

    Golay, M.W.

    1995-01-01

    The project on open-quotes Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performanceclose quotes has been undertaken in order to address the important problem of human error in advanced nuclear power plant designs. Most of the creativity in formulating such concepts has focused upon improving the mechanical reliability of safety related plant systems. However, the lack of a mature theory has retarded similar progress in reducing the likely frequencies of human errors. The main design mechanism used to address this class of concerns has been to reduce or eliminate the human role in plant operations and accident response. The plan of work being pursued in this project is to perform a set of experiments involving human subject who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants. In the tests the systems are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds. Ultimately this computer is also to be used in compiling the results of the project. The work of this project is focused upon nuclear power plant applications. However, the persuasiveness of human errors in using all sorts of electromechanical machines gives it a much greater potential importance. Because of this we are attempting to pursue our work in a fashion permitting broad generalizations

  7. Medicinal Plants for Diabetes Treatment During Pregnancy.

    Science.gov (United States)

    Damasceno, Debora Cristina; Leal-Silva, Thais; Soares, Thaigra Sousa; Moraes-Souza, Rafaianne Queiroz; Volpato, Gustavo Tadeu

    2017-01-01

    Diabetes mellitus is a syndrome of great importance that affects an increasing number of people every day. In particular, diabetes is a common and important disease during pregnancy and is marked by complications, both fetal and maternal, that increase the risks of morbidity and mortality for diabetic pregnant women and their offspring. Drugs such as insulin and hypoglycemic drugs are given to treat diabetes, but regular exercise and adequate diet have also been indicated. Furthermore, coadjutant therapies such as medicinal plants are popularly used to reduce diabetes-induced hyperglycemia, either within or outside the context of pregnancy. However, studies examining plant use for diabetes treatment are necessary to confirm its possible effects and its safety for the mother and fetus. The objective of this literature review was to conduct a survey of plant species that are utilized worldwide and their stated therapeutic uses. A literature search was performed using the terms "diabetes and pregnancy", which resulted in the identification of 31,272 articles. Of these studies, only 12 (0.0038%) were related to medicinal plants, demonstrating that there has been little investigation into this issue. Of the papers analyzed in this review, half evaluated plant leaves, indicating that these scientific studies attempted to reproduce the preparations commonly used by various populations, i.e., in the form of tea. Additionally, more than 90% of studies utilized experimental animals to evaluate the maternal-fetal safety of medicinal plant substances that may potentially be dangerous for humans. Thus, once confidence levels for plant-derived substances are established based on toxicological analyses and safety is confirmed, it is possible that plants will be used to complement conventional diabetes therapies. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

  8. Strategy for establishing integrated l and c reliability of operating nuclear power plants in korea

    International Nuclear Information System (INIS)

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

    2008-01-01

    Korea hydro and nuclear power co. (KHNP) are in progress of developing a integrated I and C reliability establishing strategy for managing l and C obsolescence and phasing in new technology that both meets the needs of the fleet and captures the benefits of applying proven solutions to multiple plants, with reduced incremental costs. In view of this, we are developing I and C component management which covers major failure mode, symptom of performance degradation, condition-based or time-based preventive management (PM), monitoring, and failure finding and correction based on equipment reliability (ER). Furthermore, for the l and C system replacement management, we are in progress of 3-year-long I and C systems upgrade fundamental designing in developing the long-term major l and C systems implementation plan to improve plant operations, eliminate operator challenges, reduce maintenance costs, and cope with the challenges of component obsolescence. For accomplishing I and C digital upgrade in near future, we chose demonstration plant, Younggwang (YGN) unit 3 and 4 which are Korean Standard Nuclear Power Plant (KSNP). In this paper, we established the long term reliability strategy of I and C system based on ER in component replacement and furthermore I and C systems digital upgrade in system replacement. (authors)

  9. Reliability analysis of meteorological data registered during nuclear power plant normal operation

    International Nuclear Information System (INIS)

    Amado, V.; Ulke, A.; Marino, B.; Thomas, L.

    2011-01-01

    The atmosphere is the environment in which gaseous radioactive discharges from nuclear power plants are transported. It is therefore essential to have reliable meteorological information to characterize the dispersion and feed evaluation models and radiological environmental impact during normal operation of the plant as well as accidental releases. In this way it is possible to determine the effects on the environment and in humans. The basic data needed to represent adequately the local weather include air temperature, wind speed and direction, rainfall, humidity and pressure. On the other hand, specific data consistent with the used model is required to determine the turbulence, for instance, radiation, cloud cover and vertical temperature gradient. It is important that the recorded data are representative of the local meteorology. This requires, first, properly placed instruments, that should be kept in operation and undergoing maintenance on a regular basis. Second, but equally substantial, a thorough analysis of its reliability must be performed prior to storage and/or data processing. In this paper we present the main criteria to consider choosing the location of a meteorological tower in the area of a nuclear power plant and propose a methodology for assessing the reliability of recorded data. The methodology was developed from the analysis of meteorological data registered in nuclear power plants in Argentina. (authors) [es

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

    International Nuclear Information System (INIS)

    2005-06-01

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

  11. Rapid and reliable extraction of genomic DNA from various wild-type and transgenic plants

    Directory of Open Access Journals (Sweden)

    Yang Moon-Sik

    2004-09-01

    Full Text Available Abstract Background DNA extraction methods for PCR-quality DNA from calluses and plants are not time efficient, since they require that the tissues be ground in liquid nitrogen, followed by precipitation of the DNA pellet in ethanol, washing and drying the pellet, etc. The need for a rapid and simple procedure is urgent, especially when hundreds of samples need to be analyzed. Here, we describe a simple and efficient method of isolating high-quality genomic DNA for PCR amplification and enzyme digestion from calluses, various wild-type and transgenic plants. Results We developed new rapid and reliable genomic DNA extraction method. With our developed method, plant genomic DNA extraction could be performed within 30 min. The method was as follows. Plant tissue was homogenized with salt DNA extraction buffer using hand-operated homogenizer and extracted by phenol:chloroform:isoamyl alcohol (25:24:1. After centrifugation, the supernatant was directly used for DNA template for PCR, resulting in successful amplification for RAPD from various sources of plants and specific foreign genes from transgenic plants. After precipitating the supernatant, the DNA was completely digested by restriction enzymes. Conclusion This DNA extraction procedure promises simplicity, speed, and efficiency, both in terms of time and the amount of plant sample required. In addition, this method does not require expensive facilities for plant genomic DNA extraction.

  12. INPO's role in the improvement of nuclear plant safety and reliability

    International Nuclear Information System (INIS)

    Pate, Z.T.

    1985-01-01

    The Institute of Nuclear Power Operations (INPO) is a nonprofit, nongovernment corporation dedicated to promoting safe and reliable operation and quality construction of nuclear power plants. The institute is supported by the US nuclear utility industry. All US utilities building or operating nuclear power plants are INPO members. INPO's many activities fall within four major program areas: (1) Evaluations: INPO conducts detailed evaluations of all US operating plants, utility corporate support of nuclear programs, and nuclear projects under active construction. Events analysis and information exchange: INPO reviews plant reports of abnormal or unusual events and reports the lessons learned to the industry. INPO also fosters improved industry communications through a worldwide telecommunications network. (3) Training and accreditation: INPO assists utilities, including international participants, in developing quality training programs; and (4) Assistance: the Institute provides various forms of assistance to members and participants. INPO places emphasis on visits to facilities to aid members and participants in various program or operational areas

  13. Waste Treatment Plant LAW Evaporation: Antifoam Performance

    International Nuclear Information System (INIS)

    BAICH, MARKA

    2004-01-01

    This report describes the work performed to determine the performance and fate of several commercial antifoams during evaporation of various simulants of Envelope A, B, and C mixed with simulated River Protection Project Waste Treatment Plant (RPP-WTP) recycle streams. Chemical and radiation stability of selected antifoams was also investigated.Contributors to this effort include: Illinois Institute of Technology (IIT), DOW Corning Analytical, and Savannah River Technology Center (SRTC)

  14. Diesel-generator reliability at nuclear power plants: data and preliminary analysis. Interim report

    International Nuclear Information System (INIS)

    McClymont, A.; McLagan, G.

    1982-06-01

    This report summarizes work performed under RP1233-1 relating to the collection and analysis of data pertaining to diesel generator reliability in nuclear power plants. Drawing from data collected on-site at plants, data supplied by utilites, and data from Licensee Event Reports (LERs), the report describes methods of deriving reliability estimates from data for use in probabilistic risk assessment and presents results when these methods are applied to data collected from 14 plants. Specifically, data are used to estimate diesel failure probabilities for failures to start and failure rates for failures to continue to run. A sampling theory approach and a Bayesian approach to failure probability estimation are compared. The data are used to derive estimates of diesel repair time for some plants, maintenance outages, and multiple diesel failure rates. In addition, a section is included that presents suggestions for failure-rate estimation when an accurate count of diesel start attempts at a plant is not available. The final section presents an analysis of diesel failures based on data from LERs, including a breakdown of failure event by subsystem, failure mode, and failure cause. Appendixes include detailed summaries of the data used in the analysis of previous sections

  15. Impact of power plant reliability on the choice of operating parameter values

    International Nuclear Information System (INIS)

    Kramer, R.A.

    1985-01-01

    In this thesis, the basic structure for the development of a methodology to evaluate the effect of operating parameters on plant availability and generating system economic dispatch optimization is described. Plant availability is determined by a fault free model. In this model historic, time dependent, component induced forced outage data is utilized as the basis for the calculation of projected plant forced outage rates. The influence of a particular fuel-cycle length at a specific generating station on the operational planning of a multi unit generating system is considered. The basis of the dispatch of units in this analysis is optimal economic operation, i.e., the minimization of the cost of reliability supplying electricity to the system's customers. As a result of the utilization of this technique, a simplified example that considers the choice between a 12- and 18-month fuel cycle length is evaluated in terms of its impact on plant availability, fuel cycle economics and overall optimal generating system economic dispatch. The reliability portion of this methodology is applied to a simplified representation of the recirculation system of a pressurized water reactor nuclear power plant to illustrate the analytic techniques

  16. Natural Circulation in Water Cooled Nuclear Power Plants Phenomena, models, and methodology for system reliability assessments

    Energy Technology Data Exchange (ETDEWEB)

    Jose Reyes

    2005-02-14

    In recent years it has been recognized that the application of passive safety systems (i.e., those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially to improved economics of new nuclear power plant designs. In 1991 the IAEA Conference on ''The Safety of Nuclear Power: Strategy for the Future'' noted that for new plants the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate''.

  17. The purpose and organisation of reliability and risk assessment studies for power plant in operation

    International Nuclear Information System (INIS)

    Ohlmeier, H.

    1989-01-01

    Upon recommendation of the Reaktorsicherheitskommission RSK, specific, probabilistic safety analyses have to be made within the next few years for every nuclear power plant in operation. The paper deals with the activities and tasks and the necessary organisational preparations to be made for carrying out the studies. A systematic determination of reliability parameters and establishment of suitable computer codes are one of the major tasks in the preparatory phase, and information for further quantification of safety reserves and more plant-specific emergency management plans will be major results of the studies. (orig.) [de

  18. Natural Circulation in Water Cooled Nuclear Power Plants Phenomena, models, and methodology for system reliability assessments

    International Nuclear Information System (INIS)

    Jose Reyes

    2005-01-01

    In recent years it has been recognized that the application of passive safety systems (i.e., those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially to improved economics of new nuclear power plant designs. In 1991 the IAEA Conference on ''The Safety of Nuclear Power: Strategy for the Future'' noted that for new plants the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate''

  19. Operating reliability of valves in French pressurized water nuclear power plants

    International Nuclear Information System (INIS)

    Conte

    1986-10-01

    Taking into account the large numbers of valves (about 10000) of a PWR nuclear power plant, the importance of some valves in the safety functions and the cost resulting from their unavailability, the individual operability of these equipments has to be ensured at a high reliability level. This assurance can be obtained by means of an effort at all the stages which contribute to the quality of the product: design, qualification tests, fabrication, tests at the start-up stage, maintenance and tests during the power plant operation, experience feedback. This paper emphasizes more particularly on the tests carried out on loops of qualification [fr

  20. Evolving inspection technologies for reliable condition assessment of components and plants

    International Nuclear Information System (INIS)

    Baldev Raj

    1994-01-01

    Condition assessment of components and plants are being done regularly in many an industry. The methodologies adopted are being continuously refined. However, each of these methodologies are being applied in isolation, without realizing the synergistic advantage we derive when a global approach is taken for condition assessment. Developments in a variety of fields, that have a definite bearing on the reliability of condition assessment, are not applied (or even thought that they could be applied) together. The possible impact of evolving technologies in enhancing the efficiency of condition assessment of components and plants are discussed. (author). 11 refs

  1. Neuropsychological Aspects Observed in a Nuclear Plant Simulator and its Relation with Human Reliability Analysis

    International Nuclear Information System (INIS)

    Prado, E.A.P. do; Martins, M.; Pinheiro, A.; Silveira, J.

    2016-01-01

    This paper will discuss preliminary results of an evaluation methodology for the analysis and quantification of errors in manual (human) operation by training cognitive parameters and skill levels in the complex control system operation using Neuropsychophysiology and Neuro feedback equipment. The research was conducted using a game (nuclear power plant simulator) that simulates concepts of operation of a nuclear plant with a split sample evaluating aspects of learning and knowledge in the nuclear area. Operators were monitored using biomarkers (ECG, EEG, GSR, face detection and eye tracking) and the results were analyzed by Statistical multivariate techniques. An important component in the evaluation of complex systems is the human reliability during operation. Human reliability refers to the probability of the human element perform the tasks scheduled during the defined period for system operation when tested under specified environmental conditions, and additionally not to take any action detrimental to system operation.

  2. A reliability program for emergency diesel generators at nuclear power plants: Maintenance, surveillance, and condition monitoring

    International Nuclear Information System (INIS)

    Lofgren, E.V.; Henderson, W.; Burghardt, D.; Kripps, L.; Rothleder, B.

    1988-12-01

    This report is a companion report on NUREG/CR-5078, Volume 1, ''A Reliability Program for Emergency Diesel Generators at Nuclear Power Plants: Program Structure.'' The purpose of this report is to provide technical findings and insights related to: failure evaluation, troubleshooting, maintenance, surveillance, and condition monitoring. Examples and recommendations are provided for each of these areas based on actual emergency diesel generator (EDG) operating experience and the opinions of diesel generator experts. This report expands the more general guidance provided in Volume 1. In addition, a discussion of EDG interactions with other plant systems (e.g., instrument, air, service water, dc power) is provided since experience has shown that these support systems and their operation can adversely affect EDG reliability. Portions of this report have been designed for use by onsite personnel for evaluating operational characteristics of EDGs. 5 refs., 8 figs., 7 tabs

  3. A Reliability-Based Determination of Economic Life of Marine power plants

    International Nuclear Information System (INIS)

    Atua, K.

    1999-01-01

    The reliability-based life approach is utilized. Selective failure modes of marine power plants are used for illustration. A case study of the Egyptian Commercial Fleet owned by the Public Sector Company was analyzed and used to establish a demonstration of the expected economic life based on local operating and maintenance conditions. The data acquired is analyzed and failure trend is derived for each failure mode. Probabilistic techniques are used to randomly generate numbers and times of occurrence of different failure modes. The reliability analysis is performed on the life span expected by the manufacture to predict the total number of failures, dependent failures, and cost of failures. Total expenditure due to random failure and cost of scheduled maintenance together with the annual income are utilized (using the time value of money) to determine the economic life of the plant. Conclusions are derived and recommendations for the enhancement of this work in the future are made

  4. Reliability analysis of repairable safety systems of a reprocessing plant allowing for tolerable system downtimes

    International Nuclear Information System (INIS)

    Schaefer, H.

    1987-01-01

    GRS has been engaged in safety analysises of the German Reprocessing Plant for several years. The development and verification of appropriate reliability analysis methods, the generation of data as well as the search for an adequate structural presentation of the results to form a basis of recommendations for technical or administrative measures or contributions to risk oriented evaluations have been or are in the process of being established. In contrast to NPP-studies, the reliability assessment of safety systems of a reprocessing plant is applied to repairable and often relatively small systems allowing for tolerable system downtimes. A sketch of the diverse cooling systems of a vessel containing a selfheating solution is given. The interruption of the cooling function for about one day might be tolerable before boiling will be reached. This interval is suitable for transfer of the solution to a spare vessel or for repairing the failed components, thus restoring the cooling function

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

    Energy Technology Data Exchange (ETDEWEB)

    Swain, A D; Guttmann, H E

    1983-08-01

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

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

    International Nuclear Information System (INIS)

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

    1983-08-01

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

  7. Study of evaluation techniques of software safety and reliability in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Youn, Cheong; Baek, Y. W.; Kim, H. C.; Park, N. J.; Shin, C. Y. [Chungnam National Univ., Taejon (Korea, Republic of)

    1999-04-15

    Software system development process and software quality assurance activities are examined in this study. Especially software safety and reliability requirements in nuclear power plant are investigated. For this purpose methodologies and tools which can be applied to software analysis, design, implementation, testing, maintenance step are evaluated. Necessary tasks for each step are investigated. Duty, input, and detailed activity for each task are defined to establish development process of high quality software system. This means applying basic concepts of software engineering and principles of system development. This study establish a guideline that can assure software safety and reliability requirements in digitalized nuclear plant systems and can be used as a guidebook of software development process to assure software quality many software development organization.

  8. Assessing the adequacy and reliability of fire barriers in nuclear power plants

    International Nuclear Information System (INIS)

    Beard, A.N.

    1991-01-01

    Fire barriers on nuclear power plants are essential for proper segregation of redundant trains of safety equipment. The contribution they make to nuclear safety is obviously significant, but difficult to quantify. As a result, the analysis of fire barriers for nuclear safety justification purposes tends to concentrate on demonstrating that they are adequate instead. The paper discusses various methods of analysing fire barriers and introduces work being completed on a method for quantifying the reliability of a fire barrier. (orig.)

  9. Demonstration of Essential Reliability Services by a 300-MW Solar Photovoltaic Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Loutan, Clyde; Klauer, Peter; Chowdhury, Sirajul; Hall, Stephen; Morjaria, Mahesh; Chadliev, Vladimir; Milam, Nick; Milan, Christopher; Gevorgian, Vahan

    2017-03-24

    The California Independent System Operator (CAISO), First Solar, and the National Renewable Energy Laboratory (NREL) conducted a demonstration project on a large utility-scale photovoltaic (PV) power plant in California to test its ability to provide essential ancillary services to the electric grid. With increasing shares of solar- and wind-generated energy on the electric grid, traditional generation resources equipped with automatic governor control (AGC) and automatic voltage regulation controls -- specifically, fossil thermal -- are being displaced. The deployment of utility-scale, grid-friendly PV power plants that incorporate advanced capabilities to support grid stability and reliability is essential for the large-scale integration of PV generation into the electric power grid, among other technical requirements. A typical PV power plant consists of multiple power electronic inverters and can contribute to grid stability and reliability through sophisticated 'grid-friendly' controls. In this way, PV power plants can be used to mitigate the impact of variability on the grid, a role typically reserved for conventional generators. In August 2016, testing was completed on First Solar's 300-MW PV power plant, and a large amount of test data was produced and analyzed that demonstrates the ability of PV power plants to use grid-friendly controls to provide essential reliability services. These data showed how the development of advanced power controls can enable PV to become a provider of a wide range of grid services, including spinning reserves, load following, voltage support, ramping, frequency response, variability smoothing, and frequency regulation to power quality. Specifically, the tests conducted included various forms of active power control such as AGC and frequency regulation; droop response; and reactive power, voltage, and power factor controls. This project demonstrated that advanced power electronics and solar generation can be

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  11. Software reliability evaluation of digital plant protection system development process using V and V

    International Nuclear Information System (INIS)

    Lee, Na Young; Hwang, Il Soon; Seong, Seung Hwan; Oh, Seung Rok

    2001-01-01

    In the nuclear power industry, digital technology has been introduced recently for the Instrumentation and Control (I and C) of reactor systems. For its application to the safety critical system such as Reactor Protection System(RPS), a reliability assessment is indispensable. Unlike traditional reliability models, software reliability is hard to evaluate, and should be evaluated throughout development lifecycle. In the development process of Digital Plant Protection System(DPPS), the concept of verification and validation (V and V) was introduced to assure the quality of the product. Also, test should be performed to assure the reliability. Verification procedure with model checking is relatively well defined, however, test is labor intensive and not well organized. In this paper, we developed the methodological process of combining the verification with validation test case generation. For this, we used PVS for the table specification and for the theorem proving. As a result, we could not only save time to design test case but also get more effective and complete verification related test case set. Add to this, we could extract some meaningful factors useful for the reliability evaluation both from the V and V and verification combined tests

  12. Waste Treatment Plant Liquid Effluent Treatability Evaluation

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2001-01-01

    Bechtel National, Inc. (BNI) provided a forecast of the radioactive, dangerous liquid effluents expected to be generated by the Waste Treatment Plant (WTP). The forecast represents the liquid effluents generated from the processing of 25 distinct batches of tank waste through the WTP. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Fluor Hanford, Inc. (FH) evaluated the treatability of the WTP liquid effluents in the LERFIETF. The evaluation was conducted by comparing the forecast to the LERFIETF treatability envelope, which provides information on the items that determine if a liquid effluent is acceptable for receipt and treatment at the LERFIETF. The WTP liquid effluent forecast is outside the current LERFlETF treatability envelope. There are several concerns that must be addressed before the WTP liquid effluents can be accepted at the LERFIETF

  13. Review of Software Reliability Assessment Methodologies for Digital I and C Software of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jae Hyun; Lee, Seung Jun; Jung, Won Dea [KAERI, Daejeon (Korea, Republic of)

    2014-08-15

    Digital instrumentation and control (I and C) systems are increasingly being applied to current nuclear power plants (NPPs) due to its advantages; zero drift, advanced data calculation capacity, and design flexibility. Accordingly, safety issues of software that is main part of the digital I and C system have been raised. As with hardware components, the software failure in NPPs could lead to a large disaster, therefore failure rate test and reliability assessment of software should be properly performed, and after that adopted in NPPs. However, the reliability assessment of the software is quite different with that of hardware, owing to the nature difference between software and hardware. The one of the most different thing is that the software failures arising from design faults as 'error crystal', whereas the hardware failures are caused by deficiencies in design, production, and maintenance. For this reason, software reliability assessment has been focused on the optimal release time considering the economy. However, the safety goal and public acceptance of the NPPs is so distinctive with other industries that the software in NPPs is dependent on reliability quantitative value rather than economy. The safety goal of NPPs compared to other industries is exceptionally high, so conventional methodologies on software reliability assessment already used in other industries could not adjust to safety goal of NPPs. Thus, the new reliability assessment methodology of the software of digital I and C on NPPs need to be developed. In this paper, existing software reliability assessment methodologies are reviewed to obtain the pros and cons of them, and then to assess the usefulness of each method to software of NPPs.

  14. Review of Software Reliability Assessment Methodologies for Digital I and C Software of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Cho, Jae Hyun; Lee, Seung Jun; Jung, Won Dea

    2014-01-01

    Digital instrumentation and control (I and C) systems are increasingly being applied to current nuclear power plants (NPPs) due to its advantages; zero drift, advanced data calculation capacity, and design flexibility. Accordingly, safety issues of software that is main part of the digital I and C system have been raised. As with hardware components, the software failure in NPPs could lead to a large disaster, therefore failure rate test and reliability assessment of software should be properly performed, and after that adopted in NPPs. However, the reliability assessment of the software is quite different with that of hardware, owing to the nature difference between software and hardware. The one of the most different thing is that the software failures arising from design faults as 'error crystal', whereas the hardware failures are caused by deficiencies in design, production, and maintenance. For this reason, software reliability assessment has been focused on the optimal release time considering the economy. However, the safety goal and public acceptance of the NPPs is so distinctive with other industries that the software in NPPs is dependent on reliability quantitative value rather than economy. The safety goal of NPPs compared to other industries is exceptionally high, so conventional methodologies on software reliability assessment already used in other industries could not adjust to safety goal of NPPs. Thus, the new reliability assessment methodology of the software of digital I and C on NPPs need to be developed. In this paper, existing software reliability assessment methodologies are reviewed to obtain the pros and cons of them, and then to assess the usefulness of each method to software of NPPs

  15. Utilizing clad piping to improve process plant piping integrity, reliability, and operations

    International Nuclear Information System (INIS)

    Chakravarti, B.

    1996-01-01

    During the past four years carbon steel piping clad with type 304L (UNS S30403) stainless steel has been used to solve the flow accelerated corrosion (FAC) problem in nuclear power plants with exceptional success. The product is designed to allow ''like for like'' replacement of damaged carbon steel components where the carbon steel remains the pressure boundary and type 304L (UNS S30403) stainless steel the corrosion allowance. More than 3000 feet of piping and 500 fittings in sizes from 6 to 36-in. NPS have been installed in the extraction steam and other lines of these power plants to improve reliability, eliminate inspection program, reduce O and M costs and provide operational benefits. This concept of utilizing clad piping in solving various corrosion problems in industrial and process plants by conservatively selecting a high alloy material as cladding can provide similar, significant benefits in controlling corrosion problems, minimizing maintenance cost, improving operation and reliability to control performance and risks in a highly cost effective manner. This paper will present various material combinations and applications that appear ideally suited for use of the clad piping components in process plants

  16. Health hazards related to Soba sewage treatment plant, Sudan

    Directory of Open Access Journals (Sweden)

    Rasha Osman Abdelwahab Abdelmoneim

    2017-12-01

    Full Text Available The aim of this study was to determine the health hazards acquired by the residents nearby Soba sewage treatment plant. A descriptive cross-sectional study was carried out in Soba locality, Khartoum, Sudan. An interviewer-administrated questionnaire was assigned to 462 residents of the area living in four geographically distributed squares around the sewage plant. The data was analyzed in SPSS; Cronbach’s alpha reliability scale of measurement was used to check the internal validity of six variables related to the quality of life. A logistic regression analysis was used to assess the relationship between the health hazards and the quality of life. Among the 462 residents, difficulty in breathing (37.9% and nausea (37.2 were the principal health hazards. Moreover, the residents had a satisfactory level of awareness (88.7% about the health hazards. The utmost impact on the quality of life was psychological (97.2%. It was statistically correlated with the reported factors, which impacted the quality of life in the district as revealed by the Cronbach’s alpha reliability test with absenteeism (P=0.026, disability (P=0.014, socialization (P=0.032 and death (P=0.016. A logistic regression analysis revealed chemical hazards had a statistically significant association (P<0.05 with quality of life of the residents of Soba district. The study strongly entails the fact that sewage treatment plants crave exceptional consideration from the concerned responsible authorities, together with the fact that the evolved health threats should be confronted with immense responsibility as soon as possible.

  17. Reliability evaluation of emergency AC power systems based on operating experience at U.S. nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Baranowsky, P. W. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

    1986-02-15

    The reliability of emergency AC power Systems has been under study at the U.S. Nuclear Regulatory Commission and by its contractors for several years. This paper provides the results of work recently performed to evaluate past U.S. nuclear power plant emergency AC power System reliability performance using system level data. Operating experience involving multiple diesel generator failures, unavailabilities, and simultaneous occurrences of failures and out of service diesel generators were used to evaluate reliability performance at individual nuclear power plants covering a 9 year period from 1976 through 1984. The number and nature of failures and distributions of reliability evaluation results are provided. The results show that plant specific performance varied considerably during the period with a large number achieving high reliability performance and a smaller number accounting for lower levels of reliability performance. (author)

  18. Human Reliability analysis for digitized nuclear power plants: Case study on the LingAo II nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Zou, Yan Hua; Zhang, Li [Institute of Human Factors Engineering AND Safety Management, Hunan Institute of Technology, Hengyang (China); Dai, Cao; Li, Peng Cheng; Qing, Tao [Human Factors Institute, University of South China, Hengyang (China)

    2017-03-15

    The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

  19. Human Reliability Analysis for Digitized Nuclear Power Plants: Case Study on the LingAo II Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Yanhua Zou

    2017-03-01

    Full Text Available The main control room (MCR in advanced nuclear power plants (NPPs has changed from analog to digital control system (DCS. Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

  20. Effluent treatment plant and decontamination centre, Trombay

    International Nuclear Information System (INIS)

    Kaushik, C.P.; Agarwal, K.

    2017-01-01

    The Bhabha Atomic Research Centre, Trombay, has a number of plants and laboratories, which generate Radioactive Liquid Waste and Protective Wears. Two facilities have been established in late 1960s to cater to this requirement. The Centre, on the average generates about 50,000 m"3 of active liquid effluents of varying specific activities. The Effluent Treatment Plant was setup to receive and process radioactive liquids generated by various facilities of BARC in Trombay. It also serves a single-point discharge facility to enable monitoring of radioactive effluents discharged from the Trombay site. About 120-150 Te of protective wears and inactive apparel are generated annually from various radioactive facilities and laboratories of BARC. In addition, contaminated fuel assembly components are generated by DHRUVA and formerly by CIRUS. These components require decontamination before its recycle to the fuel assembly process. The Decontamination Centre, setup in late 1960s, is mandated to carry out the above mentioned decontamination activities

  1. Verification and validation--The key to operating plant software reliability

    International Nuclear Information System (INIS)

    Daughtrey, H.T.; Daggett, P.W.; Schamp, C.A.

    1983-01-01

    This paper discusses the design and implementation of a verification and validation (V and V) plan for reviewing the microcomputer software developed for a Safety Parameter Display System (SPDS). Topics considered include a historical perspective on V and V, the function and significance of SPDS software, and testing. An SPDS provides information to nuclear power plant operators about the status of the plant under all operating conditions. It is determined that by implementing V and V activities throughout the development cycle, problems are less expensive to locate in the early phases of software development, problems are less expensive to fix in the early phases of software development, and a parallel V and V activity is more cost effective than a similar effort performed only at the end of software development. It is concluded that V and V is a proven tool for improving power plant software reliability

  2. Improving human reliability through better nuclear power plant system design: Program for advanced nuclear power studies

    International Nuclear Information System (INIS)

    Golay, M.W.

    1993-01-01

    The project on ''Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performance'' was been undertaken in order to address the problem of human error in advanced nuclear power plant designs. Lack of a mature theory has retarded progress in reducing likely frequencies of human errors. Work being pursued in this project is to perform a set of experiments involving human subjects who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants, which are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds

  3. Reliability centered maintenance as an optimization tool for electrical power plants

    International Nuclear Information System (INIS)

    Jacquot, J.P.; Bryla, P.; Martin-Mattei, C.; Meuwisse, C.

    1997-08-01

    Seven years ago, Electricite de France launched a Reliability Centered Maintenance (RCM) pilot project to optimize preventive maintenance for its nuclear power plants. After a feasibility study, a RCM method was standardized. It is now applied on a large scale to the 50 EDF nuclear units. A RCM workstation based on this standardized method has been developed and is now used in each plant. In the next step, it is considered whether a Risk based Approach can be included in this RCM process in order to analyze critical passive components such as pipes and supports. Considering the potential advantages of these optimization techniques, a dedicated process has been also developed for maintenance of future plants, gas turbines, or nuclear units. A survey of these different developments of methods and tools is presented. (author)

  4. Role of recent research in improving check valve reliability at nuclear power plants

    International Nuclear Information System (INIS)

    Kalsi, M.S.; Horst, C.L.; Wang, J.K.; Sharma, V.

    1990-01-01

    Check valve failures at nuclear power plants in recent years have led to serious safety concerns, and caused extensive damage to other plant components which had a significant impact on plant availability. In order to understand the failure mechanism and improve the reliability of check valves, a systematic research effort was proposed by Kalsi Engineering, Inc. to U.S. Nuclear Regulatory Commission (NRC). The overall goal of the research was to develop models for predicting the performance and degradation of swing check valves in nuclear power plant systems so that appropriate preventive maintenance or design modifications can be performed to improve the reliability of check valves. Under Phase I of this research, a large matrix of tests was run with instrumented swing check valves to determine the stability of the disc under a variety of upstream flow disturbances, covering a wide range of disc stop positions and flow velocities in two different valve sizes. The goals of Phase II research were to develop predictive models which quantify the anticipated degradation of swing check valves that have flow disturbances closely upstream of the valve and are operating under flow velocities that do not result in full disc opening. This research allows the inspection/maintenance activities to be focussed on those check valves that are more likely to suffer premature degradation. The quantitative wear and fatigue prediction methodology can be used to develop a sound preventive maintenance program. The results of the research also show the improvements in check valve performance/reliability that can be achieved by certain modifications in the valve design

  5. TBP production plant effluent treatment process

    International Nuclear Information System (INIS)

    Sriniwas, C.; Sugilal, G.; Wattal, P.K.

    2004-06-01

    TBP production facility at Heavy Water Plant, Talcher generates about 2000 litres of effluent per 200 kg batch. The effluent is basically an aqueous solution containing dissolved and dispersed organics such as dibutyl phosphate, butanol etc. The effluent has high salinity, chemical oxygen demand (30-80 g/L) and pungent odour. It requires treatment before discharge. A chemical precipitation process using ferric chloride was developed for quantitative separation of organics from the aqueous part of the effluent. This process facilitates the discharge of the aqueous effluent. Results of the laboratory and bench scale experiments on actual effluent samples are presented in this report. (author)

  6. Water treatment for 500 MWe PHWR plants

    International Nuclear Information System (INIS)

    Vasist, Sudheer; Sharma, M.C.; Agarwal, N.K.

    1995-01-01

    Large quantities of treated water is required for power generation. For a typical 500 MWe PHWR inland station with cooling towers, raw water at the rate of 6000 m 3 /hr is required. Impurities in cooling water give rise to the problems of corrosion, scaling, microbiological contamination, fouling, silical deposition etc. These problems lead to increased maintenance cost, reduced heat transfer efficiency, and possible production cut backs or shutdowns. The problems in coastal based power plants are more serious because of the highly corrosive nature of sea water used for cooling. An overview of the cooling water systems and water treatment method is enumerated. (author). 2 refs., 1 fig

  7. Reliability and safety of a new upper cervical spine injury treatment algorithm

    Directory of Open Access Journals (Sweden)

    Andrei Fernandes Joaquim

    Full Text Available ABSTRACT In the present study, we evaluated the reliability and safety of a new upper cervical spine injury treatment algorithm to help in the selection of the best treatment modality for these injuries. Methods Thirty cases, previously treated according to the new algorithm, were presented to four spine surgeons who were questioned about their personal suggestion for treatment, and the treatment suggested according to the application of the algorithm. After four weeks, the same questions were asked again to evaluate reliability (intra- and inter-observer using the Kappa index. Results The reliability of the treatment suggested by applying the algorithm was superior to the reliability of the surgeons’ personal suggestion for treatment. When applying the upper cervical spine injury treatment algorithm, an agreement with the treatment actually performed was obtained in more than 89% of the cases. Conclusion The system is safe and reliable for treating traumatic upper cervical spine injuries. The algorithm can be used to help surgeons in the decision between conservative versus surgical treatment of these injuries.

  8. Effect of communication on the reliability of nuclear power plant control room operations - pre study

    International Nuclear Information System (INIS)

    Kettunen, Jari; Pyy, Pekka

    1999-01-01

    The objective of the study presented in this paper is to investigate communication practices and their impact on human reliability and plant safety in a nuclear power plant environment. The study aims at developing a general systems approach towards the issue. The ultimate goal of the study is to contribute to the development of probabilistic safety assessment methodologies in the area of communications and crew co-operation. This paper outlines the results of the pre-study. The study is based on the use and further development of different modelling techniques and the application of generic systems engineering as well as crew resource management (CRM) principles. The results so far include a concise literature review on communication and crew performance, a presentation of some potential theoretical concepts and approaches for studying communication in relation to organisational reliability, causal failure sequences and human failures mechanisms, and an introduction of a General Communications Model (GCM) that is presented as a promising approach for studying the reliability and adequacy of communication transactions. Finally, some observations and recommendation concerning next phases of the study are made (author) (ml)

  9. The United States nuclear plant reliability data program: Its description and status

    International Nuclear Information System (INIS)

    Wise, M.J.

    1975-01-01

    The American National Standards Institute Subcommittee N18-20 has developed and implemented the United States Nuclear Plant Reliability Data System (NPRDS). The NPRDS is designed to accumulate, store, analyse, and report reliability and failure statistics on systems and components of nuclear power plants related to nuclear safety. Input data to the NPRDS consist of engineering, operating, and failure information submitted on a voluntary basis by participating utilities. Prior to entry into the computerized data base, the data are thoroughly checked for accuracy by both the submitting organizations and the NPRDS operating contractor. The data base is the source of various periodic output reports to the nuclear power industry and is utilized to produce special reports upon request. The present data base represents data accumulated from about thirty nuclear units with additional units expected to begin submitting data immediately. The objective is to have essentially all operating nuclear units in the United States of America participating in the program by the end of 1975. The first NPRDS annual reports containing meaningful reliability and failure statistics are expected to be produced following the end of 1975. (author)

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

    International Nuclear Information System (INIS)

    Ohno, Tokue; Tanaka, Nagatoshi

    1988-01-01

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

  11. Study on the Management for the Nuclear Power Plant Maintenance and Equipment Reliability

    International Nuclear Information System (INIS)

    Yoon, Kyeongseop; Lee, Sangheon; Kim, Myungjin; Lee, Unjang

    2015-01-01

    In our country, many studies on the regulatory policy of the plant maintenance have ever been performed since 1998, but the relevant regulatory requirements were not established yet. These background mentioned above request us to study on the regulation policy and maintenance plan to improve the safety, reliability and efficiency of NPP. To solve these problems, in this study, we deduct the management methodology for the improvement of NPP maintenance and equipment reliability that is essential to secure the safety and efficiency of the commercial NPP. For analysis the maintenance and equipment reliability management methodology in overseas NPP. We studied maintenance and equipment reliability of USA, Canada and Europe(France, England, German). We also studied status and application condition of Korean NPP maintenance management technical development. We deducted an effective maintenance methodology that is needed to Korean NPP, as a result of comparison on the technical trend of the maintenance management between overseas and Korean, such like following. - Regulation form ·Specific provision of regulation requirement and application of form that is clarifying application standard - Maintenance management methodology, Maintenance management program. This results of study could be applied for regulation policy, law and guideline establishment of NPP maintenance, operation, supervision and a system establishment for maintenance management, education data about maintenance for NPP employees

  12. High reliable and Real-time Data Communication Network Technology for Nuclear Power Plant

    International Nuclear Information System (INIS)

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

    2008-03-01

    As advanced digital Instrumentation and Control (I and C) system of NPP(Nuclear Power Plant) are being introduced to replace analog systems, a Data Communication Network(DCN) is becoming the important system for transmitting the data generated by I and C systems in NPP. In order to apply the DCNs to NPP I and C design, DCNs should conform to applicable acceptance criteria and meet the reliability and safety goals of the system. As response time is impacted by the selected protocol, network topology, network performance, and the network configuration of I and C system, DCNs should transmit a data within time constraints and response time required by I and C systems to satisfy response time requirements of I and C system. To meet these requirements, the DCNs of NPP I and C should be a high reliable and real-time system. With respect to high reliable and real-time system, several reports and techniques having influences upon the reliability and real-time requirements of DCNs are surveyed and analyzed

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

    International Nuclear Information System (INIS)

    2007-05-01

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

  14. Reliability and maintenance in European nuclear power plants: A structural analysis of a controlled stochastic process

    International Nuclear Information System (INIS)

    Sturm, R.

    1991-01-01

    Two aspects of performance are of main concern: plant availability and plant reliability (defined as the conditional probability of an unplanned shutdown). The goal of the research is a unified framework that combines behavioral models of optimizing agents with models of complex technical systems that take into account the dynamic and stochastic features of the system. In order to achieve this synthesis, two liens of work are necessary. One line requires a deeper understanding of complex production systems and the type of data they give rise to; the other line involves the specification and estimation of a rigorously specified behavioral model. Plant operations are modeled as a controlled stochastic process, and the sequence of up and downtime spells is analyzed during failure time and point process models. Similar to work on rational expectations and structural econometric models, the behavior model of how the plant process is controlled is formulated at the level of basic processes, i.e., the objective function of the plant manager, technical constraints, and stochastic disturbances

  15. From reliability to maintenance of emergency generator sets in nuclear plants

    International Nuclear Information System (INIS)

    Reyraud, Y.

    1986-01-01

    The particular conditions of operation of emergency generator sets in a nuclear energy plant induce to take up a strategy of supervision and of maintenance very different of the one recommended for production generator sets. Mechanical and thermal pulls are affected by the size of the set and the choice of rotation running in respect of the wanted power and the response time requirements for the security of nuclear reactor. Reliability studies are helpful to define the strategy of supervision tests. The importance of the number of starts with respect to the running time requires the introduction of the idea of equivalent hours for the definition of maintenance periods. The security of the equipment and the upholding of the reliability at a value close to the optimum impose rigorous choices and strict conditions of supervision and maintenance [fr

  16. Practical applications of probabilistic structural reliability analyses to primary pressure systems of nuclear power plants

    International Nuclear Information System (INIS)

    Witt, F.J.

    1980-01-01

    Primary pressure systems of nuclear power plants are built to exacting codes and standards with provisions for inservice inspection and repair if necessary. Analyses and experiments have demonstrated by deterministic means that very large margins exist on safety impacting failures under normal operating and upset conditions. Probabilistic structural reliability analyses provide additional support that failures of significance are very, very remote. They may range in degree of sophistication from very simple calculations to very complex computer analyses involving highly developed mathematical techniques. The end result however should be consistent with the desired usage. In this paper a probabilistic structural reliability analysis is performed as a supplement to in-depth deterministic evaluations with the primary objective to demonstrate an acceptably low probability of failure for the conditions considered. (author)

  17. A new modular procedure for industrial plant simulations and its reliable implementation

    International Nuclear Information System (INIS)

    Carcasci, C.; Marini, L.; Morini, B.; Porcelli, M.

    2016-01-01

    Modeling of industrial plants, and especially energy systems, has become increasingly important in industrial engineering and the need for accurate information on their behavior has grown along with the complexity of the industrial processes. Consequently, accurate and flexible simulation tools became essential yielding the development of modular codes. The aim of this work is to propose a new modular mathematical modeling for industrial plant simulation and its reliable numerical implementation. Regardless of their layout, a large class of plant's configurations is modeled by a library of elementary parts; then the physical properties, compositions of the working fluid, and plant's performance are estimated. Each plant component is represented by equations modeling fundamental mechanical and thermodynamic laws and giving rise to a system of algebraic nonlinear equations; remarkably, suitable restrictions on the variables of such nonlinear equations are imposed to guarantee solutions of physical meaning. The proposed numerical procedure combines an outer iterative process which refines plants characteristic parameters and an inner one which solves the arising nonlinear systems and consists of a trust-region solver for bound-constrained nonlinear equalities. The new procedure has been validated performing simulations against an existing modular tool on two compression train arrangements with both series and parallel-mounted compressors. - Highlights: • A numerical modular tool for industrial plants simulation is presented. • Mathematical modeling is thoroughly described. • Solution of the nonlinear system is performed by a trust-region Gauss–Newton solver. • A detailed explanation of the optimization solver named TRESNEI is provided. • Code flexibility and robustness are investigated through numerical simulations.

  18. Reliability of emergency alternating-current power systems at nuclear power plants: a discussion of NUREG/CR-2989

    International Nuclear Information System (INIS)

    Battle, R.E.

    1985-01-01

    The reliability of emergency alternating-current power systems typical of most nuclear power plants was estimated by using fault-tree analysis of selected typical designs. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports and from operating experience information obtained from nuclear plant licensees. Trends of diesel generator independent failure on demand are included. No one or two improvements can be made at all plants to increase significantly the industry-average emergency alternating-current power system reliability; the most beneficial improvements are varied and plant specific

  19. Experimental Research of Reliability of Plant Stress State Detection by Laser-Induced Fluorescence Method

    Directory of Open Access Journals (Sweden)

    Yury Fedotov

    2016-01-01

    Full Text Available Experimental laboratory investigations of the laser-induced fluorescence spectra of watercress and lawn grass were conducted. The fluorescence spectra were excited by YAG:Nd laser emitting at 532 nm. It was established that the influence of stress caused by mechanical damage, overwatering, and soil pollution is manifested in changes of the spectra shapes. The mean values and confidence intervals for the ratio of two fluorescence maxima near 685 and 740 nm were estimated. It is presented that the fluorescence ratio could be considered a reliable characteristic of plant stress state.

  20. Interim reliability evaluation program: analysis of the Arkansas Nuclear One. Unit 1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kolb, G.J.; Kunsman, D.M.; Bell, B.J.

    1982-06-01

    This report represents the results of the analysis of Arkansas Nuclear One (ANO) Unit 1 nuclear power plant which was performed as part of the Interim Reliability Evaluation Program (IREP). The IREP has several objectives, two of which are achieved by the analysis presented in this report. These objectives are: (1) the identification, in a preliminary way, of those accident sequences which are expected to dominate the public health and safety risks; and (2) the development of state-of-the-art plant system models which can be used as a foundation for subsequent, more intensive applications of probabilistic risk assessment. The primary methodological tools used in the analysis were event trees and fault trees. These tools were used to study core melt accidents initiated by loss of coolant accidents (LOCAs) of six different break size ranges and eight different types of transients

  1. Advanced control systems to improve nuclear power plant reliability and efficiency

    International Nuclear Information System (INIS)

    1997-07-01

    The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs

  2. Job analysis of the electrician position for the nuclear power plant maintenance personnel reliability model

    International Nuclear Information System (INIS)

    Federman, P.J.; Bartter, W.D.; Siegel, A.I.

    1984-02-01

    This report presents the methods, procedures, and results of the fourth and final of a series of job analytic studies which characterize maintenance positions in nuclear power plants. The electrician position is the subject of the present report. The characterization of the electrician position takes the form of detailed information about: (1) the frequency of performing various tasks, (2) the time required for performing each task, (3) the training required for adequate performance of each task, and (4) the perceived consequences resulting from inadequate task performance. Additionally, information is presented about the intellective and the perceptual-motor loading imposed by each task. This information contributes to job design and training requirements derivation as well as to the assessment of human performance reliability in nuclear power plants

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

    International Nuclear Information System (INIS)

    Maurer, H.A.

    1978-01-01

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

  4. Advanced control systems to improve nuclear power plant reliability and efficiency

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs.

  5. Configuration of risk monitor system by plant defense-in-depth risk monitor and reliability monitor

    International Nuclear Information System (INIS)

    Yoshikawa, Hidekazu; Lind Morten; Yang Ming; Hashim Muhammad; Zhang Zhijian

    2012-01-01

    A new method of risk monitor system of a nuclear power plant has been proposed from the aspect by what degree of safety functions incorporated in the plant system is maintained by multiple barriers of defense-in-depth (DiD). Wherein, the central idea is plant DiD risk monitor and reliability monitor derived from the five aspects of (1) design principle of nuclear safety based on DiD concept, (2) definition of risk and risk to be monitored, (3) severe accident phenomena as major risk, (4) scheme of risk ranking, and (5) dynamic risk display. In this paper, the overall frame of the proposed risk monitor system is summarized and the detailed discussion is made on major items such as definition of risk and risk ranking, anatomy of fault occurrence, two-layer configuration of risk monitor, how to configure individual elements of plant DiD risk monitor, and lastly how to apply for a PWR safety system. (author)

  6. An Update on Modifications to Water Treatment Plant Model

    Science.gov (United States)

    Water treatment plant (WTP) model is an EPA tool for informing regulatory options. WTP has a few versions: 1). WTP2.2 can help in regulatory analysis. An updated version (WTP3.0) will allow plant-specific analysis (WTP-ccam) and thus help meet plant-specific treatment objectives...

  7. Aqueous Waste Treatment Plant at Aldermaston

    International Nuclear Information System (INIS)

    Keene, D.; Fowler, J.; Frier, S.

    2006-01-01

    For over half a century the Pangbourne Pipeline formed part of AWE's liquid waste management system. Since 1952 the 11.5 mile pipeline carried pre-treated wastewater from the Aldermaston site for safe dispersal in the River Thames. Such discharges were in strict compliance with the exacting conditions demanded by all regulatory authorities, latterly, those of the Environment Agency. In March 2005 AWE plc closed the Pangbourne Pipeline and ceased discharges of treated active aqueous waste to the River Thames via this route. The ability to effectively eliminate active liquid discharges to the environment is thanks to an extensive programme of waste minimization on the Aldermaston site, together with the construction of a new Waste Treatment Plant (WTP). Waste minimization measures have reduced the effluent arisings by over 70% in less than four years. The new WTP has been built using best available technology (evaporation followed by reverse osmosis) to remove trace levels of radioactivity from wastewater to exceptionally stringent standards. Active operation has confirmed early pilot scale trials, with the plant meeting throughput and decontamination performance targets, and final discharges being at or below limits of detection. The performance of the plant allows the treated waste to be discharged safely as normal industrial effluent from the AWE site. Although the project has had a challenging schedule, the project was completed on programme, to budget and with an exemplary safety record (over 280,000 hours in construction with no lost time events) largely due to a pro-active partnering approach between AWE plc and RWE NUKEM and its sub-contractors. (authors)

  8. Agricultural use of municipal wastewater treatment plant ...

    Science.gov (United States)

    Agricultural use of municipal wastewater treatment plant sewage sludge as a source of per- and polyfluoroalkyl substance (PFAS) contamination in the environment The National Exposure Research Laboratory (NERL) Human Exposure and Atmospheric Sciences Division (HEASD) conducts research in support of EPA mission to protect human health and the environment. HEASD research program supports Goal 1 (Clean Air) and Goal 4 (Healthy People) of EPA strategic plan. More specifically, our division conducts research to characterize the movement of pollutants from the source to contact with humans. Our multidisciplinary research program produces Methods, Measurements, and Models to identify relationships between and characterize processes that link source emissions, environmental concentrations, human exposures, and target-tissue dose. The impact of these tools is improved regulatory programs and policies for EPA.

  9. An automation model of Effluent Treatment Plant

    Directory of Open Access Journals (Sweden)

    Luiz Alberto Oliveira Lima Roque

    2012-07-01

    Full Text Available Population growth and intensification of industrial activities have increased the deterioration of natural resources. Industrial, hospital and residential wastes are dumped directly into landfills without processing, polluting soils. This action will have consequences later, because the liquid substance resulting from the putrefaction of organic material plows into the soil to reach water bodies. Cities arise without planning, industrial and household wastes are discharged into rivers, lakes and oceans without proper treatment, affecting water resources. It is well known that in the next century there will be fierce competition for fresh water on the planet, probably due to the scarcity of it. Demographic expansion has occurred without proper health planning, degrading oceans, lakes and rivers. Thus, a large percentage of world population suffers from diseases related to water pollution. Accordingly, it can be concluded that sewage treatment is essential to human survival, to preserve rivers, lakes and oceans. An Effluent Treatment Plant (ETP treats wastewater to reduce its pollution to acceptable levels before sending them to the oceans or rivers. To automate the operation of an ETP, motors, sensors and logic blocks, timers and counters are needed. These functions are achieved with programmable logic controllers (PLC and Supervisory Systems. The Ladder language is used to program controllers and is a pillar of the Automation and Control Engineering. The supervisory systems allow process information to be monitored, while the PLC are responsible for control and data acquisition. In the age we live in, process automation is used in an increasing scale in order to provide higher quality, raise productivity and improve the proposed activities. Therefore, an automatic ETP will improve performance and efficiency to handle large volumes of sewage. Considering the growing importance of environmental awareness with special emphasis

  10. Increasing the reliability of electric energy supply to consumers in ROMAG-PROD Heavy Water Plant

    International Nuclear Information System (INIS)

    Barta, Ioan; Hanes, Marian . E-mail electrica@romag.ro

    2004-01-01

    Full text: This work aims at achieving an analysis of time evolution of the status of electrical installations, their performances and reliability, at describing the refurbishment measures adopted, at assessing the efficiency of these measures and also to suggest solutions for improving the reliability in the electric energy supply of ROMAG-PROD Heavy Water Plant. The analysis started from the original design, the manner the electrical installations were mounted, the technological level of this equipment and gives an evaluation of the deficiencies and the evolution of incidents occurred during the operation period. On the basis of the experience gathered one advances new items for equipment renewing and refurbishment of electric installations which together with the existing ones would ensure an electric energy supply more secure and efficient, leading directly to a more safe and efficient operation of the ROMAG-PROD Heavy Water Plant. In this work the incidents of electric energy nature which occurred are analyzed, the equipment which generated events identified and measures to solve these problems proposed

  11. Researching and improving the reliability of reactor protection system of Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Zuyue; Sheng Jiannan

    1997-01-01

    Due to the original design defects of the Reactor Protection System (RPS) of Qinshan Nuclear Power Plant, this system has brought about a number of reactor shutdown accidents and Engineered Safety Features (ESF) mis-activation events which have seriously endangered safe and steady operation of the nuclear power plant. So over three years have been spent on research on the reform of the original design on the premise that the general wiring of the system should remain the same and that the system size should also remain small to be contained in the original cabinets. The following improvements were made: (1) Increase the system's anti-disturbance capability. The system's zero volt bus floating designs were modified to surmount the disturbance resulting from the bad isolation performance of impedance-isolated amplifier; Double grounds have been added to logical modules to surmount the disturbance resulting from zero volt floating bus during the replacement of single module with two connectors; The opto-coupling circuit in its oscillation input stage of Engineered Safety Features have been improved to increase its reliability. (2)Modify to output activation part of the system. The new type of output relays were selected and the relay activation circuits were redesigned in which switcher activation mode is used instead of amplifier activation mode so as to increase the reliability of relay operation and reduce the power consumption; CMOS buffer gates in the input and output stage of the circuit were used to match TTL circuits to CMOS circuits of the system

  12. Reliability of some ageing nuclear power plant systems: a simple stochastic model

    International Nuclear Information System (INIS)

    Suarez Antola, R.

    2007-01-01

    The random number of failure-related events in certain repairable ageing systems, like certain nuclear power plant components, during a given time interval, may be often modelled by a compound Poisson distribution. One of these is the Polya-Aeppli distribution. The derivation of a stationary Polya-Aeppli distribution as a limiting distribution of rare events for stationary Bernouilli trials with first order Markov dependence is considered. But if the parameters of the Polya-Aeppli distribution are suitable time functions, we could expect that the resulting distribution would allow us to take into account the distribution of failure-related events in an ageing system. Assuming that a critical number of damages produce an emergent failure, the abovementioned results can be applied in a reliability analysis. It is natural to ask under what conditions a Polya-Aeppli distribution could be a limiting distribution for non-homogeneous Bernouilli trials with first order Markov dependence. In this paper this problem is analyzed and possible applications of the obtained results to ageing or deteriorating nuclear power plant components are considered. The two traditional ways of modelling repairable systems in reliability theory: the - as bad as old - concept, that assumes that the replaced component is exactly under the same conditions as was the aged component before failure, and the - as good as new - concept, that assumes that the new component is under the same conditions of the replaced component when it was new, are briefly discussed in relation with the findings of the present work

  13. 26+ Year Old Photovoltaic Power Plant: Degradation and Reliability Evaluation of Crystalline Silicon Modules -- South Array

    Science.gov (United States)

    Olakonu, Kolapo

    As the use of photovoltaic (PV) modules in large power plants continues to increase globally, more studies on degradation, reliability, failure modes, and mechanisms of field aged modules are needed to predict module life expectancy based on accelerated lifetime testing of PV modules. In this work, a 26+ year old PV power plant in Phoenix, Arizona has been evaluated for performance, reliability, and durability. The PV power plant, called Solar One, is owned and operated by John F. Long's homeowners association. It is a 200 kW dc, standard test conditions (STC) rated power plant comprised of 4000 PV modules or frameless laminates, in 100 panel groups (rated at 175 kW ac). The power plant is made of two center-tapped bipolar arrays, the north array and the south array. Due to a limited time frame to execute this large project, this work was performed by two masters students (Jonathan Belmont and Kolapo Olakonu) and the test results are presented in two masters theses. This thesis presents the results obtained on the south array and the other thesis presents the results obtained on the north array. Each of these two arrays is made of four sub arrays, the east sub arrays (positive and negative polarities) and the west sub arrays (positive and negative polarities), making up eight sub arrays. The evaluation and analyses of the power plant included in this thesis consists of: visual inspection, electrical performance measurements, and infrared thermography. A possible presence of potential induced degradation (PID) due to potential difference between ground and strings was also investigated. Some installation practices were also studied and found to contribute to the power loss observed in this investigation. The power output measured in 2011 for all eight sub arrays at STC is approximately 76 kWdc and represents a power loss of 62% (from 200 kW to 76 kW) over 26+ years. The 2011 measured power output for the four south sub arrays at STC is 39 kWdc and represents a power

  14. Integrating software reliability concepts into risk and reliability modeling of digital instrumentation and control systems used in nuclear power plants

    International Nuclear Information System (INIS)

    Arndt, S. A.

    2006-01-01

    As software-based digital systems are becoming more and more common in all aspects of industrial process control, including the nuclear power industry, it is vital that the current state of the art in quality, reliability, and safety analysis be advanced to support the quantitative review of these systems. Several research groups throughout the world are working on the development and assessment of software-based digital system reliability methods and their applications in the nuclear power, aerospace, transportation, and defense industries. However, these groups are hampered by the fact that software experts and probabilistic safety assessment experts view reliability engineering very differently. This paper discusses the characteristics of a common vocabulary and modeling framework. (authors)

  15. reliability reliability

    African Journals Online (AJOL)

    eobe

    Corresponding author, Tel: +234-703. RELIABILITY .... V , , given by the code of practice. However, checks must .... an optimization procedure over the failure domain F corresponding .... of Concrete Members based on Utility Theory,. Technical ...

  16. Passive safety systems reliability and integration of these systems in nuclear power plant PSA

    International Nuclear Information System (INIS)

    La Lumia, V.; Mercier, S.; Marques, M.; Pignatel, J.F.

    2004-01-01

    Innovative nuclear reactor concepts could lead to use passive safety features in combination with active safety systems. A passive system does not need active component, external energy, signal or human interaction to operate. These are attractive advantages for safety nuclear plant improvements and economic competitiveness. But specific reliability problems, linked to physical phenomena, can conduct to stop the physical process. In this context, the European Commission (EC) starts the RMPS (Reliability Methods for Passive Safety functions) program. In this RMPS program, a quantitative reliability evaluation of the RP2 system (Residual Passive heat Removal system on the Primary circuit) has been realised, and the results introduced in a simplified PSA (Probabilistic Safety Assessment). The scope is to get out experience of definition of characteristic parameters for reliability evaluation and PSA including passive systems. The simplified PSA, using event tree method, is carried out for the total loss of power supplies initiating event leading to a severe core damage. Are taken into account: failures of components but also failures of the physical process involved (e.g. natural convection) by a specific method. The physical process failure probabilities are assessed through uncertainty analyses based on supposed probability density functions for the characteristic parameters of the RP2 system. The probabilities are calculated by MONTE CARLO simulation coupled to the CATHARE thermalhydraulic code. The yearly frequency of the severe core damage is evaluated for each accident sequence. This analysis has identified the influence of the passive system RP2 and propose a re-dimensioning of the RP2 system in order to satisfy the safety probabilistic objectives for reactor core severe damage. (authors)

  17. Evaluation of piping reliability and failure data for use in risk-based inspections of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, V. de; Soares, W.A.; Costa, A.C.L. da; Rabello, E.G.; Marques, R.O., E-mail: vasconv@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2016-07-01

    During operation of industrial facilities, components and systems can deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) involves inspection planning based on information about risks, through assessing of probability and consequence of failures. In-service inspections are used in nuclear power plants, in order to ensure reliable and safe operation. Traditional deterministic inspection approaches investigate generic degradation mechanisms on all systems. However, operating experience indicates that degradation occurs where there are favorable conditions for developing a specific mechanism. Inspections should be prioritized at these places. Risk-Informed In-service Inspections (RI-ISI) are types of RBI that use Probabilistic Safety Assessment results, increasing reliability and plant safety, and reducing radiation exposure. These assessments use both available generic reliability and failure data, as well as plant specific information. This paper proposes a method for evaluating piping reliability and failure data important for RI-ISI programs, as well as the techniques involved. (author)

  18. Evaluation of piping reliability and failure data for use in risk-based inspections of nuclear power plants

    International Nuclear Information System (INIS)

    Vasconcelos, V. de; Soares, W.A.; Costa, A.C.L. da; Rabello, E.G.; Marques, R.O.

    2016-01-01

    During operation of industrial facilities, components and systems can deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) involves inspection planning based on information about risks, through assessing of probability and consequence of failures. In-service inspections are used in nuclear power plants, in order to ensure reliable and safe operation. Traditional deterministic inspection approaches investigate generic degradation mechanisms on all systems. However, operating experience indicates that degradation occurs where there are favorable conditions for developing a specific mechanism. Inspections should be prioritized at these places. Risk-Informed In-service Inspections (RI-ISI) are types of RBI that use Probabilistic Safety Assessment results, increasing reliability and plant safety, and reducing radiation exposure. These assessments use both available generic reliability and failure data, as well as plant specific information. This paper proposes a method for evaluating piping reliability and failure data important for RI-ISI programs, as well as the techniques involved. (author)

  19. The number of measurements needed to obtain high reliability for traits related to enzymatic activities and photosynthetic compounds in soybean plants infected with Phakopsora pachyrhizi

    Science.gov (United States)

    de Oliveira, Tássia Boeno; Teodoro, Paulo Eduardo; de Alvarenga, Amauri Alves; Bhering, Leonardo Lopes; Campo, Clara Beatriz Hoffmann

    2018-01-01

    Asian rust affects the physiology of soybean plants and causes losses in yield. Repeatability coefficients may help breeders to know how many measurements are needed to obtain a suitable reliability for a target trait. Therefore, the objectives of this study were to determine the repeatability coefficients of 14 traits in soybean plants inoculated with Phakopsora pachyrhizi and to establish the minimum number of measurements needed to predict the breeding value with high accuracy. Experiments were performed in a 3x2 factorial arrangement with three treatments and two inoculations in a random block design. Repeatability coefficients, coefficients of determination and number of measurements needed to obtain a certain reliability were estimated using ANOVA, principal component analysis based on the covariance matrix and the correlation matrix, structural analysis and mixed model. It was observed that the principal component analysis based on the covariance matrix out-performed other methods for almost all traits. Significant differences were observed for all traits except internal CO2 concentration for the treatment effects. For the measurement effects, all traits were significantly different. In addition, significant differences were found for all Treatment x Measurement interaction traits except coumestrol, chitinase and chlorophyll content. Six measurements were suitable to obtain a coefficient of determination higher than 0.7 for all traits based on principal component analysis. The information obtained from this research will help breeders and physiologists determine exactly how many measurements are needed to evaluate each trait in soybean plants infected by P. pachyrhizi with a desirable reliability. PMID:29438380

  20. Reliability assessment and correlation analysis of evaluating orthodontic treatment outcome in Chinese patients

    OpenAIRE

    Song, Guang-Ying; Zhao, Zhi-He; Ding, Yin; Bai, Yu-Xing; Wang, Lin; He, Hong; Shen, Gang; Li, Wei-Ran; Baumrind, Sheldon; Geng, Zhi; Xu, Tian-Min

    2013-01-01

    This study aimed to assess the reliability of experienced Chinese orthodontists in evaluating treatment outcome and to determine the correlations between three diagnostic information sources. Sixty-nine experienced Chinese orthodontic specialists each evaluated the outcome of orthodontic treatment of 108 Chinese patients. Three different information sources: study casts (SC), lateral cephalometric X-ray images (LX) and facial photographs (PH) were generated at the end of treatment for 108 pat...

  1. Focus on 14 sewage treatment plants in the Mpumalanga Province ...

    African Journals Online (AJOL)

    In order to identify the treatment methods used in different sewage treatment plants (STPs) in the Mpumalanga Province and to determine the efficiency of wastewater treatment by these plants, municipal STPs were surveyed, and raw and treated wastewater samples collected. A total of 14 STPs were visited and the ...

  2. Study on the reliability of large coal-fired and nuclear power plants. Factors affecting power plant reliability. Volume I. Final report

    International Nuclear Information System (INIS)

    1975-01-01

    The study consisted of a comparative evaluation of 2 nuclear units (Indian Point 2 - Consolidated Edison of New York, Turkey Point 4 - Florida Power and Light Company) and 2 coal-fired units (Bull Run and Widows Creek Unit 8 - Tennessee Valley Authority). The purpose of the study was to identify and assess the underlying causes of unit reliability and the causes of the observed differences in reliability performance of the units. Recommended actions for improving the reliability of one of the study units was to be presented in a format useful to other utility companies for improving reliability of their generating units. The emphasis of the study was on the aspects of management, manning, operations, and maintenance which had a significant impact on unit reliability. Volume 1 includes a summary, a description of the major findings from the comparative evaluation, conclusions based on these findings, and recommendations for improving the reliability of the below average units

  3. Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

    2003-04-01

    The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

  4. The significance of motivation in periodontal treatment: validity and reliability of the motivation assessment scale among patients undergoing periodontal treatment.

    Science.gov (United States)

    Pac, A; Oruba, Z; Olszewska-Czyż, I; Chomyszyn-Gajewska, M

    2014-03-01

    The individual evaluation of patients' motivation should be introduced to the protocol of periodontal treatment, as it could impact positively on effective treatment planning and treatment outcomes. However, a standardised tool measuring the extent of periodontal patients' motivation has not yet been proposed in the literature. Thus, the objective of the present study was to determine the validity and reliability of the Zychlińscy motivation scale adjusted to the needs of periodontology. Cross sectional study. Department of Periodontology and Oral Medicine, Dental University Clinic, Jagiellonian University, Krakow, Poland. 199 adult periodontal patients, aged 20-78. 14-item questionnaire. The items were adopted from the original Zychlińscy motivation assessment scale. Validity and reliability of the proposed motivation assessment instrument. The assessed Cronbach's alpha of 0.79 indicates the scale is a reliable tool. Principal component analysis revealed a model with three factors, which explained half of the total variance. Those factors represented: the patient's attitude towards treatment and oral hygiene practice; previous experiences during treatment; and the influence of external conditions on the patient's attitude towards treatment. The proposed scale proved to be a reliable and accurate tool for the evaluation of periodontal patients' motivation.

  5. A task analysis-linked approach for integrating the human factor in reliability assessments of nuclear power plants

    International Nuclear Information System (INIS)

    Ryan, T.G.

    1988-01-01

    This paper describes an emerging Task Analysis-Linked Evaluation Technique (TALENT) for assessing the contributions of human error to nuclear power plant systems unreliability and risk. Techniques such as TALENT are emerging as a recognition that human error is a primary contributor to plant safety, however, it has been a peripheral consideration to data in plant reliability evaluations. TALENT also recognizes that involvement of persons with behavioral science expertise is required to support plant reliability and risk analyses. A number of state-of-knowledge human reliability analysis tools are also discussed which support the TALENT process. The core of TALENT is comprised of task, timeline and interface analysis data which provide the technology base for event and fault tree development, serve as criteria for selecting and evaluating performance shaping factors, and which provide a basis for auditing TALENT results. Finally, programs and case studies used to refine the TALENT process are described along with future research needs in the area. (author)

  6. CONSIDERATIONS FOR THE TREATMENT OF COMPUTERIZED PROCEDURES IN HUMAN RELIABILITY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; David I. Gertman

    2012-07-01

    Computerized procedures (CPs) are an emerging technology within nuclear power plant control rooms. While CPs have been implemented internationally in advanced control rooms, to date no US nuclear power plant has implemented CPs in its main control room. Yet, CPs are a reality of new plant builds and are an area of considerable interest to existing plants, which see advantages in terms of easier records management by omitting the need for updating hardcopy procedures. The overall intent of this paper is to provide a characterization of human reliability analysis (HRA) issues for computerized procedures. It is beyond the scope of this document to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper serves as a review of current HRA as it may be used for the analysis and review of computerized procedures.

  7. Brewer, Maine Wastewater Treatment Plant Recognized for Excellence

    Science.gov (United States)

    The Brewer Water Pollution Control Facility was recently honored with a 2015 Regional Wastewater Treatment Plant Excellence Award by the US Environmental Protection Agency's New England regional office.

  8. Towards energy positive wastewater treatment plants.

    Science.gov (United States)

    Gikas, Petros

    2017-12-01

    Energy requirement for wastewater treatment is of major concern, lately. This is not only due to the increasing cost of electrical energy, but also due to the effects to the carbon footprint of the treatment process. Conventional activated sludge process for municipal wastewater treatment may consume up to 60% of the total plant power requirements for the aeration of the biological tank. One way to deal with high energy demand is by eliminating aeration needs, as possible. The proposed process is based on enhanced primary solids removal, based on advanced microsieving and filtration processes, by using a proprietary rotating fabric belt MicroScreen (pore size: 100-300 μm) followed by a proprietary Continuous Backwash Upflow Media Filter or cloth media filter. About 80-90% reduction in TSS and 60-70% reduction in BOD5 has been achieved by treating raw municipal wastewater with the above process. Then the partially treated wastewater is fed to a combination low height trickling filters, combined with encapsulated denitrification, for the removal of the remaining BOD and nitrogen. The biosolids produced by the microsieve and the filtration backwash concentrate are fed to an auger press and are dewatered to about 55% solids. The biosolids are then partially thermally dried (to about 80% solids) and conveyed to a gasifier, for the co-production of thermal (which is partly used for biosolids drying) and electrical energy, through syngas combustion in a co-generation engine. Alternatively, biosolids may undergo anaerobic digestion for the production of biogas and then electric energy. The energy requirements for complete wastewater treatment, per volume of inlet raw wastewater, have been calculated to 0.057 kWh/m 3 , (or 0.087 kWh/m 3 , if UV disinfection has been selected), which is about 85% below the electric energy needs of conventional activated sludge process. The potential for net electric energy production through gasification/co-generation, per volume of

  9. Anaerobic bacteria in wastewater treatment plant.

    Science.gov (United States)

    Cyprowski, Marcin; Stobnicka-Kupiec, Agata; Ławniczek-Wałczyk, Anna; Bakal-Kijek, Aleksandra; Gołofit-Szymczak, Małgorzata; Górny, Rafał L

    2018-03-28

    The objective of this study was to assess exposure to anaerobic bacteria released into air from sewage and sludge at workplaces from a wastewater treatment plant (WWTP). Samples of both sewage and sludge were collected at six sampling points and bioaerosol samples were additionally collected (with the use of a 6-stage Andersen impactor) at ten workplaces covering different stages of the technological process. Qualitative identification of all isolated strains was performed using the biochemical API 20A test. Additionally, the determination of Clostridium pathogens was carried out using 16S rRNA gene sequence analysis. The average concentration of anaerobic bacteria in the sewage samples was 5.49 × 10 4 CFU/mL (GSD = 85.4) and in sludge-1.42 × 10 6 CFU/g (GSD = 5.1). In turn, the average airborne bacterial concentration was at the level of 50 CFU/m 3 (GSD = 5.83) and the highest bacterial contamination (4.06 × 10 3  CFU/m 3 ) was found in winter at the bar screens. In total, 16 bacterial species were determined, from which the predominant strains belonged to Actinomyces, Bifidobacterium, Clostridium, Propionibacterium and Peptostreptococcus genera. The analysis revealed that mechanical treatment processes were responsible for a substantial emission of anaerobic bacteria into the air. In both the sewage and air samples, Clostridium perfringens pathogen was identified. Anaerobic bacteria were widely present both in the sewage and in the air at workplaces from the WWTP, especially when the technological process was performed in closed spaces. Anaerobic bacteria formed small aggregates with both wastewater droplets and dust particles of sewage sludge origin and as such may be responsible for adverse health outcomes in exposed workers.

  10. Reliability study: raw and make-up water system, Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Peterman, S.M.; Wiehle, W.E.; Walder, A.; Houk, T.C.; West, R.M.

    1981-09-01

    A reliability study for determining the ability of the raw and make-up water system to provide reliable and adequate service through the year 2000 has been completed. This study includes an evaluation of the well fields, X-608 Raw Water Pump House, X-605 Booster Station Complex, X-611 Water Treatment Complex, and the associated piping. The raw and make-up water system is in good overall condition, but to maintain this condition, the reliability study team made the following recommendations: (1) increase well field capacity; (2) replace certain speed reducers at X-611; (3) repair deteriorated poles, crossarms, and accessories on F-2 and W-1 feeders; (4) stabilize the landslide in vicinity of the 48 in. raw water main; and (5) initiate further investigation, testing, or engineering studies to correct deficiencies in the supervisory control system between well fields, pump house, and X-611, and determine if the 2400 volt underground cables to X-608A wells should be replaced

  11. Natural circulation in water cooled nuclear power plants: Phenomena, models, and methodology for system reliability assessments

    International Nuclear Information System (INIS)

    2005-11-01

    In recent years it has been recognized that the application of passive safety systems (i.e. those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially to improved economics of new nuclear power plant designs. Further, the IAEA Conference on The Safety of Nuclear Power: Strategy for the Future which was convened in 1991 noted that for new plants 'the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate'. Considering the weak driving forces of passive systems based on natural circulation, careful design and analysis methods must be employed to assure that the systems perform their intended functions. To support the development of advanced water cooled reactor designs with passive systems, investigations of natural circulation are an ongoing activity in several IAEA Member States. Some new designs also utilize natural circulation as a means to remove core power during normal operation. In response to the motivating factors discussed above, and to foster international collaboration on the enabling technology of passive systems that utilize natural circulation, an IAEA Coordinated Research Project (CRP) on Natural Circulation Phenomena, Modelling and Reliability of Passive Systems that Utilize Natural Circulation was started in early 2004. Building on the shared expertise within the CRP, this publication presents extensive information on natural circulation phenomena, models, predictive tools and experiments that currently support design and analyses of natural circulation systems and highlights areas where additional research is needed. Therefore, this publication serves both to provide a description of the present state of knowledge on natural circulation in water cooled nuclear power plants and to guide the planning and conduct of the CRP in

  12. Water chemistry data acquisition, processing, evaluation and diagnostic systems in Light Water Reactors: Future improvement of plant reliability and safety

    International Nuclear Information System (INIS)

    Uchida, S.; Takiguchi, H.; Ishigure, K.

    2006-01-01

    Data acquisition, processing and evaluation systems have been applied in major Japanese PWRs and BWRs to provide (1) reliable and quick data acquisition with manpower savings in plant chemical laboratories and (2) smooth and reliable information transfer among chemists, plant operators, and supervisors. Data acquisition systems in plants consist of automatic and semi-automatic instruments for chemical analyses, e. g., X-ray fluorescence analysis and ion chromatography, while data processing systems consist of PC base-sub-systems, e.g., data storage, reliability evaluation, clear display, and document preparation for understanding the plant own water chemistry trends. Precise and reliable evaluations of water chemistry data are required in order to improve plant reliability and safety. For this, quality assurance of the water chemistry data acquisition system is needed. At the same time, theoretical models are being applied to bridge the gaps between measured water chemistry data and the information desired to understand the interaction of materials and cooling water in plants. Major models which have already been applied for plant evaluation are: (1) water radiolysis models for BWRs and PWRs; (2) crevice radiolysis model for SCC in BWRs; and (3) crevice pH model for SG tubing in PWRs. High temperature water chemistry sensors and automatic plant diagnostic systems have been applied in only restricted areas. ECP sensors are gaining popularity as tools to determine the effects of hydrogen injection in BWR systems. Automatic plant diagnostic systems based on artificial intelligence will be more popular after having sufficient experience with off line diagnostic systems. (author)

  13. Nuclear power plant maintenance personnel reliability prediction (NPP/MPRP) effort at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Knee, H.E.; Haas, P.M.; Siegel, A.I.

    1981-01-01

    Human errors committed during maintenance activities are potentially a major contribution to the overall risk associated with the operation of a nuclear power plant (NPP). An NRC-sponsored program at Oak Ridge National Laboratory is attempting to develop a quantitative predictive technique to evaluate the contribution of maintenance errors to the overall NPP risk. The current work includes a survey of the requirements of potential users to ascertain the need for and content of the proposed quantitative model, plus an initial job/task analysis to determine the scope and applicability of various maintenance tasks. In addition, existing human reliability prediction models are being reviewed and assessed with respect to their applicability to NPP maintenance tasks. This paper discusses the status of the program and summarizes the results to date

  14. Reliability Data Handbook for Piping Components in Nordic Nuclear Power Plants - R Book, Phase 2

    International Nuclear Information System (INIS)

    Hedtjaern Swaling, Vidar; Olsson, Anders

    2011-02-01

    This report presents results of a long research and development project financed by the regulatory body Straalsaekerhetsmyndigheten (SSM) (former SKI), the Swedish nuclear power plant licensees. The report presents a harmonized method for estimating Reliability Data for Piping Components in ASME code class 1 and 2 piping components (R-Book). Data in the R-Book is measured based on 'data driven' strategy. This first version of the R-Book comprises rupture frequencies and failure rates for all systems where ASME Code Class 1 or 2 events could be found in the OECD OPDE database. Nordic and Non-Nordic data are presented separately. Worldwide experience data is used to set up the relevant calculation cases, i.e. intersections of attributes for which there are at least one event present

  15. Efforts to improve safety and reliability of nuclear power plants in Kyushu Electric Power

    International Nuclear Information System (INIS)

    Yamamoto, Satoshi

    2014-01-01

    After the Fukushima accident, Kyushu Electric Power Co. took emergency safety measures requested by government to ensure power supply, coolant supply pumps and cooling water so as to keep cooling fuels in the reactor and spent fuel storage pool in case of losses of ordinary cooling capability caused by earthquake and tsunami. In order to improve safety and reliability of nuclear power plants, further efforts based on lessons learned from the Fukushima accident had been made to diversify corresponding equipment of safety measures in terms of prevention of core damage, prevention of containment failure, mitigation of radioactive materials release, cooling of spent fuel pit and ensurance of power supply, and to enhance emergency response capability so as to make operational management more complete. Additional safety measures applicable to new regulatory requirements against severe accidents were in progress. This article introduced details of such activities. (T. Tanaka)

  16. Advances in small zero-leak valves point to better nuclear power-plant reliability

    Energy Technology Data Exchange (ETDEWEB)

    Eacott, K B; Kin, J C; Hotta, Y [Dresser Japan, Ltd.

    1978-04-01

    In the selection of small valves less than two inches used for nuclear power plants, sufficient consideration must be given to the reliability to radioactive material, the easy operability, and the significant function, especially zero leak. These valves are classified into bellows and diaphragm seal types which must satisfy zero leak, 4000 cycles life test and good maintainability. Welded bellows, formed bellows, and metal diaphragms are actually used for these requirements. The construction of these types are shown. The requirements and principal specifications for these small valves are explained, and some examples are given. These zero leak valves are installed in reactor coolant loop system, borated water from B. A. system, pressurizer instrument system, containment spray system, high head system and off gas system for PWRS, and main steam line system, diesel generator cooling water system, re-circulation system, clean up water system, etc. for BWRS.

  17. Hydrothermal Liquefaction of Wastewater Treatment Plant Solids

    Energy Technology Data Exchange (ETDEWEB)

    Billing, Justin M.

    2016-10-16

    Feedstock cost is the greatest barrier to the commercial production of biofuels. The merits of any thermochemical or biological conversion process are constrained by their applicability to the lowest cost feedstocks. At PNNL, a recent resource assessment of wet waste feedstocks led to the identification of waste water treatment plant (WWTP) solids as a cost-negative source of biomass. WWTP solids disposal is a growing environmental concern [1, 2] and can account for up to half of WWTP operating costs. The high moisture content is well-suited for hydrothermal liquefaction (HTL), avoiding the costs and parasitic energy losses associated with drying the feedstock for incineration. The yield and quality of biocrude and upgraded biocrude from WWTP solids is comparable to that obtained from algae feedstocks but the feedstock cost is $500-1200 less per dry ton. A collaborative project was initiated and directed by the Water Environment & Reuse Foundation (WERF) and included feedstock identification, dewatering, shipping to PNNL, conversion to biocrude by HTL, and catalytic hydrothermal gasification of the aqueous byproduct. Additional testing at PNNL included biocrude upgrading by catalytic hydrotreatment, characterization of the hydrotreated product, and a preliminary techno-economic analysis (TEA) based on empirical results. This short article will cover HTL conversion and biocrude upgrading. The WERF project report with complete HTL results is now available through the WERF website [3]. The preliminary TEA is available as a PNNL report [4].

  18. Reliability of some ageing nuclear power plant system: a simple stochastic model

    Energy Technology Data Exchange (ETDEWEB)

    Suarez-Antola, Roberto [Catholic University of Uruguay, Montevideo (Uruguay). School of Engineering and Technologies; Ministerio de Industria, Energia y Mineria, Montevideo (Uruguay). Direccion Nacional de Energia y Tecnologia Nuclear; E-mail: rsuarez@ucu.edu.uy

    2007-07-01

    The random number of failure-related events in certain repairable ageing systems, like certain nuclear power plant components, during a given time interval, may be often modelled by a compound Poisson distribution. One of these is the Polya-Aeppli distribution. The derivation of a stationary Polya-Aeppli distribution as a limiting distribution of rare events for stationary Bernouilli trials with first order Markov dependence is considered. But if the parameters of the Polya-Aeppli distribution are suitable time functions, we could expect that the resulting distribution would allow us to take into account the distribution of failure-related events in an ageing system. Assuming that a critical number of damages produce an emergent failure, the above mentioned results can be applied in a reliability analysis. It is natural to ask under what conditions a Polya-Aeppli distribution could be a limiting distribution for non-homogeneous Bernouilli trials with first order Markov dependence. In this paper this problem is analyzed and possible applications of the obtained results to ageing or deteriorating nuclear power plant components are considered. The two traditional ways of modelling repairable systems in reliability theory: the 'as bad as old' concept, that assumes that the replaced component is exactly under the same conditions as was the aged component before failure, and the 'as good as new' concept, that assumes that the new component is under the same conditions of the replaced component when it was new, are briefly discussed in relation with the findings of the present work. (author)

  19. Application of systems engineering techniques (reliability, availability, maintainability, and dollars) to the Gas Centrifuge Enrichment Plant

    International Nuclear Information System (INIS)

    Boylan, J.G.; DeLozier, R.C.

    1982-01-01

    The systems engineering function for the Gas Centrifuge Enrichment Plant (GCEP) covers system requirements definition, analyses, verification, technical reviews, and other system efforts necessary to assure good balance of performance, safety, cost, and scheduling. The systems engineering function will support the design, installation, start-up, and operational phases of GCEP. The principal objectives of the systems engineering function are to: assure that the system requirements of the GCEP process are adequately specified and documented and that due consideration and emphasis are given to all aspects of the project; provide system analyses of the designs as they progress to assure that system requirements are met and that GCEP interfaces are compatible; assist in the definition of programs for the necessary and sufficient verification of GCEP systems; and integrate reliability, maintainability, logistics, safety, producibility, and other related specialties into a total system effort. This paper addresses the GCEP reliability, availability, maintainability, and dollars (RAM dollars) analyses which are the primary systems engineering tools for the development and implementation of trade-off studies. These studies are basic to reaching cost-effective project decisions. The steps necessary to achieve optimum cost-effective design are shown

  20. Reliability analysis of self-supply system of V-1 nuclear power plant

    International Nuclear Information System (INIS)

    Kuklik, B.

    The results are summarized of the fault tree analysis of the V-1 power plant self-consumption system. The 6 kV busbars providing power for the main circulating pumps, the steam generator feed pumps and other important components including the 0.4 kV busbars are of the highest importance for nuclear safety. A fault tree analysis was also made of the emergency core cooling system of the reactor. Dangerous faults are defined and fault trees are developed. A brief description is given of the calculation algorithm for a digital computer. Some results are discussed. The calculated reliability of the emergency core cooling system is 10 5 years, of the 6 kV busbars it is 6.6x10 4 years. In case of a permanent or a long-term outage of the 220 kV stand-bye power supply, the system reliability is reduced to 7x10 2 years. (Z.M.)

  1. Performance of wastewater treatment plants in Jordan and suitability ...

    African Journals Online (AJOL)

    STORAGESEVER

    2008-08-04

    Aug 4, 2008 ... and NH4; therefore it is classified as a strong waste. ... Key words: Wastewater, treatment plants, water reuse, wastewater characteristics, wastewater treatment,. Jordan. ..... MSc. thesis, university of Jordan. Bataineh F, Najjar ...

  2. NPDES Permit for Crow Nation Water Treatment Plants in Montana

    Science.gov (United States)

    Under NPDES permit MT-0030538, the U.S. Bureau of Indian Affairs is authorized to discharge from the Crow Agency water treatment plants via the wastewater treatment facility located in Bighorn County, Montana to the Little Bighorn River.

  3. Medicinal plants used for the treatment of jaundice and hepatitis ...

    African Journals Online (AJOL)

    The present study deals with socio-economic documentation of medicinal plant species against jaundice and hepatitis. A total of 30 plant species belonging to 24 families were reported by local practitioners for the treatment of jaundice and hepatitis. The most important plant species are Adiantum capillus, Boerhaavia ...

  4. Quantitative evaluation of the impact of human reliability in risk assessment for nuclear power plants

    International Nuclear Information System (INIS)

    Samanta, P.K.

    1981-01-01

    The role of human beings in the safe operation of a nuclear power plant has been a matter of concern. This study describes methods for the quantitative description of that role and its impact on the risk from nuclear power plants. The impact of human errors was calculated by observing the changes in risk parameters, such as core melt probability, release category probabilities, accident sequence probabilities and system unavailabilities due to changes in the contribution to unavailablity of human errors, within the framework of risk assessment methodology. It was found that for operational pressurized water reactors the opportunity for reduction in core melt probability by reducing the human error rates without simultaneous reduction of hardware failures is limited, but that core melt probability would significantly increase as human error rates increased. More importantly, most of the dominant accident sequences showed a significant increase in their probabilities with an increase in human error rates. Release categories resulting in high consequences showed a much larger sensitivity to human errors than categories resulting in low consequences. A combination of structural importance and reliability importance measure was used to describe the importance of individual errors

  5. External hazards in reliability and risk assessment of nuclear power plants

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1977-01-01

    It is current practice in the design of nuclear power generating stations to protect against the effects of significant natural and man-made external hazards which can occur at the plant site in excess of those hazards normally considered for conventional facilities. This paper is meant to identify those postulated external hazards typically considered in nuclear facility design. The paper also attempts to fulfill the following four objectives: (1) Define the current state of the art in applying reliability and risk analysis to determine external hazard design requirements. (2) Provide a ready source of literature references applicable to probabilistic design for extreme loads. (3) Provide some quantitative probability assessment estimates of external hazards. (4) Develop exclusion criteria by which postulated external hazards can be eliminated as a design basis. Rigorous evaluation of the design requirements for nuclear power plant facilities based on principles of probability and risk analysis is just beginning. It is hoped these techniques will be used more extensively in the future to provide a more rational basis for developing design requirements. (orig.) [de

  6. Investigation of the impact of main control room digitalization on operators cognitive reliability in nuclear power plants.

    Science.gov (United States)

    Zhou, Yong; Mu, Haiying; Jiang, Jianjun; Zhang, Li

    2012-01-01

    Currently, there is a trend in nuclear power plants (NPPs) toward introducing digital and computer technologies into main control rooms (MCRs). Safe generation of electric power in NPPs requires reliable performance of cognitive tasks such as fault detection, diagnosis, and response planning. The digitalization of MCRs has dramatically changed the whole operating environment, and the ways operators interact with the plant systems. If the design and implementation of the digital technology is incompatible with operators' cognitive characteristics, it may have negative effects on operators' cognitive reliability. Firstly, on the basis of three essential prerequisites for successful cognitive tasks, a causal model is constructed to reveal the typical human performance issues arising from digitalization. The cognitive mechanisms which they impact cognitive reliability are analyzed in detail. Then, Bayesian inference is used to quantify and prioritize the influences of these factors. It suggests that interface management and unbalanced workload distribution have more significant impacts on operators' cognitive reliability.

  7. Pilot plant for flue gas treatment - continuous operation tests

    International Nuclear Information System (INIS)

    Chmielewski, A.G.; Tyminski, B.; Iller, E.; Zimek, Z.; Licki, J.; Radzio, B.

    1995-01-01

    Tests of continuous operation have been performed on pilot plant at EPS Kaweczyn in the wide range of SO 2 concentration (500-3000 ppm). The bag filter has been applied for aerosol separation. The high efficiencies of SO 2 and NO x removal, approximately 90% were obtained and influenced by such process parameters as: dose, gas temperature and ammonia stoichiometry. The main apparatus of the pilot plant (e.g. both accelerators) have proved their reliability in hard industrial conditions. (Author)

  8. Improving motor reliability in nuclear power plants: Volume 1, Performance evaluation and maintenance practices

    International Nuclear Information System (INIS)

    Subudhi, M.; Gunther, W.E.; Taylor, J.H.; Sugarman, A.C.; Sheets, M.W.

    1987-11-01

    This report constitutes the first of the three volumes under this NUREG. The report presents recommendations for developing a cost-effective program for performance evaluation and maintenance of electric motors in nuclear power plants. These recommendations are based on current industry practices, available techniques for monitoring degradation in motor components, manufacturer's recommendations, operating experience, and results from two laboratory tests on aged motors. Two laboratory test reports on a small and a large motor are presented in separate volumes of this NUREG. These provide the basis for the various functional indicators recommended for maintenance programs in this report. The overall preventive maintenance program is separated into two broad areas of activity aimed at mitigating the potential effects of equipment aging: Performance Evaluation and Equipment Maintenance. The latter involves actually maintaining the condition of the equipment while the former involves those activities undertaken to monitor degradation due to aging. These monitoring methods are further categorized into periodic testing, surveillance testing, continuous monitoring and inspections. This study focuses on the methods and procedures for performing the above activities to maintain the motors operationally ready in a nuclear facility. This includes an assessment of various functional indicators to determine their suitability for trending to monitor motor component condition. The intrusiveness of test methods and the present state-of-the-art for using the test equipment in a plant environment are discussed. In conclusion, implementation of the information provided in this report, will improve motor reliability in nuclear power plants. The study indicates the kinds of tests to conduct, how and when to conduct them, and to which motors the tests should be applied. 44 refs., 12 figs., 13 tabs

  9. Reliability-based service life assessment of concrete structures in nuclear power plants: optimum inspection and repair

    International Nuclear Information System (INIS)

    Ellingwood, B.R.; Mori, Y.

    1995-01-01

    Research is being conducted to address aging management of safety-related reinforced concrete structures in nuclear power plants (NPPs). Documentation is being prepared to identify potential structural safety issues and to recommend criteria for use in evaluating reinforced concrete structures for continued service. Time-dependent reliability analysis provides the framework and quantitative tools for the condition assessment. The role of in-service inspection and repair in ensuring continued reliability in-service is examined. (author). 19 refs., 4 figs

  10. Medicinal plants indications from herbal healers for wound treatment

    OpenAIRE

    Maria Willianne Alves do Nascimento; Regina Célia Sales Santos Veríssimo; Maria Lysete de Assis Bastos; Thaís Honório Lins Bernardo

    2016-01-01

    The objective was to identify medicinal plants indicated by commercial herbal healers for wound treatment, in street markets. A descriptive study conducted in a capital city in the northeast of Brazil, through interviews. The results indicate that plant commerce by healers of both genders, aged between 37 to 52 years, from those 69.3% learned about their function with family members. Forty-eight plant species were cited for wound treatment, between those, all participants cited Barbatimão and...

  11. Determining the reliability function of the thermal power system in power plant "Nikola Tesla, Block B1"

    Directory of Open Access Journals (Sweden)

    Kalaba Dragan V.

    2015-01-01

    Full Text Available Representation of probabilistic technique for evaluation of thermal power system reliability is the main subject of this paper. The system of thermal power plant under study consists of three subsystems and the reliability assessment is based on a sixteen-year failure database. By applying the mathematical theory of reliability to exploitation research data and using complex two-parameter Weibull distribution, the theoretical reliability functions of specified system have been determined. Obtained probabilistic laws of failure occurrence have confirmed a hypothesis that the distribution of the observed random variable fully describes behaviour of such a system in terms of reliability. Shown results make possible to acquire a better knowledge of current state of the system, as well as a more accurate estimation of its behavior during future exploitation. Final benefit is opportunity for potential improvement of complex system maintenance policies aimed at the reduction of unexpected failure occurrences.

  12. Development of the software for the component reliability database system of Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sang Hoon; Kim, Seung Hwan; Choi, Sun Young [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-03-01

    A study was performed to develop the system for the component reliability database which consists of database system to store the reliability data and softwares to analyze the reliability data.This system is a part of KIND (Korea Information System for Nuclear Reliability Database).The MS-SQL database is used to stores the component population data, component maintenance history, and the results of reliability analysis. Two softwares were developed for the component reliability system. One is the KIND-InfoView for the data storing, retrieving and searching. The other is the KIND-CompRel for the statistical analysis of component reliability. 4 refs., 13 figs., 7 tabs. (Author)

  13. Medicinal Plants for the Treatment of Acne Vulgaris: A Review of Recent Evidences.

    Science.gov (United States)

    Nasri, Hamid; Bahmani, Mahmoud; Shahinfard, Najmeh; Moradi Nafchi, Atefeh; Saberianpour, Shirin; Rafieian Kopaei, Mahmoud

    2015-11-01

    Acne vulgaris affects about 85% of teenagers and may continue to adulthood. There are about two million visits to physicians per year for teenagers and the direct cost of acne treatment in the US exceeds $1 billion per year. A wide variety of treatment regimens exist for acne vulgaris including benzoil peroxide, retinoids, isotretinoids, keratolytic soaps, alpha hydroxy acids, azelaic acid, salicilic acid as well as hormonal, anti-androgen or antiseborrheic treatments. However, none of these methods is free of side effects and their exact role in therapy is not clear. In this paper apart from presenting the possible causes of acne vulgaris and its available drugs, recently published papers about medicinal plants used in the treatment of acne vulgaris were reviewed. Consumption of alternative and complementary medicine, including medicinal plants, is increasing and is common amongst patients affected by acne and infectious skin diseases. Medicinal plants have a long history of use and have been shown to possess low side effects. These plants are a reliable source for preparation of new drugs. Many plants seem to have inhibitory effects on the growth of bacteria, fungi and viruses in vitro. However, there are a few clinical evidences about the effectiveness and safety of these plants in the treatment of acne and other skin infections.

  14. Reliability analysis of mining equipment: A case study of a crushing plant at Jajarm Bauxite Mine in Iran

    International Nuclear Information System (INIS)

    Barabady, Javad; Kumar, Uday

    2008-01-01

    The performance of mining machines depends on the reliability of the equipment used, the operating environment, the maintenance efficiency, the operation process, the technical expertise of the miners, etc. As the size and complexity of mining equipments continue to increase, the implications of equipment failure become ever more critical. Therefore, reliability analysis is required to identify the bottlenecks in the system and to find the components or subsystems with low reliability for a given designed performance. It is important to select a suitable method for data collection as well as for reliability analysis. This paper presents a case study describing reliability and availability analysis of the crushing plant number 3 at Jajarm Bauxite Mine in Iran. In this study, the crushing plant number 3 is divided into six subsystems. The parameters of some probability distributions, such as Weibull, Exponential, and Lognormal distributions have been estimated by using ReliaSoft's Weibull++6 software. The results of the analysis show that the conveyer subsystem and secondary screen subsystem are critical from a reliability point of view, and the secondary crusher subsystem and conveyer subsystem are critical from an availability point of view. The study also shows that the reliability analysis is very useful for deciding maintenance intervals

  15. Human reliability analysis data obtainment through fuzzy logic in nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 Sao Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN - SP), Av. Professor Lineu Prestes 2242, 05508-000 Sao Paulo, SP (Brazil)

    2012-09-15

    Highlights: Black-Right-Pointing-Pointer Human Error Probability estimates from operator's reactions to emergency situations. Black-Right-Pointing-Pointer Human Reliability Analysis input data obtainment through fuzzy logic inference. Black-Right-Pointing-Pointer Performance Shaping Factors evaluation influence level onto the operator's actions. - Abstract: Human error has been recognized as an important factor for many industrial and nuclear accidents occurrence. Human error data is scarcely available for different reasons among which, lapses in historical database registry methodology is an important one. Human Reliability Analysis (HRA) is an usual tool employed to estimate the probability that an operator will reasonably perform a system required task in required time without degrading the system. This meta-analysis requires specific Human Error Probability estimates for most of its procedure. This work obtains Human Error Probability (HEP) estimates from operator's actions in response to emergency situations hypothesis on Research Reactor IEA-R1 from IPEN, Brazil. Through this proposed methodology HRA should be able to be performed even with shortage of related human error statistical data. A Performance Shaping Factors (PSF's) evaluation in order to classify and estimate their influence level onto the operator's actions and to determine their actual state over the plant was also done. Both HEP estimation and PSF evaluation were done based on expert judgment using interviews and questionnaires. Expert group was established based on selected IEA-R1 operators, and their evaluation were put into a knowledge representation system which used linguistic variables and group evaluation values that were obtained through Fuzzy Logic and Fuzzy Set theory. HEP obtained values show good agreement with literature published data corroborating the proposed methodology as a good alternative to be used on HRA.

  16. Human reliability analysis data obtainment through fuzzy logic in nuclear plants

    International Nuclear Information System (INIS)

    Nascimento, C.S. do; Mesquita, R.N. de

    2012-01-01

    Highlights: ► Human Error Probability estimates from operator's reactions to emergency situations. ► Human Reliability Analysis input data obtainment through fuzzy logic inference. ► Performance Shaping Factors evaluation influence level onto the operator's actions. - Abstract: Human error has been recognized as an important factor for many industrial and nuclear accidents occurrence. Human error data is scarcely available for different reasons among which, lapses in historical database registry methodology is an important one. Human Reliability Analysis (HRA) is an usual tool employed to estimate the probability that an operator will reasonably perform a system required task in required time without degrading the system. This meta-analysis requires specific Human Error Probability estimates for most of its procedure. This work obtains Human Error Probability (HEP) estimates from operator's actions in response to emergency situations hypothesis on Research Reactor IEA-R1 from IPEN, Brazil. Through this proposed methodology HRA should be able to be performed even with shortage of related human error statistical data. A Performance Shaping Factors (PSF's) evaluation in order to classify and estimate their influence level onto the operator's actions and to determine their actual state over the plant was also done. Both HEP estimation and PSF evaluation were done based on expert judgment using interviews and questionnaires. Expert group was established based on selected IEA-R1 operators, and their evaluation were put into a knowledge representation system which used linguistic variables and group evaluation values that were obtained through Fuzzy Logic and Fuzzy Set theory. HEP obtained values show good agreement with literature published data corroborating the proposed methodology as a good alternative to be used on HRA.

  17. Collection and classification of human error and human reliability data from Indian nuclear power plants for use in PSA

    International Nuclear Information System (INIS)

    Subramaniam, K.; Saraf, R.K.; Sanyasi Rao, V.V.S.; Venkat Raj, V.; Venkatraman, R.

    2000-01-01

    Complex systems such as NPPs involve a large number of Human Interactions (HIs) in every phase of plant operations. Human Reliability Analysis (HRA) in the context of a PSA, attempts to model the HIs and evaluate/predict their impact on safety and reliability using human error/human reliability data. A large number of HRA techniques have been developed for modelling and integrating HIs into PSA but there is a significant lack of HAR data. In the face of insufficient data, human reliability analysts have had to resort to expert judgement methods in order to extend the insufficient data sets. In this situation, the generation of data from plant operating experience assumes importance. The development of a HRA data bank for Indian nuclear power plants was therefore initiated as part of the programme of work on HRA. Later, with the establishment of the coordinated research programme (CRP) on collection of human reliability data and use in PSA by IAEA in 1994-95, the development was carried out under the aegis of the IAEA research contract No. 8239/RB. The work described in this report covers the activities of development of a data taxonomy and a human error reporting form (HERF) based on it, data structuring, review and analysis of plant event reports, collection of data on human errors, analysis of the data and calculation of human error probabilities (HEPs). Analysis of plant operating experience does yield a good amount of qualitative data but obtaining quantitative data on human reliability in the form of HEPs is seen to be more difficult. The difficulties have been highlighted and some ways to bring about improvements in the data situation have been discussed. The implementation of a data system for HRA is described and useful features that can be incorporated in future systems are also discussed. (author)

  18. The development of a nuclear chemical plant human reliability management approach: HRMS and JHEDI

    International Nuclear Information System (INIS)

    Kirwan, Barry

    1997-01-01

    In the late 1980's, amidst the qualitative and quantitative validation of certain Human Reliability Assessment (HRA) techniques, there was a desire for a new technique specifically for a nuclear reprocessing plant being designed. The technique was to have the following attributes: it should be data-based rather than involving pure expert judgement; it was to be flexible, so that it would allow both relatively rapid screening and more detailed assessment; and it was to have sensitivity analysis possibilities, so that Human Factors design-related parameters, albeit at a gross level, could be brought into the risk assessment equation. The techniques and literature were surveyed, and it was decided that no one technique fulfilled these requirements, and so a new approach was developed. Two techniques were devised, the Human Reliability Management System (HRMS), and the Justification of Human Error Data Information (JHEDI) technique, the latter being essentially a quicker screening version of the former. Both techniques carry out task analysis, error analysis, and Performance Shaping Factor-based quantification, but JHEDI involves less detailed assessment than HRMS. Additionally, HRMS can be utilised to determine error reduction mechanisms, based on the way the Performance Shaping Factors are contributing to the assessed error probabilities. Both techniques are fully computerised and assessments are highly documentable and auditable, which was seen as a useful feature both by the company developing the techniques, and by the regulatory authorities assessing the final output risk assessments into which these two techniques fed data. This paper focuses in particular on the quantification process used by these techniques. The quantification approach for both techniques was principally one of extrapolation from real data to the desired Human Error Probability (HEP), based on a comparison between Performance Shaping Factor (PSF) profiles for the real, and the to

  19. T-book. Reliability data of components in Nordic nuclear power plants. 6. ed

    International Nuclear Information System (INIS)

    2005-01-01

    The main objective of the T-Book is to provide reliability data for the unavailability computations that are made for each component that is considered in the compulsory, probabilistic safety assessments (PSA) of nuclear power plants. As the use of PSA is large in the normal safety work at the NPPs, there is a need for easily accessible and reliable failure data. The failure characteristics presented in the T-Book are primarily based on the failure reports stored in the central database TUD and the Licensee Event Reports delivered to the Swedish Nuclear Power Inspectorate (SKI). Fortunately, the TUD database was started already in the middle of the seventies by the Swedish power companies. In 1981, the Finnish power company TVO, operating two reactor units of Swedish design, joined the data collection system. Before the TUD data are statistically treated they are carefully examined with respect to the consistency and correctness. This T-Book comprises only critical failures, i.e. failures that stops the function of components or leads to repair. The first edition of the T-Book was issued in 1982 encompassing operational statistics from 21 reactor years. The second edition was published 1985, based on operating data covering about 40 reactor years. The T-Book 3 was published in 1992 and included data up to the operating year 1987 (108 reactor years). Edition 4 was published 1994 containing information up to and including 1992 (178 reactor years). Edition 5 was published year 2000 containing information up to and including 1996 (234 reactor years). This edition 6 contains information including year 2002 (315 reactor years). At the same time as the amount of data has increased with the successive editions of the T-Book there has been a continuous work to improve the methods for the statistical inference and related program tools, required to derive the reliability parameters from the operational data in the database. Already in the initial edition there was a Bayesian

  20. Assessment of the technological reliability of a hybrid constructed wetland for wastewater treatment in a mountain eco-tourist farm in Poland.

    Science.gov (United States)

    Jucherski, Andrzej; Nastawny, Maria; Walczowski, Andrzej; Jóźwiakowski, Krzysztof; Gajewska, Magdalena

    2017-06-01

    The aim of the present study was to assess the technological reliability of a domestic hybrid wastewater treatment installation consisting of a classic three-chambered (volume 6 m 3 ) septic tank, a vertical flow trickling bed filled with granules of a calcinated clay material (KERAMZYT), a special wetland bed constructed on a slope, and a permeable pond used as a receiver. The test treatment plant was located at a mountain eco-tourist farm on the periphery of the spa municipality of Krynica-Zdrój, Poland. The plant's operational reliability in reducing the concentration of organic matter, measured as biochemical oxygen demand (BOD 5 ) and chemical oxygen demand (COD), was 100% when modelled by both the Weibull and the lognormal distributions. The respective reliability values for total nitrogen removal were 76.8% and 77.0%, total suspended solids - 99.5% and 92.6%, and PO 4 -P - 98.2% and 95.2%, with the differences being negligible. The installation was characterized by a very high level of technological reliability when compared with other solutions of this type. The Weibull method employed for statistical evaluation of technological reliability can also be used for comparison purposes. From the ecological perspective, the facility presented in the study has proven to be an effective tool for protecting local aquifer areas.

  1. Integrated Life Cycle Management: A Strategy for Plants to Extend Operating Lifetimes Safely with High Operational Reliability

    International Nuclear Information System (INIS)

    Esselman, Thomas; Bruck, Paul; Mengers, Charles

    2012-01-01

    Nuclear plant operators are studying the possibility of extending their existing generating facilities operating lifetime to 60 years and beyond. Many nuclear plants have been granted licenses to operate their facilities beyond the original 40 year term; however, in order to optimize the long term operating strategies, plant decision-makers need a consistent approach to support their options. This paper proposes a standard methodology to support effective decision-making for the long-term management of selected station assets. Methods detailed are intended to be used by nuclear plant site management, equipment reliability personnel, long term planners, capital asset planners, license renewal staff, and others that intend to look at operation between the current time and the end of operation. This methodology, named Integrated Life Cycle Management (ILCM), will provide a technical basis to assist decision makers regarding the timing of large capital investments required to get to the end of operation safely and with high plant reliability. ILCM seeks to identify end of life cycle failure probabilities for individual plant large capital assets and attendant costs associated with their refurbishment or replacement. It will provide a standard basis for evaluation of replacement and refurbishment options for these components. ILCM will also develop methods to integrate the individual assets over the entire plant thus assisting nuclear plant decision-makers in their facility long term operating strategies. (author)

  2. The collection, storage and use of equipment performance data for the safety and reliability assessment of nuclear power plants

    International Nuclear Information System (INIS)

    Fothergill, C.D.H.

    1975-01-01

    It has been characteristic of the Nuclear Industry that it should grow up in an atmosphere where reliability and operational safety considerations have been of vital importance. Consequently all aspects of Nuclear Power Reactor design, construction and operation (in the U.K.A.E.A.) are subjected to rigorous reliability assessments, beginning with the automatic protective devices and the safety shut-down systems. This has resulted in the setting up of large and small private data stores to support this upsurgence of Safety and Reliability assessment work. Unfortunately, much of the information being stored and published falls short of the minimum requirements of Safety Assessors and Reliability Analysts who need to make use of it. That there is still an urgent need for more work to be done in the Reliability Data field is universally acknowledged. The characteristics which make up good quality reliability data must be defined and achievable minimum standards must be set for its identification, collection, storage and retrieval. To this end the United Kingdom Atomic Energy Authority have set up the Systems Reliability Service Data Bank. This includes a computerized storage facility comprised of two principal data stores: (i) Reliability Data Store, (ii) Event Data Store. The figures available in the Reliability Data Store range from those relating to the lifetimes of minute components to those obtained from the assessment of whole plants and complete assemblies. These data have been accumulated from many reliable sources both inside and outside the Nuclear Industry, including the transfer of 'live' data generated from the results of reliability surveillance exercises associated with Event Data collection. Computer techniques developed specifically for the Reliability Data Store enable further 'processing' of these data to be carried out. The Event Data Store consists of three discrete computerized data stores, each one providing the necessary storage, retrieval and

  3. Reliability and Validity of a Treatment Barriers Scale for Individuals With Alcohol Use Disorder.

    Science.gov (United States)

    Possemato, Kyle; Funderburk, Jennifer; Spinola, Suzanne; Hutchison, Dezarie; Maisto, Stephen A; Lantinga, Larry J; Oslin, David W

    2016-01-01

    Few studies have measured addiction-specific barriers to treatment. A measurement of barriers with psychometric support that has been tested in diverse samples and that assesses multiple components of addiction treatment barriers is needed to inform providers and treatment programs. This paper aims to provide an initial psychometric investigation of a measure of barriers to seeking addictions treatment. Data were collected from 196 Veterans Affairs primary care patients with Alcohol Use Disorder that participated in a randomized clinical trial. A Principal Components Analysis revealed that the 32-item Treatment Barriers Scale (TBS) can be reduced to 14 items, measuring 4 factors: stigma, dislike of the treatment process, alcohol problem identification, and logistical concerns. Acceptable internal consistent reliability (α = .64-.76) and excellent precision of alpha (α = 0.001-0.009) was found for each subscale. Support for the measure's concurrent validity was found, for example, participants who reported more motivation to reduce their drinking perceived significantly fewer barriers to care. Support for the measure's predictive validity was also found, including that more barriers were related to future drinking among all participants and less mental health and addictions treatment visits among participants in one treatment condition. Conclusions/ Importance: Our results provide initial support for the utility of the TBS-14 among primary care patients with Alcohol Use Disorder. Use of the TBS-14 could enable healthcare providers to better understand patient-specific treatment barriers, provide corrective information on treatment misconceptions, and inform individualized treatment plans that increase patient engagement in addiction services.

  4. Development of corrosion models to ensure reliable performance of nuclear power plants

    International Nuclear Information System (INIS)

    Kritzky, V.G.; Stjazhkin, P.S.

    1993-01-01

    The safety and reliability of the coolant circuits in nuclear power plants depend much on corrosion and corrosion products transfer processes. Various empirical models have been developed which are applicable to particular sets of operational conditions. In our laboratory a corrosion model has been worked out, which is based on the thermodynamic properties of the compounds, participating in corrosion process and on the assumption, that the corrosion process is controlled by the solubilities of the corrosion products forming the surface oxide layer. The validity of the model has been verified by use of retrospective experimental data, which have been obtained for a series of structural materials such as e.g., carbon and stainless steels, Cu-, Al-, and Zr alloys. With regard for hydriding the model satisfactorily describes stress corrosion cracking process in water-salt environments. This report describes a model based on the thermodynamic properties of the compounds participating in the corrosion process, and on the assumption that the corrosion process is controlled by the solubilities of the corrosion products forming the surface oxide layer

  5. IAEA TC Project 'Strengthening safety and reliability of fuel and materials in nuclear power plants'

    International Nuclear Information System (INIS)

    Makihara, Y.

    2008-01-01

    The Regional TC Project in Europe RER9076 'Strengthening Safety and Reliability of Fuel and Materials in Nuclear Power Plants' was launched in 2003 as a four-year project and was subsequently extended in 2006 to run through 2008. The purpose of the Project is to support the Central and Eastern European countries with the necessary tools to fulfill their own fuel and material licensing needs. The main objective will be to provide quality data on fuel and materials irradiated in power reactors and in dedicated experiments carried out in material test reactors (MTRs). Within the framework of the Project, ten tasks were implemented. These included experiments performed at the test facilities in the region, training courses and workshops related to fuel safety. While several tasks are expected to be completed by the end of RER9076, some remain. It would be desirable to initiate a new RER Project from the next TC cycle (2009-2011) in order to take over RER9076 and to implement new tasks required for enhancing fuel safety in the region. (author)

  6. Microbial Communities in Danish Wastewater Treatment Plants with Nutrient Removal

    DEFF Research Database (Denmark)

    Mielczarek, Artur Tomasz

    Activated sludge treatment plants are the most used wastewater treatment systems worldwide for biological nutrient removal from wastewater. Nevertheless, the treatment systems have been for many years operated as so called “black-box”, where specific process parameters were adjusted without...... that plants with return sludge Side-Stream Hydrolysis (SSH) instead of the normal anaerobic process tank tended to have significantly fewer unwanted GAOs in contrast to many plants with traditional mainstream anaerobic tank and thus it was proposed that this system might be an effective strategy of control...

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

    International Nuclear Information System (INIS)

    Shcherbinskij, V.G.

    1981-01-01

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

  8. Beliefs concerning the reliability of nuclear power plant in-service inspections; Uskomuksia ydinvoimalaitoksissa suoritettavien tarkastusten luotettavuudesta

    Energy Technology Data Exchange (ETDEWEB)

    Kettunen, J. [VTT Automation, Espoo (Finland)

    1997-01-01

    The aim of the study was to investigate belief systems held by the officials responsible for the planning and supervision of NDT operations within the Finnish nuclear industry. They were asked to express their opinions on (1) the reliability of NDT methods in general, (2) the factors influencing the reliability of in-service inspections, and (3) the degree of reliability of the current inspections operations conducted by means of NDT methods in the Finnish nuclear power plants. Another goal of the study was to assess the adequacy of officials` beliefs (or belief systems). The research data was collected by interviewing representatives from Finnish power companies (Imatran Voima Oy and Teollisuuden Voima Oy), independent inspection organisations, and the Finnish Centre for Radiation and Nuclear Safety (STUK). The adequacy of the beliefs expressed was assessed by means of the results obtained from international NDT reliability studies and on the basis of interviewees` own justification. (refs.).

  9. Survey of bayesian belif nets for quantitative reliability assessment of safety critical software used in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Eom, H.S.; Sung, T.Y.; Jeong, H.S.; Park, J.H.; Kang, H.G.; Lee, K

    2001-03-01

    As part of the Probabilistic Safety Assessment of safety grade digital systems used in Nuclear Power plants research, measures and methodologies applicable to quantitative reliability assessment of safety critical software were surveyed. Among the techniques proposed in the literature we selected those which are in use widely and investigated their limitations in quantitative software reliability assessment. One promising methodology from the survey is Bayesian Belief Nets (BBN) which has a formalism and can combine various disparate evidences relevant to reliability into final decision under uncertainty. Thus we analyzed BBN and its application cases in digital systems assessment area and finally studied the possibility of its application to the quantitative reliability assessment of safety critical software.

  10. Survey of bayesian belif nets for quantitative reliability assessment of safety critical software used in nuclear power plants

    International Nuclear Information System (INIS)

    Eom, H. S.; Sung, T. Y.; Jeong, H. S.; Park, J. H.; Kang, H. G.; Lee, K.

    2001-03-01

    As part of the Probabilistic Safety Assessment of safety grade digital systems used in Nuclear Power plants research, measures and methodologies applicable to quantitative reliability assessment of safety critical software were surveyed. Among the techniques proposed in the literature we selected those which are in use widely and investigated their limitations in quantitative software reliability assessment. One promising methodology from the survey is Bayesian Belief Nets (BBN) which has a formalism and can combine various disparate evidences relevant to reliability into final decision under uncertainty. Thus we analyzed BBN and its application cases in digital systems assessment area and finally studied the possibility of its application to the quantitative reliability assessment of safety critical software

  11. Reliability of the Solar One plant during the power production phase: August 1, 1984--July 31, 1987

    Energy Technology Data Exchange (ETDEWEB)

    Kolb, G.J.; Lopez, C.W.

    1988-10-01

    The power production phase at Solar One spanned three years from August 1, 1984 through July 31, 1987. In that period the plant achieved an average availability, during hours of sunshine, of 81.7%. This report presents the frequencies and causes of the plant outages that occurred. The eleven most important causes composed 75% of the total outage time. Qualitative insights related to the origin and mitigation of these causes are provided. Also presented are insights and statistics regarding the reliability of the heliostat field. The quantitative and qualitative information presented in this report will be useful to studies aimed at improving the reliability of future solar central receiver power plants. 20 refs., 11 figs., 3 tabs.

  12. 40 CFR 63.1581 - Does the subpart distinguish between different types of POTW treatment plants?

    Science.gov (United States)

    2010-07-01

    ... different types of POTW treatment plants? 63.1581 Section 63.1581 Protection of Environment ENVIRONMENTAL... treatment plants? Yes, POTW treatment plants are divided into two subcategories. A POTW treatment plant which does not meet the characteristics of an industrial POTW treatment plant belongs in the non...

  13. A human reliability analysis of the Three Mile power plant accident considering the THERP and ATHEANA methodologies

    International Nuclear Information System (INIS)

    Fonseca, Renato Alves da

    2004-03-01

    The main purpose of this work is the study of human reliability using the THERP (Technique for Human Error Prediction) and ATHEANA methods (A Technique for Human Error Analysis), and some tables and also, from case studies presented on the THERP Handbook to develop a qualitative and quantitative study of nuclear power plant accident. This accident occurred in the TMI (Three Mile Island Unit 2) power plant, PWR type plant, on March 28th, 1979. The accident analysis has revealed a series of incorrect actions, which resulted in the Unit 2 shut down and permanent loss of the reactor. This study also aims at enhancing the understanding of the THERP method and ATHEANA, and of its practical applications. In addition, it is possible to understand the influence of plant operational status on human failures and of these on equipment of a system, in this case, a nuclear power plant. (author)

  14. Reliability of plant root comet assay in comparison with human leukocyte comet assay for assessment environmental genotoxic agents.

    Science.gov (United States)

    Reis, Gabriela Barreto Dos; Andrade-Vieira, Larissa Fonseca; Moraes, Isabella de Campos; César, Pedro Henrique Souza; Marcussi, Silvana; Davide, Lisete Chamma

    2017-08-01

    Comet assay is an efficient test to detect genotoxic compounds based on observation of DNA damage. The aim of this work was to compare the results obtained from the comet assay in two different type of cells extracted from the root tips from Lactuca sativa L. and human blood. For this, Spent Pot Liner (SPL), and its components (aluminum and fluoride) were applied as toxic agents. SPL is a solid waste generated in industry from the aluminum mining and processing with known toxicity. Three concentrations of all tested solutions were applied and the damages observed were compared to negative and positive controls. It was observed an increase in the frequency of DNA damage for human leukocytes and plant cells, in all treatments. On human leukocytes, SPL induced the highest percentage of damage, with an average of 87.68%. For root tips cells of L. sativa the highest percentage of damage was detected for aluminum (93.89%). Considering the arbitrary units (AU), the average of nuclei with high levels of DNA fragmentation was significant for both cells type evaluated. The tested cells demonstrated equal effectiveness for detection of the genotoxicity induced by the SPL and its chemical components, aluminum and fluoride. Further, using a unique method, the comet assay, we proved that cells from root tips of Lactuca sativa represent a reliable model to detect DNA damage induced by genotoxic pollutants is in agreement of those observed in human leukocytes as model. So far, plant cells may be suggested as important system to assess the toxicological risk of environmental agents. Copyright © 2017 Elsevier Inc. All rights reserved.

  15. Reliability, validity and treatment sensitivity of the Schizophrenia Cognition Rating Scale.

    Science.gov (United States)

    Keefe, Richard S E; Davis, Vicki G; Spagnola, Nathan B; Hilt, Dana; Dgetluck, Nancy; Ruse, Stacy; Patterson, Thomas D; Narasimhan, Meera; Harvey, Philip D

    2015-02-01

    Cognitive functioning can be assessed with performance-based assessments such as neuropsychological tests and with interview-based assessments. Both assessment methods have the potential to assess whether treatments for schizophrenia improve clinically relevant aspects of cognitive impairment. However, little is known about the reliability, validity and treatment responsiveness of interview-based measures, especially in the context of clinical trials. Data from two studies were utilized to assess these features of the Schizophrenia Cognition Rating Scale (SCoRS). One of the studies was a validation study involving 79 patients with schizophrenia assessed at 3 academic research centers in the US. The other study was a 32-site clinical trial conducted in the US and Europe comparing the effects of encenicline, an alpha-7 nicotine agonist, to placebo in 319 patients with schizophrenia. The SCoRS interviewer ratings demonstrated excellent test-retest reliability in several different circumstances, including those that did not involve treatment (ICC> 0.90), and during treatment (ICC>0.80). SCoRS interviewer ratings were related to cognitive performance as measured by the MCCB (r=-0.35), and demonstrated significant sensitivity to treatment with encenicline compared to placebo (Pcognition in schizophrenia, and may be useful for clinical practice. The weaknesses of the SCoRS include its reliance on informant information, which is not available for some patients, and reduced validity when patient's self-report is the sole information source. Copyright © 2014 Elsevier B.V. and ECNP. All rights reserved.

  16. [Reliability of endocervical curettage after conservative treatment of intraepithelial neoplasia of the cervix].

    Science.gov (United States)

    Lecointre, L; Akladios, C-Y; Averous, G; Lefebvre, F; Baulon, E; Thoma, V; Fender, M; Baldauf, J-J

    2015-02-01

    To evaluate the reliability of endocervical curettage (ECC) in patients previously treated for CIN. Retrospective analysis of data from 85 patients between January 1985 and December 2011 who received an ECC during monitoring after treatment of CIN. The reliability of the ECC was evaluated by comparison with the final histological analysis of the surgical specimen or the data for subsequent cyto-colpo-histological follow-up. Patients were referred to colposcopy either within the immediate post-treatment monitoring (n=42), meanly 9.7±5.3 months after treatment, or if cytological abnormalities were detected during long-term monitoring, meanly 78.6±52.4 months after treatment. Colposcopy was unsatisfactory in 75.3% of patients and normal colposcopic findings were found in 80% of patients. A perfect agreement between the ECC and the endocervical final diagnosis was noted in 68 patients (80%). For the diagnosis of severe cervical lesions (CIN 2+) ECC had a sensitivity of 86.2% (68.3-96.1), a specificity of 94.6% (85.1-98.9) and positive and negative predictive values of 61.4% (47.6-74.0) and 93% (83.0-98.1), respectively. The high sensitivity and negative predictive value of ECC for the diagnosis of severe post-therapeutic endocervical lesions avoid iterative treatment without increasing the risk of progression of a lesion to cancer. Copyright © 2014 Elsevier Masson SAS. All rights reserved.

  17. Work Practice, Safety and Heedfulness. Studies of Organizational Reliability in Hospitals and Nuclear Power Plants

    International Nuclear Information System (INIS)

    Gauthereau, Vincent

    2003-01-01

    The study of safety in complex systems has focused on different issues over the past decades. This focus was often linked to the conclusions of previous accidents'/incidents' analyses. When accidents were attributed to technical causes, safety research focused on technical developments. When they were later attributed to 'human errors', safety research focused on this 'component'. And when, since the mid-eighties accidents have been attributed to 'organizational factors', safety research has focused on these very same 'organizational factors'. The present thesis argues for a 'practice view' over safety to be taken. This view is mainly drawn from the field of research on High Reliability Organizations (HRO). HRO theorists' point of view on safety is that we can operate complex systems safely despite the fact that we have made them so complex that they are prone to 'normal accidents'. Humans involved in the operation of our systems actually create safety. Safety is formed through the adaptation of work practice to local conditions, and this adaptation is part of safe operation. Safety is not only a substantial quality of our socio-technical systems: the discursive dimension of safety actually seems to be a central component of safety creation. However, the adaptive ability of HRO can sometimes become their downfall. Adaptation, which is the backbone of safety, can sometimes be a drawback as well. Consequently, the practice view of safety, proposed in the present work, argues that we need to further comprehend how work practice evolves over time, and more specifically what are the inherent characteristics of work practice that create this evolution. Empirical studies from health-care and nuclear power generation highlight different details about organizational reliability. For instance, one study of planning at a nuclear power plant draws our attention to the different roles of planning in the organization. Another study, within heath-care, underlines the evolution of

  18. Identification and Control of Nutrient Removing Processes in Wastewater Treatment Plants

    DEFF Research Database (Denmark)

    Nielsen, Marinus K.; Madsen, Henrik; Carstensen, Niels Jacob

    1994-01-01

    the possibility of using statistical methods for identifying dynamical models for the biological processes. These models can then be used for simulating various control strategies and the parameters of the controllers can be found by off-line optimization. Simulation studies have shown that considerable savings......Today the use of on-line control for wastewater treatment plants is very low. A main reason is the lack of quality of the data, and the fact that more sophisticated control strategies must be based on a model of the dynamics of the biological processes. This paper discusses the historical reasons...... for the limited use of modern control strategies for wastewater treatment plants. Today, however, on-line nutrient sensors are more reliable. In the present context the use of on-line monitored values of ammonia, nitrate and phosphate from a full scale plant are used as the background for discussing...

  19. A systematic methodology for controller tuning in wastewater treatment plants

    DEFF Research Database (Denmark)

    Mauricio Iglesias, Miguel; Jørgensen, S.B.; Sin, G.

    2012-01-01

    Wastewater treatment plants are typically subject to continuous disturbances caused by influent variations which exhibits diurnal patterns as well as stochastic changes due to rain and storm water events. In order to achieve an efficient operation, the control system of the plant should be able t...

  20. Benchmarking of Control Strategies for Wastewater Treatment Plants

    DEFF Research Database (Denmark)

    Wastewater treatment plants are large non-linear systems subject to large perturbations in wastewater flow rate, load and composition. Nevertheless these plants have to be operated continuously, meeting stricter and stricter regulations. Many control strategies have been proposed in the literature...

  1. Use of robotics in a Radwaste treatment plant

    International Nuclear Information System (INIS)

    Leeks, C.W.E.

    1991-01-01

    A 762 Unimate Puma, clean room standard Robot has been installed and commissioned in the Radwaste Treatment Plant at the Winfrith Technology Centre. The robot interacts with a variety of purpose designed tools and proprietary welding equipment. It performs 13 dedicated tasks in the final closure and health physics operations, before the 500 litre waste drum is despatched from the plant. (author)

  2. Radioactive waste treatment technology at Czech nuclear power plants

    International Nuclear Information System (INIS)

    Kulovany, J.

    2001-01-01

    This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

  3. Performance of wastewater treatment plants in Jordan and suitability ...

    African Journals Online (AJOL)

    STORAGESEVER

    2008-08-04

    Aug 4, 2008 ... while the available sources of water are limited and de-. *Corresponding author. ... 186223 m3/d inflow to Asamra wastewater treatment plant. (ASTP) (Bataineh et al., ..... MSc. thesis, university of Jordan. Bataineh F, Najjar M, ...

  4. Ethnobiological survey of plants and animals used for the treatment ...

    African Journals Online (AJOL)

    Ethnobiological survey of plants and animals used for the treatment of acute respiratory ... African Journal of Traditional, Complementary and Alternative Medicines ... Methods: It is a descriptive exploratory study with a quantitative approach, ...

  5. Wastewater Treatment Plants, North America, 2010, Dun and Bradstreet

    Data.gov (United States)

    U.S. Environmental Protection Agency — D&B 20101220 Wastewater Treatment Plants Points for the United States, including Puerto Rico and the US Virgin Islands, Canada, and Mexico, Released Quarterly...

  6. Assessment of wastewater treatment plant effluent effects on fish reproduction

    Science.gov (United States)

    Wastewater treatment plant (WWTP) effluents are known contributors of chemical mixtures into the environment. Of particular concern are endocrine-disrupting compounds that can affect hypothalamic-pituitary-gonadal axis function in exposed organisms. The present study examined t...

  7. EPA Facility Registry Service (FRS): Wastewater Treatment Plants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains data on wastewater treatment plants, based on EPA's Facility Registry Service (FRS), EPA's Integrated Compliance Information System (ICIS)...

  8. A reliability program for emergency diesel generators at nuclear power plants: Program structure

    International Nuclear Information System (INIS)

    Lofgren, E.V.; DeMoss, G.M.; Fragola, J.R.; Appignani, P.L.; Delarche, G.; Boccio, J.

    1988-04-01

    The purpose of this report is to provide technical guidelines for NRC staff use in the development of positions for evaluating emergency diesel generator (EDG) reliability programs. Such reviews will likely result following resolution of USI A-44 and GSI B-56. The diesel generator reliability program is a management system for achieving and maintaining a selected (or target) level of reliability. This can be achieved by: (1) understanding the factors that control the EDG reliability and (2) then applying reliability and maintenance techniques in the proper proportion to achieve selected performance goals. The concepts and guidelines discussed in this report are concepts and approaches that have been successful in applications where high levels of reliability must be maintained. Both an EDG reliability program process and a set of review items for NRC use are provided. The review items represent a checklist for reviewing EDG reliability programs. They do not, in themselves, constitute a reliability program. Rather, the review items are those distinctive features of a reliability program that must be present for the program to be effective

  9. Reliability modeling of safety-critical network communication in a digitalized nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kim, Hee Eun; Son, Kwang Seop; Shin, Sung Min; Lee, Seung Jun; Kang, Hyun Gook

    2015-01-01

    The Engineered Safety Feature-Component Control System (ESF-CCS), which uses a network communication system for the transmission of safety-critical information from group controllers (GCs) to loop controllers (LCs), was recently developed. However, the ESF-CCS has not been applied to nuclear power plants (NPPs) because the network communication failure risk in the ESF-CCS has yet to be fully quantified. Therefore, this study was performed to identify the potential hazardous states for network communication between GCs and LCs and to develop quantification schemes for various network failure causes. To estimate the risk effects of network communication failures in the ESF-CCS, a fault-tree model of an ESF-CCS signal failure in the containment spray actuation signal condition was developed for the case study. Based on a specified range of periodic inspection periods for network modules and the baseline probability of software failure, a sensitivity study was conducted to analyze the risk effect of network failure between GCs and LCs on ESF-CCS signal failure. This study is expected to provide insight into the development of a fault-tree model for network failures in digital I&C systems and the quantification of the risk effects of network failures for safety-critical information transmission in NPPs. - Highlights: • Network reliability modeling framework for digital I&C system in NPP is proposed. • Hazardous states of network protocol between GC and LC in ESF-CCS are identified. • Fault-tree model of ESF-CCS signal failure in ESF actuation condition is developed. • Risk effect of network failure on ESF-CCS signal failure is analyzed.

  10. System Statement of Tasks of Calculating and Providing the Reliability of Heating Cogeneration Plants in Power Systems

    Science.gov (United States)

    Biryuk, V. V.; Tsapkova, A. B.; Larin, E. A.; Livshiz, M. Y.; Sheludko, L. P.

    2018-01-01

    A set of mathematical models for calculating the reliability indexes of structurally complex multifunctional combined installations in heat and power supply systems was developed. Reliability of energy supply is considered as required condition for the creation and operation of heat and power supply systems. The optimal value of the power supply system coefficient F is based on an economic assessment of the consumers’ loss caused by the under-supply of electric power and additional system expences for the creation and operation of an emergency capacity reserve. Rationing of RI of the industrial heat supply is based on the use of concept of technological margin of safety of technological processes. The definition of rationed RI values of heat supply of communal consumers is based on the air temperature level iside the heated premises. The complex allows solving a number of practical tasks for providing reliability of heat supply for consumers. A probabilistic model is developed for calculating the reliability indexes of combined multipurpose heat and power plants in heat-and-power supply systems. The complex of models and calculation programs can be used to solve a wide range of specific tasks of optimization of schemes and parameters of combined heat and power plants and systems, as well as determining the efficiency of various redundance methods to ensure specified reliability of power supply.

  11. Suitability review of FMEA and reliability analysis for digital plant protection system and digital engineered safety features actuation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, I. S.; Kim, T. K.; Kim, M. C.; Kim, B. S.; Hwang, S. W.; Ryu, K. C. [Hanyang Univ., Seoul (Korea, Republic of)

    2000-11-15

    Of the many items that should be checked out during a review stage of the licensing application for the I and C system of Ulchin 5 and 6 units, this report relates to a suitability review of the reliability analysis of Digital Plant Protection System (DPPS) and Digital Engineered Safety Features Actuation System (DESFAS). In the reliability analysis performed by the system designer, ABB-CE, fault tree analysis was used as the main methods along with Failure Modes and Effect Analysis (FMEA). However, the present regulatory technique dose not allow the system reliability analysis and its results to be appropriately evaluated. Hence, this study was carried out focusing on the following four items ; development of general review items by which to check the validity of a reliability analysis, and the subsequent review of suitability of the reliability analysis for Ulchin 5 and 6 DPPS and DESFAS L development of detailed review items by which to check the validity of an FMEA, and the subsequent review of suitability of the FMEA for Ulchin 5 and 6 DPPS and DESFAS ; development of detailed review items by which to check the validity of a fault tree analysis, and the subsequent review of suitability of the fault tree for Ulchin 5 and 6 DPPS and DESFAS ; an integrated review of the safety and reliability of the Ulchin 5 and 6 DPPS and DESFAS based on the results of the various reviews above and also of a reliability comparison between the digital systems and the comparable analog systems, i.e., and analog Plant Protection System (PPS) and and analog Engineered Safety Features Actuation System (ESFAS). According to the review mentioned above, the reliability analysis of Ulchin 5 and 6 DPPS and DESFAS generally satisfies the review requirements. However, some shortcomings of the analysis were identified in our review such that the assumed test periods for several equipment were not properly incorporated in the analysis, and failures of some equipment were not included in the

  12. Exploration of reliability assurance program (RAP) for advanced nuclear power plant

    International Nuclear Information System (INIS)

    Chen Fang; Xu Rongbin

    2009-01-01

    This article describes the new requirements in US SRP on Reliability Assurance Program, inquires into the evolution of the reliability assurance requirements, and investigates the regulatory requirements on reliability assurance program for advanced reactors, it's main contents, and evaluation review practices and related issues, with the aim of enabling staff to understand be familiar and pay attention to this engineering program. This article may be as a reference for related workers. (authors)

  13. Importance of independent and dependent human error to system reliability and plant safety

    International Nuclear Information System (INIS)

    Dach, K.

    1988-08-01

    Uncertainty analysis of the quantification of the unavailability for the emergency core cooling system was made. The reliability analysis of the low pressure injection system (LPIS) of the ECCS of WWER-440 reactor was also performed. Results of reliability analysis proved that LPIS reliability under normal conditions is sufficient and can be increased by two orders of magnitude. This increase in reliability can be achieved by means of simple changes such as securing an opening of the quick-acting fittings at LPIS discharge line. A method for analysis of systems uncertainty with periodic inspected components was elaborated and verified by performing an analysis of the medium size system. Refs, figs and tabs

  14. Sludge quantification at water treatment plant and its management scenario.

    Science.gov (United States)

    Ahmad, Tarique; Ahmad, Kafeel; Alam, Mehtab

    2017-08-15

    Large volume of sludge is generated at the water treatment plants during the purification of surface water for potable supplies. Handling and disposal of sludge require careful attention from civic bodies, plant operators, and environmentalists. Quantification of the sludge produced at the treatment plants is important to develop suitable management strategies for its economical and environment friendly disposal. Present study deals with the quantification of sludge using empirical relation between turbidity, suspended solids, and coagulant dosing. Seasonal variation has significant effect on the raw water quality received at the water treatment plants so forth sludge generation also varies. Yearly production of the sludge in a water treatment plant at Ghaziabad, India, is estimated to be 29,700 ton. Sustainable disposal of such a quantity of sludge is a challenging task under stringent environmental legislation. Several beneficial reuses of sludge in civil engineering and constructional work have been identified globally such as raw material in manufacturing cement, bricks, and artificial aggregates, as cementitious material, and sand substitute in preparing concrete and mortar. About 54 to 60% sand, 24 to 28% silt, and 16% clay constitute the sludge generated at the water treatment plant under investigation. Characteristics of the sludge are found suitable for its potential utilization as locally available construction material for safe disposal. An overview of the sustainable management scenario involving beneficial reuses of the sludge has also been presented.

  15. Specification of a Human Reliability Data Bank for conducting HRA segments of PRAs for nuclear power plants

    International Nuclear Information System (INIS)

    Comer, M.K.; Donovan, M.D.

    1985-02-01

    The US Nuclear Regulatory Commission (NRC), Sandia National Laboratories (SNL), and General Physics Corporation have conducted a research program to develop a Human Reliability Data Bank for nuclear power industry probabilistic risk assessment (PRA). As part of this program, a survey of existing human reliability data banks from other industries was conducted and a concept of a Data Bank for the nuclear industry was developed. The results of these efforts were published in the two volumes of NUREG/CR-2744: ''Human Reliability Data Bank for Nuclear Power Plant Operations: Volume 1, A Review of Existing Human Reliability Data Banks, and Volume 2, A Data Bank Concept and System Description.'' This document, NUREG/CR-4010, is the revised technical specification for the Human Reliability Data Bank. The organization of the Data Bank and a description of a data publication, the Human Reliability Data Manual, are provided. Details of the administration and operation of the Data Bank are discussed. Appendices present the detailed procedures for processing data, revising the Data Manual, operating the Data Bank, and reviewing data for the Data Bank. The final appendix is a skeleton version (structure only) of the Data Manual

  16. Stimulation treatments of large-seed leguminous plants Pt. 1

    International Nuclear Information System (INIS)

    Nagy, Istvan; Borbely, Ferenc; Nagy, Janos; Dezsi, Zoltan

    1983-01-01

    The effect of low dose X-ray irradiation on the sprouting and initial growth of some leguminous plants was studied. After having the seeds of peas, beans, lupines and horse beans irradiated, the sprouting rate, the amount of sprouting plants, the length of the roots, the sprouts and the sprouting plants, the electrolyte conductivity and the water uptake were determined. The height and the amount of the plants were measured after a period of 6 weeks. According to the sprout-length values, an increased variation in the plant features can be observed as a result of irradiation treatment: both stimulation and inhibition of plant growth occured, depending on the variety of the leguminosae. The indices of sprouting and initial growth agree well with each other. (V.N.)

  17. Reliability Calculations

    DEFF Research Database (Denmark)

    Petersen, Kurt Erling

    1986-01-01

    Risk and reliability analysis is increasingly being used in evaluations of plant safety and plant reliability. The analysis can be performed either during the design process or during the operation time, with the purpose to improve the safety or the reliability. Due to plant complexity and safety...... and availability requirements, sophisticated tools, which are flexible and efficient, are needed. Such tools have been developed in the last 20 years and they have to be continuously refined to meet the growing requirements. Two different areas of application were analysed. In structural reliability probabilistic...... approaches have been introduced in some cases for the calculation of the reliability of structures or components. A new computer program has been developed based upon numerical integration in several variables. In systems reliability Monte Carlo simulation programs are used especially in analysis of very...

  18. influence of treatment of seed potato tubers with plant crude

    African Journals Online (AJOL)

    ACSS

    essential oil extracts, on the growth and yield of the potato crop. Treatments consisted of .... Seed potato tuber treatment with plant crude essential oil extracts. 297 were pipetted on to ..... and clove essential oils on sprout suppression in potato ...

  19. Conceptual project of waste treatment plant of CDTN

    International Nuclear Information System (INIS)

    Gabriel, J.L.; Astolfi, D.

    1983-01-01

    This paper presents the conceptual project of the waste treatment plant of CDTN. Several areas, such as: process area, material entrance and exit area are studied. The treatment processes are: evaporation, filtration, cementation, cutting and processing of solid wastes. (C.M.)

  20. Adaptive model based control for wastewater treatment plants

    NARCIS (Netherlands)

    de Niet, Arie; van de Vrugt, Noëlle Maria; Korving, Hans; Boucherie, Richardus J.; Savic, D.A.; Kapelan, Z.; Butler, D.

    2011-01-01

    In biological wastewater treatment, nitrogen and phosphorous are removed by activated sludge. The process requires oxygen input via aeration of the activated sludge tank. Aeration is responsible for about 60% of the energy consumption of a treatment plant. Hence optimization of aeration can

  1. Hydraulic modelling of drinking water treatment plant operations

    NARCIS (Netherlands)

    Worm, G.I.M.; Mesman, G.A.M.; Van Schagen, K.M.; Borger, K.J.; Rietveld, L.C.

    2009-01-01

    The flow through a unit of a drinking water treatment plant is one of the most important parameters in terms of a unit's effectiveness. In the present paper, a new EPAnet library is presented with the typical hydraulic elements for drinking water treatment processes well abstraction, rapid sand

  2. Handwriting on the power plant wall: flue gas treatment

    Energy Technology Data Exchange (ETDEWEB)

    Troupe, J.S.

    1979-08-01

    This paper reviews the present state of flue gas treatment technology. Describes the operation of four basic types of devices used by electric utilities:- mechanical dust collectors, electrostatic precipitators, wet scrubbers and fabric filters. Considers their reliability and cost, and outlines possible future trends.

  3. Electron beam treatment plant for textile dyeing wastewater

    International Nuclear Information System (INIS)

    Han, B.; Kim, J.; Kim, Y.; Choi, J.; Ahn, S.; Makarov, I.E.; Ponomarev, A.V.

    2006-01-01

    A pilot plant for treating 1,000 m 3 of textile dyeing wastewater per day with electron beam has constructed and operated continuously in Daegu, Korea since 1998. This plant is combined with biological treatment system and it shows the reduction of chemical reagent consumption, and also the reduction in retention time with the increase in removal efficiencies of COD Cr and BOD 5 up to 30∼40%. Increase in biodegradability after radiation treatment of aqueous-organic systems is due to radiolytical conversions of non-biodegradable compounds. On the basis of data obtained from pilot plant operation, construction of actual industrial scale plant has started in 2003, and will be finished by 2005. This plant is located on the area of existing wastewater treatment facility (Daegu Dyeing Industrial Complex) and to have treatment capacity 10,000 m 3 of wastewater per day using one 1 MeV, 400 kW accelerator, and combined with existing bio- treatment facility. The overall construction cost and the operation cost in the radiation processing, when compared to other conventional and advanced oxidation techniques, are more cost-effective and convenient for wastewater treatment. This project is supported by the International Atomic Energy Agency (IAEA) and Korean Government. (author)

  4. An evaluation of the Browns Ferry Nuclear Plant preventive maintenance program based on reliability centered maintenance analysis

    International Nuclear Information System (INIS)

    McCullough, C.L.; McCullough, C.A.

    1989-01-01

    Reliability centered maintenance (RCM) techniques were used to support a preventative maintenance (PM) upgrade program (PMUP) performed at TVA Browns Ferry Nuclear Plant (BFNP). The purpose of the RCM analysis was to identify critical equipment based on risk and economic importance and to evaluate the PM activities applicable to that equipment. The analysis may be conveniently divided into three steps, which will be outlined in the Approach section of this paper. The net benefit of the RCM approach was a prioritization of the focus of the PM upgrade program so that plant components receive attention proportional to their importance, and assurance that PM activities properly address the most likely component failure causes

  5. A method and application study on holistic decision tree for human reliability analysis in nuclear power plant

    International Nuclear Information System (INIS)

    Sun Feng; Zhong Shan; Wu Zhiyu

    2008-01-01

    The paper introduces a human reliability analysis method mainly used in Nuclear Power Plant Safety Assessment and the Holistic Decision Tree (HDT) method and how to apply it. The focus is primarily on providing the basic framework and some background of HDT method and steps to perform it. Influence factors and quality descriptors are formed by the interview with operators in Qinshan Nuclear Power Plant and HDT analysis performed for SGTR and SLOCA based on this information. The HDT model can use a graphic tree structure to indicate that error rate is a function of influence factors. HDT method is capable of dealing with the uncertainty in HRA, and it is reliable and practical. (authors)

  6. Wastewater sludge treatment at selected wastewater treatment plants of the region Banska Bystrica

    International Nuclear Information System (INIS)

    Samesova, D.; Mitterpach, J.; Martinkova, A.

    2014-01-01

    The management of sewage sludges in water treatment plants of Banska Bystrica region. The paper deals with the problems of sewage sludge in wastewater treatment plants, its origin and possibilities how to use it in accordance with the current legislation of the Slovak Republic. We described radioactive pollution of sewage sludges. The paper consists of review of sludge production and its usage in the Slovak Republic and in selected states of the European Union. The paper deals with the sludge treatment in selected wastewater treatment plants in Banska Bystrica region in the context of biogas production and its usage by the help of the electricity and heat production. (authors)

  7. Increasing Water System Efficiency with Ultrafiltration Pre-treatment in Power Plants

    International Nuclear Information System (INIS)

    Majamaa, Katariina; Suarez, Javier; Gasia Eduard

    2012-09-01

    Water demineralization with reverse osmosis (RO) membranes has a long and successful history in water treatment for power plants. As the industry strives for more efficient, reliable and compact water systems, pressurized hollow-fiber ultrafiltration (UF) has become an increasingly appealing pre-treatment technology. Compared to conventional, non- membrane based pretreatments, ultrafiltration offers higher efficiency in the removal of suspended solids, microorganisms and colloidal matter, which are all common causes for operational challenges experienced in the RO systems. In addition, UF is more capable of handling varying feed water qualities and removes the risk of particle carry-over often seen with conventional filtration techniques. Ultrafiltration is a suitable treatment technology for various water types from surface waters to wastewater, and the more fluctuating or challenging the feed water source is, the better the benefits of UF are seen compared to conventional pretreatments. Regardless of the feed water type, ultrafiltration sustains a constant supply of high quality feed water to downstream RO, allowing a more compact and cost efficient RO system design with improved operational reliability. A detailed focus on the design and operational aspects and experiences of two plants is provided. These examples demonstrate both economical UF operation and tangible impact of RO process improvement. Experience from these plants can be leveraged to new projects. (authors)

  8. Reliability of the seismic characteristics in the nuclear power plant location; Pouzdanost seizmickih karakteristika pri lociranju nuklearne elektrane

    Energy Technology Data Exchange (ETDEWEB)

    Marsicanin, B [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

    1982-07-01

    Seismic characteristics for a nuclear power plant location are partly obtained from the analysis of past earthquakes. Data from older history concern damages, the newer data are in the form of seismic records. These two sources are often had to correlate, and the data dissipation is very large. Therefore these, rather unreliable data are not a convenient base for the precise anti-seismic analysis. A redistribution of efforts in order to get more reliable basic data seems necessary. (author)

  9. A survey on reliability and safety analysis techniques of robot systems in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Eom, H S; Kim, J H; Lee, J C; Choi, Y R; Moon, S S

    2000-12-01

    The reliability and safety analysis techniques was surveyed for the purpose of overall quality improvement of reactor inspection system which is under development in our current project. The contents of this report are : 1. Reliability and safety analysis techniques suvey - Reviewed reliability and safety analysis techniques are generally accepted techniques in many industries including nuclear industry. And we selected a few techniques which are suitable for our robot system. They are falut tree analysis, failure mode and effect analysis, reliability block diagram, markov model, combinational method, and simulation method. 2. Survey on the characteristics of robot systems which are distinguished from other systems and which are important to the analysis. 3. Survey on the nuclear environmental factors which affect the reliability and safety analysis of robot system 4. Collection of the case studies of robot reliability and safety analysis which are performed in foreign countries. The analysis results of this survey will be applied to the improvement of reliability and safety of our robot system and also will be used for the formal qualification and certification of our reactor inspection system.

  10. A survey on reliability and safety analysis techniques of robot systems in nuclear power plants

    International Nuclear Information System (INIS)

    Eom, H.S.; Kim, J.H.; Lee, J.C.; Choi, Y.R.; Moon, S.S.

    2000-12-01

    The reliability and safety analysis techniques was surveyed for the purpose of overall quality improvement of reactor inspection system which is under development in our current project. The contents of this report are : 1. Reliability and safety analysis techniques suvey - Reviewed reliability and safety analysis techniques are generally accepted techniques in many industries including nuclear industry. And we selected a few techniques which are suitable for our robot system. They are falut tree analysis, failure mode and effect analysis, reliability block diagram, markov model, combinational method, and simulation method. 2. Survey on the characteristics of robot systems which are distinguished from other systems and which are important to the analysis. 3. Survey on the nuclear environmental factors which affect the reliability and safety analysis of robot system 4. Collection of the case studies of robot reliability and safety analysis which are performed in foreign countries. The analysis results of this survey will be applied to the improvement of reliability and safety of our robot system and also will be used for the formal qualification and certification of our reactor inspection system

  11. Emergence of native plant seeds in response to seed pelleting, planting depth, scarification, and soil anti-crusting treatment, 2009

    Science.gov (United States)

    Clint Shock; Erik Feibert; Lamont Saunders; Nancy Shaw

    2010-01-01

    Seed of native plants is needed to restore rangelands of the Intermountain West. Reliable commercial seed production is desirable to provide the quantity of seed needed for restoration efforts. Establishment of native seed crops has been difficult, because fall-planted seed is susceptible to bird damage, soil crusting, and soil erosion. Fall planting is important for...

  12. 25. MPA-seminar: safety and reliability of plant technology with special emphasis on safety and reliability - integrity proofs, qualification of components, damage prevention. Vol. 1. Papers 1-29

    International Nuclear Information System (INIS)

    1999-01-01

    The proceedings of the 25th MPA Seminar on 'Safety and Reliability of Plant Technology' were issued in two volumes. The main topics of the first volume are: 1. Structural and safety analysis, 2. Reliability analysis, 3. Fracture mechanics, and 4. Nondestructive Testing. s

  13. Waste water treatment plant city of Kraljevo

    Directory of Open Access Journals (Sweden)

    Marinović Dragan D.

    2016-01-01

    Full Text Available In all countries, in the fight for the preservation of environmental protection, water pollution, waste water is one of the very serious and complex environmental problems. Waste waters pollute rivers, lakes, sea and ground water and promote the development of micro-organisms that consume oxygen, which leads to the death of fish and the occurrence of pathogenic microbes. Water pollution and determination of its numerous microbiological contamination, physical agents and various chemical substances, is becoming an increasing health and general social problem. Purification of industrial and municipal waste water before discharge into waterways is of great importance for the contamination of the water ecosystems and the protection of human health. To present the results of purification of industrial and municipal wastewater in the city center Kraljevo system for wastewater treatment. The investigated physical and chemical parameters were performed before and after the city's system for wastewater treatment. The results indicate that the effect of purification present the physical and chemical parameters in waste water ranges from 0 - 19%.

  14. Reliability Analysis of Safety Grade PLC(POSAFE-Q) for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, J. Y.; Lyou, J.; Lee, D. Y.; Choi, J. G.; Park, W. M.

    2006-01-01

    The Part Count Method of the military standard MILHDK- 217F has been used for the reliability prediction of the nuclear field. This handbook determines the Programmable Logic Controller (PLC) failure rate by summing the failure rates of the individual component included in the PLC. Normally it is easily predictable that the components added for the fault detection improve the reliability of the PLC. But the application of this handbook is estimated with poor reliability because of the increased component number for the fault detection. To compensate this discrepancy, the quantitative reliability analysis method is suggested using the functional separation model in this paper. And it is applied to the Reactor Protection System (RPS) being developed in Korea to identify any design weak points from a safety point of view

  15. Region 9 NPDES Facilities 2012- Waste Water Treatment Plants

    Science.gov (United States)

    Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from facilities that discharge treated waste water into waters of the US. Facilities are issued NPDES permits regulating their discharge as required by the Clean Water Act. A facility may have one or more outfalls (dischargers). The location represents the facility or operating plant.

  16. Region 9 NPDES Facilities - Waste Water Treatment Plants

    Science.gov (United States)

    Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from facilities that discharge treated waste water into waters of the US. Facilities are issued NPDES permits regulating their discharge as required by the Clean Water Act. A facility may have one or more outfalls (dischargers). The location represents the facility or operating plant.

  17. Method for treatment of wastewater of nuclear power plants

    International Nuclear Information System (INIS)

    Ito, Kazutoshi; Suzuki, Katsumi; Suzuki, Mamoru; Minato, Akira.

    1984-01-01

    A method for treatment of wastewater of nuclear power plants is characterized by the fact that concentration and volume reduction are performed after Ca and Mg as components for the formation of an adhering scale is converted to an 8-oxyquinoline complex, which is hardly soluble in water, and does not precipitate out as an adhering scale, by the addition of 8-oxyquinoline into nuclear power plant wastewater

  18. Plant-integrated measurement of greenhouse gas emissions from a municipal wastewater treatment plant

    DEFF Research Database (Denmark)

    Yoshida, Hiroko; Mønster, Jacob; Scheutz, Charlotte

    2014-01-01

    experiencing operational problems, such as during foaming events in anaerobic digesters and during sub-optimal operation of biological nitrogen removal in the secondary treatment of wastewater. Methane emissions detected during measurement campaigns corresponded to 2.07-32.7% of the methane generated......Wastewater treatment plants (WWTPs) contribute to anthropogenic greenhouse gas (GHG) emissions. Due to its spatial and temporal variation in emissions, whole plant characterization of GHG emissions from WWTPs face a number of obstacles. In this study, a tracer dispersion method was applied...... in the plant. As high as 4.27% of nitrogen entering the WWTP was emitted as nitrous oxide under the sub-optimal operation of biological treatment processes. The study shows that the unit process configuration, as well as the operation of the WWTP, determines the rate of GHG emission. The applied plant...

  19. Reliability modeling of digital component in plant protection system with various fault-tolerant techniques

    International Nuclear Information System (INIS)

    Kim, Bo Gyung; Kang, Hyun Gook; Kim, Hee Eun; Lee, Seung Jun; Seong, Poong Hyun

    2013-01-01

    Highlights: • Integrated fault coverage is introduced for reflecting characteristics of fault-tolerant techniques in the reliability model of digital protection system in NPPs. • The integrated fault coverage considers the process of fault-tolerant techniques from detection to fail-safe generation process. • With integrated fault coverage, the unavailability of repairable component of DPS can be estimated. • The new developed reliability model can reveal the effects of fault-tolerant techniques explicitly for risk analysis. • The reliability model makes it possible to confirm changes of unavailability according to variation of diverse factors. - Abstract: With the improvement of digital technologies, digital protection system (DPS) has more multiple sophisticated fault-tolerant techniques (FTTs), in order to increase fault detection and to help the system safely perform the required functions in spite of the possible presence of faults. Fault detection coverage is vital factor of FTT in reliability. However, the fault detection coverage is insufficient to reflect the effects of various FTTs in reliability model. To reflect characteristics of FTTs in the reliability model, integrated fault coverage is introduced. The integrated fault coverage considers the process of FTT from detection to fail-safe generation process. A model has been developed to estimate the unavailability of repairable component of DPS using the integrated fault coverage. The new developed model can quantify unavailability according to a diversity of conditions. Sensitivity studies are performed to ascertain important variables which affect the integrated fault coverage and unavailability

  20. Hydraulic modelling of drinking water treatment plant operations

    Directory of Open Access Journals (Sweden)

    L. C. Rietveld

    2009-06-01

    Full Text Available The flow through a unit of a drinking water treatment plant is one of the most important parameters in terms of a unit's effectiveness. In the present paper, a new EPAnet library is presented with the typical hydraulic elements for drinking water treatment processes well abstraction, rapid sand filtration and cascade and tower aeration. Using this treatment step library, a hydraulic model was set up, calibrated and validated for the drinking water treatment plant Harderbroek. With the actual valve position and pump speeds, the flows were calculated through the several treatment steps. A case shows the use of the model to calculate the new setpoints for the current frequency converters of the effluent pumps during a filter backwash.

  1. Medicinal plants indications from herbal healers for wound treatment

    Directory of Open Access Journals (Sweden)

    Maria Willianne Alves do Nascimento

    2016-06-01

    Full Text Available The objective was to identify medicinal plants indicated by commercial herbal healers for wound treatment, in street markets. A descriptive study conducted in a capital city in the northeast of Brazil, through interviews. The results indicate that plant commerce by healers of both genders, aged between 37 to 52 years, from those 69.3% learned about their function with family members. Forty-eight plant species were cited for wound treatment, between those, all participants cited Barbatimão and Mastic. From the plants Sambacaitá, Open Nettle, Yellow Uchi, Corona, Xiquexique, Senna and Pindaíba no properties to prove their indication was found for wound treatment. The stem bark was the most indicated part (96.15%, 81.03% of participants informed that plants should be kept dry for conservation. Studies to clarify the biological activities and collateral effects of medicinal plants are needed, beyond training for healers about indications, prepare, storage/conservation, and expiration date.

  2. Nuclear power plant laundry drain treatment using membrane bio reactor

    International Nuclear Information System (INIS)

    Tsukamoto, Masaaki; Kohanawa, Osamu; Kinugasa, Atsushi; Ogawa, Naoki; Murogaki, Kenta

    2012-01-01

    In nuclear power plant, the radioactive effluent generated by washing the clothes worn in controlled area and the hand and shower water used at the controlled area are treated in laundry drain treatment system. Although various systems which treat such liquid waste preexist, the traditional treatment system has disadvantages such as high running cost and a large amount of secondary waste generation. To solve these matters, we have considered application of an activated sludge system, membrane bio reactor, which has been practically used in general industry. For nuclear power plant, the activated sludge system has been developed, tested in its adaptability and the adequacy has been proved. Some preexisting treatment systems have been replaced with this activated sludge system for the first time in a domestic nuclear power plant, and the renewal system is now in operation. The result is reported. (author)

  3. Optimal design of regional wastewater pipelines and treatment plant systems.

    Science.gov (United States)

    Brand, Noam; Ostfeld, Avi

    2011-01-01

    This manuscript describes the application of a genetic algorithm model for the optimal design of regional wastewater systems comprised of transmission gravitational and pumping sewer pipelines, decentralized treatment plants, and end users of reclaimed wastewater. The algorithm seeks the diameter size of the designed pipelines and their flow distribution simultaneously, the number of treatment plants and their size and location, the pump power, and the required excavation work. The model capabilities are demonstrated through a simplified example application using base runs and sensitivity analyses. Scaling of the proposed methodology to real life wastewater collection and treatment plants design problems needs further testing and developments. The model is coded in MATLAB using the GATOOL toolbox and is available from the authors.

  4. Saudi medicinal plants for the treatment of scorpion sting envenomation.

    Science.gov (United States)

    Al-Asmari, Abdulrahman; Manthiri, Rajamohamed Abbas; Abdo, Nasreddien; Al-Duaiji, Fawzi Abdullah; Khan, Haseeb Ahmad

    2017-09-01

    Scorpion sting envenoming poses major public health problems. The treatment modalities include antivenoms, chemical antidotes and phytotherapy, with varying degrees of effectiveness and side effects. In this investigation, we reviewed the use of Saudi medicinal plants for the treatment of scorpion sting patients. The relevant literature was collected using the online search engines including Science Direct, Google and PubMed with the help of specific keywords. We also used the printed and online resources at our institutional library to gather the relevant information on the use of medicinal plants for the treatment of scorpion sting patients. A descriptive statistics was used for data compilation and presentation. The results of this survey showed the use of at least 92 medicinal plants with beneficial effects for treating victims of stings of different scorpion species. These commonly used herbs spanned to 37 families whilst different parts of these plants were employed therapeutically for alleviation of envenomation symptoms. The application of leaves (41%) was preferred followed by roots (19%), whole plant (14%) and seeds (9%). The use of latex (4%), stem (3%), flowers (3%) and bark (3%) was also reported. In some cases, tannin (2%), rhizome (1%) and shoot (1%) were also used. In conclusion, herbal medicines are effectively used for the treatment of patients with scorpion envenomation. This type of medication is free from side effects as observed with chemical antidotes or antivenom therapy. It is important to identify the active ingredients of herbal drugs for improving their therapeutic potential in traditional medicine.

  5. Condensate treatment and oxygen control in power plants

    International Nuclear Information System (INIS)

    Sakai, Toshiaki; Iida, Kei; Ohashi, Shinichi.

    1997-01-01

    In thermal and nuclear power stations, the steam that operated turbines is cooled and condensed with condensers. The condensate is heated again with boilers, nuclear reactors or steam generators, but if corrosion products or impurities are contained in the condensate, corrosion and scale formation occur in boilers and others. The filtration facility and the desalting facility for condensate are installed to remove impurities, but water quality control is different in thermal, BWR and PWR plants, therefore, the treatment facilities corresponding to respective condensates have been adopted. In order to reduce the amount of clud generation, the treatment of injecting a small quantity of oxygen into condensate has been adopted. In thermal power plants, all volatile treatment is carried out, in which corrosion is prevented by the addition of ammonia and hydrazine to boiler feedwater. The condensate filters of various types and the NH 4 type condensate desalter for thermal power plants are described. In BWR power plants, steam is generated in nuclear reactors, therefore, the addition of chemicals into water is never carried out, and high purity neutral water is used. In PWR power plants, the addition of chemicals to water is done in the primary system, and AVT is adopted in the secondary system. Also the condensate treatment facilities are different for both reactors. (K.I.)

  6. Operational safety performance indicator system - a management tool for the self assessment of safety and reliability of nuclear power plants

    International Nuclear Information System (INIS)

    Anil Kumar; Mandowara, S.L.; Mittal, S.

    2006-01-01

    Operational Safety Performance Indicator system is one of the self assessment tools for station management to monitor safety and reliability of nuclear power plants. It provides information to station management about the performance of various areas of the plants by means of different colours of relevant performance indicators. Such systems have been implemented at many nuclear power plants in the world and have been considered as strength during WANO Peer Review. IAEA had a Coordinated Research Programme (CRP) on this with several countries participating including India. In NPCIL this system has been implemented in KAPS about a year back and found very useful in identifying areas which needs to be given more attention. Based on the KAPS feedback Implementation of this system has been taken up in RAPS-3 and 4 and KGS-l and 2. (author)

  7. Patient Self-Report of Prior Laser Treatment Reliably Indicates Presence of Severe Diabetic Retinopathy

    Science.gov (United States)

    GRASSI, MICHAEL A.; MAZZULLA, D. ANTHONY; KNUDTSON, MICHAEL D.; HUANG, WENDY W.; LEE, KRISTINE E.; KLEIN, BARBARA E.; NICOLAE, DAN L.; KLEIN, RONALD

    2009-01-01

    PURPOSE To determine whether patient self-report of prior laser treatment can be used as a reliable tool for assessing the presence of severe diabetic retinopathy. DESIGN This was a retrospective study on two groups of diabetic subjects. METHODS One hundred patients with diabetes were recruited from the general eye and retina clinics at the University of Chicago Hospitals. The patients were asked, “Have you ever received laser treatment for your diabetic eye disease (DED)?” A chart review was then conducted noting if the patient had received either focal laser treatment for diabetic macular edema or panretinal photocoagulation for proliferative diabetic retinopathy. Data from the Wisconsin Epidemiological Study of Diabetic Retinopathy (WESDR) were also analyzed. Participant responses to the question “Have you had laser photocoagulation treatment for your eyes?” were analyzed with documentation of photocoagulation scars determined by grading seven-standard field color fundus photographs. RESULTS In the University of Chicago group, 96 of 100 (96%) of patients were accurate in reporting whether they had received previous laser treatment for DED (sensitivity 95.8%, specificity 96.1%, and positive predictive value 88.5%). In the WESDR analysis, 2,329 of 2,348 (99%) of participants were accurate in reporting whether they had prior laser treatment for DED (sensitivity 96.0%, specificity 99.5%, and positive predictive value 95.6%). CONCLUSIONS The high sensitivity and specificity of our results validate the use of patient self-report as a useful tool in assessing past laser treatment for severe diabetic retinopathy. Patient self-report may be a useful surrogate to clinical examination or medical record review to determine the presence of severe diabetic retinopathy. PMID:19054495

  8. Modelling of nuclear power plant control and instrumentation elements for automatic disturbance and reliability analysis

    International Nuclear Information System (INIS)

    Hollo, E.

    1985-08-01

    Present Final Report summarizes results of R/D work done within IAEA-VEIKI (Institute for Electrical Power Research, Budapest, Hungary) Research Contract No. 3210 during 3 years' period of 01.08.1982 - 31.08.1985. Chapter 1 lists main research objectives of the project. Main results obtained are summarized in Chapters 2 and 3. Outcomes from development of failure modelling methodologies and their application for C/I components of WWER-440 units are as follows (Chapter 2): improvement of available ''failure mode and effect analysis'' methods and mini-fault tree structures usable for automatic disturbance (DAS) and reliability (RAS) analysis; general classification and determination of functional failure modes of WWER-440 NPP C/I components; set up of logic models for motor operated control valves and rod control/drive mechanism. Results of development of methods and their application for reliability modelling of NPP components and systems cover (Chapter 3): development of an algorithm (computer code COMPREL) for component-related failure and reliability parameter calculation; reliability analysis of PAKS II NPP diesel system; definition of functional requirements for reliability data bank (RDB) in WWER-440 units. Determination of RDB input/output data structure and data manipulation services. Methods used are a-priori failure mode and effect analysis, combined fault tree/event tree modelling technique, structural computer programming, probability theory application to nuclear field

  9. Modification of Wastewater Treatment Technology at Cottonseed Oil Plant

    Directory of Open Access Journals (Sweden)

    Alshabab Mary Shick

    2016-01-01

    Full Text Available Wastewaters from cottonseed oil producing plant in Syria were studied in laboratory experiments. Aim of the study was to suggest modification of wastewater treatment technology in order to increase its efficiency. Concentration of pollutants in wastewaters was controlled by measurement of COD. According to the results of experiments it was suggested to decrease significantly (8-20 times dosages of reagents (acidifier, coagulant, flocculant in several actual stages of treatment (acidification, separation, coagulation and sedimentation and add stage of dispersed air flotation before coagulation treatment. The modified wastewater treatment technology would reduce COD to the values allowed for irrigation waters by Syrian National Standard.

  10. Cycle chemistry monitoring system as means of improving the reliability of the equipment at the power plants

    Science.gov (United States)

    Yegoshina, O. V.; Voronov, V. N.; Yarovoy, V. O.; Bolshakova, N. A.

    2017-11-01

    There are many problems in domestic energy at the present that require urgent solutions in the near future. One of these problems - the aging of the main and auxiliary equipment. Wear of equipment is the cause of decrease reliability and efficiency of power plants. Reliability of the equipment are associated with the introduction of cycle chemistry monitoring system. The most damageable equipment’s are boilers (52.2 %), turbines (12.6 %) and heating systems (12.3 %) according to the review of failure rate on the power plants. The most part of the damageability of the boiler is heated surfaces (73.2 %). According to the Russian technical requirements, the monitoring systems are responsible to reduce damageability the boiler heating surfaces and to increase the reliability of the equipment. All power units capacity of over 50 MW are equipped with cycle chemistry monitoring systems in order to maintain water chemistry within operating limits. The main idea of cycle chemistry monitoring systems is to improve water chemistry at power plants. According to the guidelines, cycle chemistry monitoring systems of a single unit depends on its type (drum or once-through boiler) and consists of: 20…50 parameters of on-line chemical analyzers; 20…30 «grab» sample analyses (daily) and about 15…20 on-line monitored operating parameters. The operator of modern power plant uses with many data at different points of steam/water cycle. Operators do not can estimate quality of the cycle chemistry due to the large volume of daily and every shift information and dispersion of data, lack of systematization. In this paper, an algorithm for calculating the quality index developed for improving control the water chemistry of the condensate, feed water and prevent scaling and corrosion in the steam/water cycle.

  11. Operational experience of gaseous effluent treatment at the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Osipenco, A.; Detilleux, E.

    1977-01-01

    The EUROCHEMIC fuel reprocessing plant applies the PUREX flow sheet. Two particular features of the plant influence gaseous and liquid effluents: chemical decanning and the ability to process a wide range of fuels, uranium metal or oxide, having an initial enrichment typical of power reactors (up to 5%) or material testing reactors (up to 93%). The ventilation circuits, treatment plant and monitoring equipment for gaseous releases are briefly described. No retention facilities for rare gases, tritium, or carbon-14 are provided. The releases are monitored for krypton-85, iodine-131, alpha and beta-gamma aerosols and tritium. Between 1966 and 1974 the plant processes about 200 tonnes of power reactor fuel, from which about 0.7 tonnes of plutonium and 1.5 tonnes of highly enriched uranium were separated. The most important points in the operation of the gas cleaning equipment are indicated: efficiency, operational reliability, incidents, etc.. Actual discharges as measured are compared with the limits set in the operation licence. Using the atmospheric diffusion coefficients, the dose commitment is estimated. The low level liquid effluents are passed, after neutralization, to the treatment plant of the Belgian nuclear center CEN/SCK. However, if the activity exceeds the limit set by the CEN/SCK, the effluents are concentrated by evaporation and stored on the EUROCHEMIC site. (orig.) [de

  12. Decision-theoretic methodology for reliability and risk allocation in nuclear power plants

    International Nuclear Information System (INIS)

    Cho, N.Z.; Papazoglou, I.A.; Bari, R.A.; El-Bassioni, A.

    1985-01-01

    This paper describes a methodology for allocating reliability and risk to various reactor systems, subsystems, components, operations, and structures in a consistent manner, based on a set of global safety criteria which are not rigid. The problem is formulated as a multiattribute decision analysis paradigm; the multiobjective optimization, which is performed on a PRA model and reliability cost functions, serves as the guiding principle for reliability and risk allocation. The concept of noninferiority is used in the multiobjective optimization problem. Finding the noninferior solution set is the main theme of the current approach. The assessment of the decision maker's preferences could then be performed more easily on the noninferior solution set. Some results of the methodology applications to a nontrivial risk model are provided and several outstanding issues such as generic allocation and preference assessment are discussed

  13. 40 CFR 63.1585 - How does an industrial POTW treatment plant demonstrate compliance?

    Science.gov (United States)

    2010-07-01

    ... Works Industrial Potw Treatment Plant Description and Requirements § 63.1585 How does an industrial POTW treatment plant demonstrate compliance? (a) An existing industrial POTW treatment plant demonstrates... §§ 63.1586 through 63.1590. Non-industrial POTW Treatment Plant Requirements ...

  14. 40 CFR 63.1582 - What are the characteristics of an industrial POTW treatment plant?

    Science.gov (United States)

    2010-07-01

    ... industrial POTW treatment plant? 63.1582 Section 63.1582 Protection of Environment ENVIRONMENTAL PROTECTION... Works Industrial Potw Treatment Plant Description and Requirements § 63.1582 What are the characteristics of an industrial POTW treatment plant? (a) Your POTW is an industrial POTW treatment plant if an...

  15. Reliability of a treatment-based classification system for subgrouping people with low back pain.

    Science.gov (United States)

    Henry, Sharon M; Fritz, Julie M; Trombley, Andrea R; Bunn, Janice Y

    2012-09-01

    Observational, cross-sectional reliability study. To examine the interrater reliability of novice raters in their use of the treatment-based classification (TBC) system for low back pain and to explore the patterns of disagreement in classification errors. Although the interrater reliability of individual test items in the TBC system is moderate to good, some error persists in classification decision making. Understanding which classification errors are common could direct further refinement of the TBC system. Using previously recorded patient data (n = 24), 12 novice raters classified patients according to the TBC schema. These classification results were combined with those of 7 other raters, allowing examination of the overall agreement using the kappa statistic, as well as agreement/disagreement among pairwise comparisons in classification assignments. A chi-square test examined differences in percent agreement between the novice and more experienced raters and differences in classification distributions between these 2 groups of raters. Among 12 novice raters, there was 80.9% agreement in the pairs of classification (κ = 0.62; 95% confidence interval: 0.59, 0.65) and an overall 75.5% agreement (κ = 0.57; 95% confidence interval: 0.55, 0.69) for the combined data set. Raters were least likely to agree on a classification of stabilization (77.5% agreement). The overall percentage of pairwise classification judgments that disagreed was 24.5%, with the most common disagreement being between manipulation and stabilization (11.0%), followed by a mismatch between stabilization and specific exercise (8.2%). Additional refinement is needed to reduce rater disagreement that persists in the TBC decision-making algorithm, particularly in the stabilization category. J Orthop Sports Phys Ther 2012;42(9):797-805, Epub 7 June 2012. doi:10.2519/jospt.2012.4078.

  16. In-plant reliability data base for nuclear plant components: a feasibility study on human error information

    International Nuclear Information System (INIS)

    Borkowski, R.J.; Fragola, J.R.; Schurman, D.L.; Johnson, J.W.

    1984-03-01

    This report documents the procedure and final results of a feasibility study which examined the usefulness of nuclear plant maintenance work requests in the IPRDS as tools for understanding human error and its influence on component failure and repair. Developed in this study were (1) a set of criteria for judging the quality of a plant maintenance record set for studying human error; (2) a scheme for identifying human errors in the maintenance records; and (3) two taxonomies (engineering-based and psychology-based) for categorizing and coding human error-related events

  17. Planning of emergency medical treatment in nuclear power plant

    International Nuclear Information System (INIS)

    Kusama, Tomoko

    1989-01-01

    Medical staffs and health physicists have shown deep concerning at the emergency plans of nuclear power plants after the TMI nuclear accident. The most important and basic countermeasure for accidents was preparing appropriate and concrete organization and plans for treatment. We have planed emergency medical treatment for radiation workers in a nuclear power plant institute. The emergency medical treatment at institute consisted of two stages, that is on-site emergency treatment at facility medical service. In first step of planning in each stage, we selected and treatment at facility medical service. In first step of planning in each stage, we selected and analyzed all possible accidents in the institute and discussed on practical treatments for some possible accidents. The manuals of concrete procedure of emergency treatment for some accidents were prepared following discussion and facilities and equipment for medical treatment and decontamination were provided. All workers in the institute had periodical training and drilling of on-site emergency treatment and mastered technique of first aid. Decontamination and operation rooms were provided in the facillity medical service. The main functions at the facility medical service have been carried out by industrial nurses. Industrial nurses have been in close co-operation with radiation safety officers and medical doctors in regional hospital. (author)

  18. Medicinal Plants for the Treatment of Hypertrophic Scars

    Directory of Open Access Journals (Sweden)

    Qi Ye

    2015-01-01

    Full Text Available Hypertrophic scar is a complication of wound healing and has a high recurrence rate which can lead to significant abnormity in aesthetics and functions. To date, no ideal treatment method has been established. Meanwhile, the underlying mechanism of hypertrophic scarring has not been clearly defined. Although a large amount of scientific research has been reported on the use of medicinal plants as a natural source of treatment for hypertrophic scarring, it is currently scattered across a wide range of publications. Therefore, a systematic summary and knowledge for future prospects are necessary to facilitate further medicinal plant research for their potential use as antihypertrophic scar agents. A bibliographic investigation was accomplished by focusing on medicinal plants which have been scientifically tested in vitro and/or in vivo and proved as potential agents for the treatment of hypertrophic scars. Although the chemical components and mechanisms of action of medicinal plants with antihypertrophic scarring potential have been investigated, many others remain unknown. More investigations and clinical trials are necessary to make use of these medical plants reasonably and phytotherapy is a promising therapeutic approach against hypertrophic scars.

  19. Life Cycle Assessment of Daugavgriva Waste Water Treatment Plant

    OpenAIRE

    Romagnoli, F; Fraga Sampaio, F; Blumberga, D

    2009-01-01

    This paper presents the assessment of the environmental impacts caused by the treatment of Riga’s waste water in the Daugavgriva plant with biogas energy cogeneration through the life cycle assessment (LCA). The LCA seems to be a good tool to assess and evaluate the most serious environmental impacts of a facility The results showed clearly that the impact category contributing the most to the total impact –eutrophicationcomes from the wastewater treatment stage. Cl...

  20. Effluent treatment plant for pharmaceutical unit at Bahipheru - case study

    International Nuclear Information System (INIS)

    Hayat, A.

    1997-01-01

    This project has been awarded to environ (Pvt) Ltd., on turnkey basis, and is an integrated waste treatment facility for pharmaceuticals companies, manufacturing paracetamole, aspirin and various pharmaceuticals intermediates, from phenol as basic raw material. A highly toxic waste water, containing high concentrations of phenolics and sulfate ions is generated at this plant and has to be treatment before final disposal into an irrigation channel. (author)

  1. Nuclear power plant's safety and risk (requirements of safety and reliability)

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1977-01-01

    Starting out from the given safety objectives as they have evolved during the past few years and from the present legal and regulatory provisions for the construction and operation of nuclear power plants, the hazards involved in regular operation, accidents and emergency situations are discussed. In compliance with the positive safety balance of nuclear power plants in the FRG, special attention is focused on the preventive safety analysis within the frame of the nuclear licensing procedure. Reference is made to the beginnings of a comprehensive hazard concept for an unbiased plant assessment. Emergency situations are discussed from the point of view of general hazard comparisons. (orig.) [de

  2. Cost effective water treatment program in Heavy Water Plant (Manuguru)

    International Nuclear Information System (INIS)

    Mohapatra, C.; Prasada Rao, G.

    2002-01-01

    Water treatment technology is in a state of continuous evolution. The increasing urgency to conserve water and reduce pollution has in recent years produced an enormous demand for new chemical treatment programs and technologies. Heavy water plant (Manuguru) uses water as raw material (about 3000 m 3 /hr) and its treatment and management has benefited the plant in a significant way. It is a fact that if the water treatment is not proper, it can result in deposit formation and corrosion of metals, which can finally leads to production losses. Therefore, before selecting treatment program, complying w.r.t. quality requirements, safety and pollution aspects cost effectiveness shall be examined. The areas where significant benefits are derived, are raw water treatment using polyelectrolyte instead of inorganic coagulant (alum), change over of regenerant of cation exchangers from hydrochloric acid to sulfuric acid and in-house development of cooling water treatment formulation. The advantages and cost effectiveness of these treatments are discussed in detail. Further these treatments has helped the plant in achieving zero discharge and indirectly increased cost reduction of final product (heavy water); the dosage of 3 ppm of polyelectrolyte can replace 90 ppm alum at turbidity level of 300 NTU of raw water which has resulted in cost saving of Rs. 15-20 lakhs in a year beside other advantages; the change over of regenerant from HCl to H 2 SO 4 will result in cost saving of at least Rs.1.4 crore a year besides other advantages; the change over to proprietary formulation to in-house formulation in cooling water treatment has resulted in a saving about Rs.11 lakhs a year. To achieve the above objectives in a sustainable way the performance results are being monitored. (author)

  3. Industrial plant for electron beam flue gas treatment

    International Nuclear Information System (INIS)

    Chmielewski, A.G.; Iller, E.; Tyminnski, B.; Zimek, Z; Ostapczuk, A.; Licki, J.

    2001-01-01

    The electron beam flue gas treatment technology was invented many years ago. Research on the process has been carried out in Japan, USA, Germany and Poland. However, the recent fidings, based on the experiments performed at pilot plant at Electric Power Station Kaweczyn, led to developments which made process mature just at the dawn of the XXI century. The process is being implemented in the full industrial scale at Electric Power Station Pomorzany (Dolna Odra EPS Group). Other developments are reported in Japan and after Nagoya's pilot plant experiments, an industrial plant has been built in China and another one is constructed in Japan. There are remarkable differences in technological and design solutions applied in all these installations. Developments achieved at EPS Kaweczyn pilot plant and INCT laboratory unit were the basis for the project realized at EPS Pomorzan

  4. Improvement of level-1 PSA computer code package - Modeling and analysis for dynamic reliability of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Hoon; Baek, Sang Yeup; Shin, In Sup; Moon, Shin Myung; Moon, Jae Phil; Koo, Hoon Young; Kim, Ju Shin [Seoul National University, Seoul (Korea, Republic of); Hong, Jung Sik [Seoul National Polytechnology University, Seoul (Korea, Republic of); Lim, Tae Jin [Soongsil University, Seoul (Korea, Republic of)

    1996-08-01

    The objective of this project is to develop a methodology of the dynamic reliability analysis for NPP. The first year`s research was focused on developing a procedure for analyzing failure data of running components and a simulator for estimating the reliability of series-parallel structures. The second year`s research was concentrated on estimating the lifetime distribution and PM effect of a component from its failure data in various cases, and the lifetime distribution of a system with a particular structure. Computer codes for performing these jobs were also developed. The objectives of the third year`s research is to develop models for analyzing special failure types (CCFs, Standby redundant structure) that were nor considered in the first two years, and to complete a methodology of the dynamic reliability analysis for nuclear power plants. The analysis of failure data of components and related researches for supporting the simulator must be preceded for providing proper input to the simulator. Thus this research is divided into three major parts. 1. Analysis of the time dependent life distribution and the PM effect. 2. Development of a simulator for system reliability analysis. 3. Related researches for supporting the simulator : accelerated simulation analytic approach using PH-type distribution, analysis for dynamic repair effects. 154 refs., 5 tabs., 87 figs. (author)

  5. Quality and reliability assurance of electronic components in small-scale and middle-sized plants

    International Nuclear Information System (INIS)

    Becker, P.

    1982-01-01

    Electronic components are forever finding their way into new fields of application and have an ever increasing influence on the quality and reliability of the products in which they are used. The user has very negligible influence on the production methods used for the manufacture of the components and the element properties. (orig.) [de

  6. Reliability analysis of scram system of a critical nuclear power plant

    International Nuclear Information System (INIS)

    Vieira Neto, A.S.; Souza Borges, W. de

    1986-01-01

    The object of this paper is to show the relevancy of reliability analysis of nuclear systems as a mean of evaluating their prospect performance in design phase. For this purpose a typical scram system design for light water cooled critical facilities is analized to verify the effects of alternative maintenance procedure and design redundancies in realibility characteristics. (Author) [pt

  7. Reliability analysis of pipelines and pressure vessels at nuclear power plants

    International Nuclear Information System (INIS)

    Klemin, A.I.; Shiverskij, E.A.

    1979-01-01

    Reliability analysis of pipelines and pressure vessels at NPP is given. The main causes and failure mechanisms of these elements, the ways of reliability improvement and preventing of great damages are considered. The reliability estimation methods both according to the statistical operation data and under the conditions of absence of failure statistics are given. The main characteristics and actual reliability factors of pipelines and pressure vessels of three home NPP: the first in the world NPP, VK-50 and Beloyarsk NPP, are presented. From the start-up there were practically no failures of the pipelines and pressure vessels at the VK-50 pilot installation. The analysis of the operation experience of the first and second blocks of the Beloyarsk NPP, as well as the first in the world NPP, shows that the most part of failures of the pipelines and pressure vessels of these energy blocks with the channel reactors is connected with the coolant leakage at minority pipelines of a small diameter. The most part of failures at individual pipelines of the first and second blocks of the Beloyarsk NPP are connected with the leakages of stuffing boxes of switching off devices. It is noted that serious failures of large pipelines and pressure vessels at all home NPP under operation have not been observed

  8. Basic user guide for the radwaste treatment plant computer system

    International Nuclear Information System (INIS)

    Keel, A.

    1990-07-01

    This guide has been produced as an aid to using the Radwaste Treatment Plant computer system. It is designed to help new users to use the database menu system. Some of the forms can be used in ways different from those explained and more complex queries can be performed. (UK)

  9. Conflicts concerning sites for waste treatment and waste disposal plants

    International Nuclear Information System (INIS)

    Werbeck, N.

    1993-01-01

    The erection of waste treatment and waste disposal flants increasingly meets with the disapproval of local residents. This is due to three factors: Firstly, the erection and operation of waste treatment plants is assumed to necessarily entail harmful effects and risks, which may be true or may not. Secondly, these disadvantages are in part considered to be non-compensable. Thirdly, waste treatment plants have a large catchment area, which means that more people enjoy their benefits than have to suffer their disadvantages. If residents in the vicinity of such plants are not compensated for damage sustained or harmed in ways that cannot be compensated for it becomes a rational stance for them, while not objecting to waste treatment and waste disposal plants in principle to object to their being in their own neighbourhood. The book comprehensively describes the subject area from an economic angle. The causes are analysed in detail and an action strategy is pointed, out, which can help to reduce acceptance problems. The individual chapters deal with emissions, risk potentials, optimization calculus considering individual firms or persons and groups of two or more firms or persons, private-economy approaches for the solving of site selection conflicts, collective decision-making. (orig./HSCH) [de

  10. Modeling of water treatment plant using timed continuous Petri nets

    Science.gov (United States)

    Nurul Fuady Adhalia, H.; Subiono, Adzkiya, Dieky

    2017-08-01

    Petri nets represent graphically certain conditions and rules. In this paper, we construct a model of the Water Treatment Plant (WTP) using timed continuous Petri nets. Specifically, we consider that (1) the water pump always active and (2) the water source is always available. After obtaining the model, the flow through the transitions and token conservation laws are calculated.

  11. Operation of Wastewater Treatment Plants, Manual of Practice No. 11.

    Science.gov (United States)

    Albertson, Orrie E.; And Others

    This book is intended to be a reference or textbook on the operation of wastewater treatment plants. The book contains thirty-one chapters and three appendices and includes the description, requirements, and latest techniques of conventional unit process operation, as well as the symptoms and corrective measures regarding process problems. Process…

  12. Treatment of anxiety and depression: medicinal plants in retrospect.

    Science.gov (United States)

    Fajemiroye, James O; da Silva, Dayane M; de Oliveira, Danillo R; Costa, Elson A

    2016-06-01

    Anxiety and depression are complex heterogeneous psychiatric disorders and leading causes of disability worldwide. This review summarizes reports on the fundamentals, prevalence, diagnosis, neurobiology, advancement in treatment of these diseases and preclinical assessment of botanicals. This review was conducted through bibliographic investigation of scientific journals, books, electronic sources, unpublished theses and electronic medium such as ScienceDirect and PubMed. A number of the first-line drugs (benzodiazepine, azapirone, antidepressant tricyclics, monoamine oxidase inhibitors, serotonin selective reuptake inhibitors, noradrenaline reuptake inhibitors, serotonin and noradrenaline reuptake inhibitors, etc.) for the treatment of these psychiatric disorders are products of serendipitous discoveries. Inspite of the numerous classes of drugs that are available for the treatment of anxiety and depression, full remission has remained elusive. The emerging clinical cases have shown increasing interests among health practitioners and patients in phytomedicine. The development of anxiolytic and antidepressant drugs of plant origin takes advantage of multidisciplinary approach including but not limited to ethnopharmacological survey (careful investigation of folkloric application of medicinal plant), phytochemical and pharmacological studies. The selection of a suitable plant for a pharmacological study is a basic and very important step. Relevant clues to achieving this step include traditional use, chemical composition, toxicity, randomized selection or a combination of several criteria. Medicinal plants have been and continue to be a rich source of biomolecule with therapeutic values for the treatment of anxiety and depression. © 2016 Société Française de Pharmacologie et de Thérapeutique.

  13. Guidelines to Career Development for Wastewater Treatment Plant Personnel.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC. Office of Education and Manpower Planning.

    The guidelines were written to promote job growth and improvement in the personnel who manage, operate, and maintain wastewater treatment plants. Trained operators and technicians are the key components in any water pollution control facility. The approach is to move from employment to training through specific modules for 21 standard job…

  14. Operation of Wastewater Treatment Plants: A Home Study Training Program.

    Science.gov (United States)

    California State Univ., Sacramento. Dept. of Civil Engineering.

    This manual was prepared by experienced wastewater treatment plant operators to provide a home study course to develop new qualified workers and expand the abilities of existing workers. The objective of this manual is to provide the knowledge and skills necessary for certification. Participants learn the basic operational aspects of treatment…

  15. Benchmarking Biological Nutrient Removal in Wastewater Treatment Plants

    DEFF Research Database (Denmark)

    Flores-Alsina, Xavier; Gernaey, Krist; Jeppsson, Ulf

    2011-01-01

    This paper examines the effect of different model assumptions when describing biological nutrient removal (BNR) by the activated sludge models (ASM) 1, 2d & 3. The performance of a nitrogen removal (WWTP1) and a combined nitrogen and phosphorus removal (WWTP2) benchmark wastewater treatment plant...

  16. Plant-wide Control Strategy for Improving Produced Water Treatment

    DEFF Research Database (Denmark)

    Yang, Zhenyu; Pedersen, Simon; Løhndorf, Petar Durdevic

    2016-01-01

    This work focuses on investigation and development of an innovative Produced Water Treatment (PWT) technology for offshore oil & gas production by employing the model-based plant-wide control strategy. The key contributions lie in two folds: (i) the advanced anti-slug analysis and control...

  17. Performance of wastewater treatment plants in Jordan and suitability ...

    African Journals Online (AJOL)

    There is an increasing trend to require more efficient use of water resources, both in urban and rural environments. In Jordan, the increase in water demand, in addition to water shortage has led to growing interest in wastewater reuse. In this work, characteristics of wastewater for four wastewater treatment plants were ...

  18. Methodology for Plantwide Design and Optimization of Wastewater Treatment Plants

    DEFF Research Database (Denmark)

    Maria Dragan, Johanna; Zubov, Alexandr; Sin, Gürkan

    2017-01-01

    Design of Wastewater Treatment Plants (WWTPs) is a complex engineering task which requires integration of knowledge and experience from environmental biotechnology, process engineering, process synthesis and design as well as mathematical programming. A methodology has been formulated and applied...... for the systematic analysis and development of plantwide design of WWTPs using mathematical optimization and statistical methods such as sensitivity and uncertainty analyses....

  19. Ethnobotanical survey of plants used for the treatment of ...

    African Journals Online (AJOL)

    Constipation is the commonest gastrointestinal complaint in most developed and poor countries including South Africa. An ethnobotanical survey of plants used by herbalists, traditional healers and rural dwellers for the treatment of constipation was conducted in the Nkonkobe Municipality, Eastern Cape Province of South ...

  20. State-of-art report on digital I and C system reliability issues for nuclear power plants

    International Nuclear Information System (INIS)

    Hwang, In Koo; Lee, Dong Gyoung; Cha, Kyung Ho; Kwon, Kee Choon; Wood, Richard T.

    2000-01-01

    As the instrumentation and control (Iand C) equipment suppliers tend to provide digital components rather than conventional analog type components for instrument and control systems of nuclear power plants(NPPs), it is unavoidable to adopt digital equipment for safety I and C systems as well as non-safety systems. However, the full introduction of digital equipment to I and C systems of nuclear power plants raises several concerns which have not been considered for conventional analog I and C systems. The two major examples of the issues of digital systems are electromagnetic compatibility (EMC) and software reliability. KAERI invited a technical expert, Dr. Richard T. Wood, from Oak Ridge National Laboratory (ORNL) in Unites States and held seminars to recognize the state-of-art of the above issues and to share the information on techniques dealing with the problems. Dr. Wood has been working on the development of EMC guidelines and technical basis in using digital equipment for safety systems in nuclear power plants on the sponsorship of US Nuclear Regulatory Commission (NRC). Being based on his statements and discussions during his visit, this report describes technical considerations and issues on digital safety I and C system application in NPPs, EMC methods, environmental effects vulnerable to digital components, reliability assurance methods, etc. (author)

  1. Infrequent use of medicinal plants from India in snakebite treatment

    Directory of Open Access Journals (Sweden)

    Manali Sughosh Upasani

    2018-03-01

    Full Text Available Snakes have fascinated humankind for millennia. Snakebites are a serious medical, social, and economic problem that are experienced worldwide; however, they are most serious in tropical and subtropical countries. The reasons for this are 1 the presence of more species of the most dangerous snakes, 2 the inaccessibility of immediate medical treatment, and 3 poor health care. The goal of this study was to collect information concerning rare, less utilized, and less studied medicinal plants. More than 100 plants were found to have potential to be utilized as anti-snake venom across India. Data accumulated from a variety of literature sources revealed useful plant families, the parts of plants used, and how to utilize them. In India, there are over 520 plant species, belonging to approximately 122 families, which could be useful in the management of snakebites. This study was conducted to encourage researchers to create herbal antidotes, which will counteract snake venom. These may prove to be an inexpensive and easily assessable alternative, which would be of immense importance to society. Plants from families such as Acanthaceae, Arecaceae, Apocynaceae, Caesalpiniaceae, Asteraceae, Cucurbitaceae, Fabaceae, Euphorbiaceae, Lamiaceae, Rubiaceae, and Zingiberaceae are the most useful. In India, experts of folklore are using herbs either single or in combination with others. Keywords: Appraise traditional medicinal plants, Ethnomedicine, India, Snake antivenom

  2. Preventative Maintenance and Reliability Study for the Central Heating and Power Plant at Fort Wainwright, Alaska

    National Research Council Canada - National Science Library

    Vavrin, John L; Brown, III, William T; Kemme, Michael R; Westerman, John; Lorand, Robert T; Walden, Charles; Swinehart, Curtis

    2007-01-01

    ... (FWA) (Vavrin et al. 2006) recommended that if the option for a new CHPP were to be pursued, among the tasks suggested for further analysis was to determine predictive maintenance requirements and new technologies for the existing plant...

  3. Preventive Maintenance and Reliability Study for the Central Heating and Power Plant at Fort Wainwright, Alaska

    National Research Council Canada - National Science Library

    Vavrin, John L; Brown, III, William T; Kemme, Michael R; Westerman, John; Lorand, Robert; Walden, Charles; Swinehart, Curtis

    2007-01-01

    ... (FWA) (Vavrin et al. 2006) recommended that if the option for a new CHPP were to be pursued, among the tasks suggested for further analysis was to determine predictive maintenance requirements and new technologies for the existing plant...

  4. Reliability assessment and correlation analysis of evaluating orthodontic treatment outcome in Chinese patients.

    Science.gov (United States)

    Song, Guang-Ying; Zhao, Zhi-He; Ding, Yin; Bai, Yu-Xing; Wang, Lin; He, Hong; Shen, Gang; Li, Wei-Ran; Baumrind, Sheldon; Geng, Zhi; Xu, Tian-Min

    2014-03-01

    This study aimed to assess the reliability of experienced Chinese orthodontists in evaluating treatment outcome and to determine the correlations between three diagnostic information sources. Sixty-nine experienced Chinese orthodontic specialists each evaluated the outcome of orthodontic treatment of 108 Chinese patients. Three different information sources: study casts (SC), lateral cephalometric X-ray images (LX) and facial photographs (PH) were generated at the end of treatment for 108 patients selected randomly from six orthodontic treatment centers throughout China. Six different assessments of treatment outcome were made by each orthodontist using data from the three information sources separately and in combination. Each assessment included both ranking and grading for each patient. The rankings of each of the 69 judges for the 108 patients were correlated with the rankings of each of the other judges yielding 13 873 Spearman rs values, ranging from -0.08 to +0.85. Of these, 90% were greater than 0.4, showing moderate-to-high consistency among the 69 orthodontists. In the combined evaluations, study casts were the most significant predictive component (R(2)=0.86, P<0.000 1), while the inclusion of lateral cephalometric films and facial photographs also contributed to a more comprehensive assessment (R(2)=0.96, P<0.000 1). Grading scores for SC+LX and SC+PH were highly significantly correlated with those for SC+LX+PH (r(SC+LX)vs.(SC+LX+PH)=0.96, r(SC+PH)vs.(SC+LX+PH)=0.97), showing that either SC+LX or SC+PH is an excellent substitute for all three combined assessment.

  5. Water Treatment Pilot Plant Design Manual: Low Flow Conventional/Direct Filtration Water Treatment Plant for Drinking Water Treatment Studies

    Science.gov (United States)

    This manual highlights the project constraints and concerns, and includes detailed design calculations and system schematics. The plant is based on engineering design principles and practices, previous pilot plant design experiences, and professional experiences and may serve as ...

  6. Resilience and reliability of compact vertical-flow treatment wetlands designed for tropical climates.

    Science.gov (United States)

    Lombard-Latune, R; Pelus, L; Fina, N; L'Etang, F; Le Guennec, B; Molle, P

    2018-06-10

    Most of the tropical areas have sanitation problems to contend with. The French system of vertical-flow treatment wetlands (FS-VFTW) fed with raw wastewater could be a good water and sludge management solution. The purpose-adapted tropical design can reduce area requirement to below 1 m 2 /population equivalents (p.e.). The Taupinière FS-VFTW on Martinique Island was built according to this design, with one stage but with a saturated layer at the bottom of the filter and a simplified trickling filter (TF) added for further treatment to meet the high performances targeted. Unsaturated/saturated vertical-flow filters (US/S FS-VFTW) have shown improved performances on total nitrogen, carbon and suspended solids removal in temperate climates, but the performances in tropical conditions remain unknown. Here, we report on real-world-operation in the French Overseas Territories (FOT), the reliability and performances of this VFCW tropical-design. The system experienced loading conditions ranging from 30% to 165% of nominal carbonaceous biological oxygen demand (BOD 5 ), as well as tropical rainstorms that brought over 7 times the nominal hydraulic load. Over a period of 3 years, 29 campaigns collected 24-h flow-proportional samples at each treatment stage (raw wastewater, FS-VFTW outlet, TF outlet). When applied loads were close to nominal values, the US/S FS-VFTW itself guarantees 85/90/60/50% removal and 125/25/40/50 mg/L at the outlet for chemical oxygen demand (COD)/total suspended solids (TSS)/total Kjeldahl nitrogen (TKN)/total nitrogen (TN), respectively. By comparison with US/S systems in mainland France, it appears that the warmer tropical-climate temperatures facilitate both nitrification and denitrification kinetics. Performances in overload conditions confirm that the US/S FS-VFTW remains robust and reliable although COD and TKN removal are impacted, especially after strong tropical rain events. By adding a simple compact trickling filter to a US/S FS

  7. Economics of wastewater treatment in GTL plant using spray technique

    Energy Technology Data Exchange (ETDEWEB)

    Enyi, G.C.; Nasr, G.G.; Burby, M. [University of Salford, Manchester, M5 4WT (United Kingdom)

    2013-07-01

    In a Gas-to-liquid (GTL) plant, significant quantities of CO2 and reaction water are produced and various chemicals are used as intermediate treatment chemicals. The reaction water is contaminated by these chemicals which impair the pH and the related properties of the water. The pH has to be controlled in the effluent treatment unit before the water is re-used or released to the environment. The overall aim of this investigation is to create a novel technique to address the problem of waste water treatment in GTL plants which will assist in the reduction of greenhouse gas (CO2) emissions into the atmosphere. A laboratory-scale effluent neutralisation unit for pH control utilising gas injectors was designed and built. The unit used the CO2 produced as a by-product of GTL process as wastewater treatment chemical instead of the conventional Sulphuric acid. The quality of wastewater after treatment with CO2 met the standards set by the state regulatory agency. The economics of the new process shows a better payout period of 3.6 years for capital investment of $1,645 Million compared to 4.7 years for an existing plant layout with capital investment of $1,900 Million. The effects of increase in plant capacity showed a lower payback back of 2.8 years for plant capacity of 140,000 barrels/day (22258 m3/day), 3.6 years for 34,000 barrels/day and 6.0 years for 12,500 barrels/day (1987 m3/day) plant capacity. The sensitivity analysis using crystal ball simulator with 'Microsoft Excel' shows that the annual revenue has the greatest effects on the NPV of the plant than the CAPEX and inflation rate. Apart from the environmental benefits the process generates by reducing CO2 emissions into the atmosphere, the study also concludes that the replacement of conventional Sulphuric acid (H2SO4) unit with CO2 improves the economics of the plant.

  8. Application of waterworks sludge in wastewater treatment plants

    DEFF Research Database (Denmark)

    Sharma, Anitha Kumari; Thornberg, D.; Andersen, Henrik Rasmus

    2013-01-01

    The potential for reuse of iron-rich sludge from waterworks as a replacement for commercial iron salts in wastewater treatment was investigated using acidic and anaerobic dissolution. The acidic dissolution of waterworks sludge both in sulphuric acid and acidic products such as flue gas washing...... for removal of phosphate in the wastewater treatment was limited, because the dissolved iron in the digester liquid was limited by siderite (FeCO3) precipitation. It is concluded that both acidic and anaerobic dissolution of iron-rich waterworks sludge can be achieved at the wastewater treatment plant...

  9. Spent solvent treatment process at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Sasaki, Akihiro; Saka, Munenori; Araya, Toshiyuki; Kitamura, Tomohiro; Wakamatsu, Toshiyuki

    2005-01-01

    In order to dispose of spent organic solvent and diluent produced by the PUREX method, it is desirable that it should be in stable form for easy handling. For this reason, spent solvent is reduced to powder form and further molded so that it becomes easier to handle for temporary storage at Rokkasho Reprocessing Plant (RRP). In this paper, the treatment unit for reducing spent solvent to powder form and the treatment unit for modeling the powder are introduced as well as their treatment results during Chemical Test. (author)

  10. RESPONSE OF TOMATO PLANTS EXPOSED TO TREATMENT WITH NANOPARTICLES

    Directory of Open Access Journals (Sweden)

    Tommaso Giordani

    2012-07-01

    Full Text Available In this work the response of Tomato plants cv. Micro-Tom to nanoparticles (NPs treatment was investigated. Tomato seedlings were grown in hydroponic condition and NPs treatments were carried out by adding Fe3O4 or TiO2 NPs to nutrient solution. At the end of treatments, NPs root uptake and tissue deposition were investigated using Environmental Scanning Electron Microscope, equipped with energy dispersive spectroscopy for chemical identification. At morphological level, one week after the beginning of NP treatment, seedlings grown with high concentration of TiO2 NPs showed an abnormal proliferation of root hairs, as compared to the control seedlings and to the seedlings exposed to Fe3O4 NPs, Shoot morphology did not differ in tomato seedlings grown under different conditions and no symptoms of toxicity were observed in NP-treated plants. In order to analyse genetic effects of NPs treatments, RNA transcription was studied in roots of NP-exposed and control plants by Illumina RNA sequencing, evidencing the induction of transposable elements.

  11. Life Cycle Assessment to Municipal Wastewater Treatment Plant

    International Nuclear Information System (INIS)

    Garcia, J. s.; Herrera, I.; Rodriguez, A.

    2011-01-01

    The evaluation was done at a Municipal Wastewater Treatment Plant (MWTP), through the application of the methodology of Life Cycle Assessment (LCA) performed by using a commercial tool called SIMAPRO. The objective of this study was to apply Life Cycle Assessment (LCA) in two systems: municipal wastewater effluent without treatment and Wastewater Treatment Plant (WTP) that is operating in poor condition and has a direct discharge to a natural body, which is a threat to the environment. A LCA was done using SIMAPRO 7, in order to determine the environmental impact in each scenery was assessed, a comparison of the impacts and propose improvements to decrease, following the steps this methodology and according to the respective standardized normative (ISO 14040/ ISO 14044). In this study, most of used data have been reported by the plant from early 2010 and some data from literature. We identified the environmental impacts generated by the treatment, making emphasis on those related to the subsequent use of the water body receiving the discharge, such as eutrophication (near to 15% reduction). Likewise, a comparative analysis between the impacts in the two systems, with and without treatment by analyzing the variation in the impact categories studied. Finally within this work, alternatives of improvements, in order to reduce the identified and quantified impacts are proposed. (Author) 33 refs.

  12. Use of F.M.E.A. for reliability analysis of safety systems in nuclear power plants

    International Nuclear Information System (INIS)

    Barbet, J.F.; Llory, M.; Villemeur, A.

    1982-01-01

    In the framework of the French nuclear power plant program, reliability studies of safety systems have been carried out at the Electricite de France since 1975. The main results of the studies are examined; about the methodological aspects it appears useful to develop an inductive approach such as the Failure Modes and Effects Analysis (F.M.E.A.). The method is described with its advantages and limitations; the possibilities of use of F.M.E.A. to solve specific safety problems are investigated. To conclude, the future trends of research and development in this field at Electricite de France are pointed out [fr

  13. Integration of energy and environmental systems in wastewater treatment plants

    Energy Technology Data Exchange (ETDEWEB)

    Long, Suzanna [Department of Engineering Management and Systems Engineering, 600 W, 14th Street, 215 EMGT Building, Rolla, MO-65401, 573-341-7621 (United States); Cudney, Elizabeth [Department of Engineering Management and Systems Engineering, 600 W, 14th Street, 217 EMGT Building, Rolla, MO-65401, 573-341-7931 (United States)

    2012-07-01

    Most wastewater treatment facilities were built when energy costs were not a concern; however, increasing energy demand, changing climatic conditions, and constrained energy supplies have resulted in the need to apply more energy-conscious choices in the maintenance or upgrade of existing wastewater treatment facilities. This research develops an integrated energy and environmental management systems model that creates a holistic view of both approaches and maps linkages capable of meeting high-performing energy management while meeting environmental standards. The model has been validated through a case study on the Rolla, Missouri Southeast Wastewater Treatment Plant. Results from plant performance data provide guidance to improve operational techniques. The significant factors contributing to both energy and environmental systems are identified and balanced against considerations of cost.

  14. Performance evaluation of effluent treatment plant for automobile industry

    Energy Technology Data Exchange (ETDEWEB)

    Ansari, Farid [Department of Applied Science and Humanities, PDM College of Engineering, Bahadurgarh (Haryana) (India); Pandey, Yashwant K. [School of Energy and Environmental Studies, Devi Ahilya Vishwavidyalaya, Indore (India); Kumar, P.; Pandey, Priyanka [Department of Environmental Science, Post Graduate College Ghazipur (IN

    2013-07-01

    The automobile industry’s wastewater not only contains high levels of suspended and total solids such as oil, grease, dyestuff, chromium, phosphate in washing products, and coloring, at various stages of manufacturing but also, a significant amount of dissolved organics, resulting in high BOD or COD loads. The study reveals the performance, evaluation and operational aspects of effluent treatment plant and its treatability, rather than the contamination status of the real property. The Results revealed that the treated effluent shows most of the parameters are within permissible limits of Central Pollution Control Board (CPCB), India and based on the site visits, discussion with operation peoples, evaluation of process design, treatment system, existing effluent discharge, results of sample analyzed and found that effluent treatment plant of automobile industry are under performance satisfactory.

  15. TECHNOLOGICAL PROCESS ASSESSMENT OF THE DRINKING WATER TREATMENT AT TARGU-MURES WATER TREATMENT PLANT

    Directory of Open Access Journals (Sweden)

    CORNELIA DIANA HERTIA

    2011-03-01

    Full Text Available This paper intends to assess the technological process of obtaining drinking water at Targu-Mures water treatment plant. The assessment was performed before changing the technological process and four months were chosen to be analized during 2008: January, April, July and October for its efficiency analysis on treatment steps. Mures River is the water source for the water treatment plant, being characterized by unsteady flow and quality parameters with possible important variability in a very short period of time. The treatment technological process is the classic one, represented by coagulation, sedimentation, filtration and disinfection, but also prechlorination was constantly applied as additional treatment during 2008. Results showed that for the measured parameters, raw water at the water treatment plant fits into class A3 for surface waters, framing dictated by the bacterial load. The treatment processes efficiency is based on the performance calculation for sedimentation, filtration, global and for disinfection, a better conformation degree of technological steps standing out in January in comparison to the other three analyzed months. A variable non-compliance of turbidity and residual chlorine levels in the disinfected water was observed constantly. Previous treatment steps managed to maintain a low level of oxidisability, chlorine consumption and residual chlorine levels being also low. 12% samples were found inconsistent with the national legislation in terms of bacteriological quality. Measures for the water treatment plant retechnologization are taken primarily for hyperchlorination elimination, which currently constitutes a discomfort factor (taste, smell, and a generating factor of chlorination by-products.

  16. Planning and implementation of reliability/quality programs to energy plants

    International Nuclear Information System (INIS)

    Quenon, J.

    1986-01-01

    Quality Assurance principles have long been applied in part to many varied industrial enterprises. The advent of commercial nuclear power brought the evolution of a more comprehensive approach to the applications of quality assurance programs in this industry. However, the application philosophy was almost totally aimed at assuring the safety of the worker and the public. Recently, there has been a strong movement by industries and business in the U.S. and Europe to apply quality assurance in a more general way to assure overall reliability as well as safety. This paper describes an approach to enable management to not only make initial determinations of how to apply the elements of a reliability/quality assurance program, but how to continuously adjust the program to optimize the benefits that can be obtained

  17. Maintenance personnel performance simulation (MAPPS): a model for predicting maintenance performance reliability in nuclear power plants

    International Nuclear Information System (INIS)

    Knee, H.E.; Krois, P.A.; Haas, P.M.; Siegel, A.I.; Ryan, T.G.

    1983-01-01

    The NRC has developed a structured, quantitative, predictive methodology in the form of a computerized simulation model for assessing maintainer task performance. Objective of the overall program is to develop, validate, and disseminate a practical, useful, and acceptable methodology for the quantitative assessment of NPP maintenance personnel reliability. The program was organized into four phases: (1) scoping study, (2) model development, (3) model evaluation, and (4) model dissemination. The program is currently nearing completion of Phase 2 - Model Development

  18. Probabilistic reliability analyses to detect weak points in secondary-side residual heat removal systems of KWU PWR plants

    International Nuclear Information System (INIS)

    Schilling, R.

    1984-01-01

    Requirements made by Federal German licensing authorities called for the analysis of the second-side residual heat removal systems of new PWR plants with regard to availability, possible weak points and the balanced nature of the overall system for different incident sequences. Following a description of the generic concept and the process and safety-related systems for steam generator feed and main steam discharge, the reliability of the latter is analyzed for the small break LOCA and emergency power mode incidents, weak points in the process systems are identified, remedial measures of a system-specific and test-strategic nature are presented and their contribution to improving system availability is quantified. A comparison with the results of the German Risk Study on Nuclear Power Plants (GRS) shows a distinct reduction in core meltdown frequency. (orig.)

  19. Reliability analyses to detect weak points in secondary-side residual heat removal systems of KWU PWR plants

    International Nuclear Information System (INIS)

    Schilling, R.

    1983-01-01

    Requirements made by Federal German licensing authorities called for the analysis of the secondary-side residual heat removal systems of new PWR plants with regard to availability, possible weak points and the balanced nature of the overall system for different incident sequences. Following a description of the generic concept and the process and safety-related systems for steam generator feed and main steam discharge, the reliability of the latter is analyzed for the small break LOCA and emergency power mode incidents, weak points in the process systems identified, remedial measures of a system-specific and test-strategic nature presented and their contribution to improving system availability quantified. A comparison with the results of the German Risk Study on Nuclear Power Plants (GRS) shows a distinct reduction in core meltdown frequency. (orig.)

  20. Impact of Advanced Alarm Systems and Information Displays on Human Reliability in the Digital Control Room of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Jong Hyun; Dang, Vinh N

    2011-01-01

    This paper discusses the potential impacts of two advanced features of digital control rooms, alarm systems and information display systems, on the Human Reliability Analysis (HRA) in nuclear power plants. Although the features of digital control rooms have already been implemented in new or upgraded nuclear power plants, HRAs have so far not taken much credit for these features. In this circumstance, this paper aims at examining the potential effects of these features on human performance and discussing how these effects can be addressed with existing HRA methods. A conclusion derivable from past experimental studies is that those features are supportive in the severe conditions such as complex scenarios and knowledge-based works. However, in the less complex scenarios and rule-based work, they may have no difference with or sometimes negative impacts on operator performance. The discussion about the impact on the HRA is provided on the basis on the THERP method

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

    International Nuclear Information System (INIS)

    1980-04-01

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

  2. Job analysis of the instrument and control technician position for the nuclear power plant maintenance personnel reliability model

    International Nuclear Information System (INIS)

    Siegel, A.I.; Bartter, W.D.; Federman, P.J.

    1983-08-01

    This report is one of a series that is planned to describe the results of a program undertaken by the Oak Ridge National Laboratory (ORNL) for the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, to define, develop, validate, and disseminate a methodology for the quantitative prediction of human reliability in the conduct of maintenance tasks in nuclear power plants (NPPs). ORNL has subcontracted portions of this effort to Applied Psychological Services, Inc. This report on the job analysis of the Instrument and Control technician (NUREG/CR-3274) and a report on the job analysis of the electrician position (NUREG/CR-3275) comprise a part of the initial efforts of the development phase of this program. With the publication of the job analysis of the electrician position, the series of job analyses reports addressing nuclear power plant maintenance personnel will be complete. Subsequent reports addressing model development and validation are planned

  3. CO{sub 2}-recycling by plants: how reliable is the carbon isotope estimation?

    Energy Technology Data Exchange (ETDEWEB)

    Siegwolf, R T.W.; Saurer, M [Paul Scherrer Inst. (PSI), Villigen (Switzerland); Koerner, C [Basel Univ., Basel (Switzerland)

    1997-06-01

    In the study of plant carbon relations, the amount of the respiratory losses from the soil was estimated, determining the gradient of the stable isotope {sup 13}C with increasing plant canopy height. According to the literature 8-26% of the CO{sub 2} released in the forests by soil and plant respiratory processes are reassimilated (recycled) by photosynthesis during the day. Our own measurements however, which we conducted in grass land showed diverging results from no indicating of carbon recycling, to a considerable {delta}{sup 13}C gradient suggesting a high carbon recycling rate. The role of other factors, such as air humidity and irradiation which influence the {delta}{sup 13}C in a canopy as well, are discussed. (author) 3 figs., 4 refs.

  4. Energy supply waste water treatment plant West Brabant

    Energy Technology Data Exchange (ETDEWEB)

    Poldervaart, A; Schouten, G J

    1983-09-01

    For the energy supply for the waste water treatment plant (rwzi-Bath) of the Hoogheemraadschap West-Brabant three energy sources are used: biogas of the digesters, natural gas and electricity delivered by the PZEM. For a good balance between heat/power demand and production a heat/power plant is installed. By using this system a high efficiency for the use of energy will be obtained. To save energy the oxygen concentration in the aerationtanks is automatically controlled by means of regulating the position of the air supply control valves and the capacity and number of the turbocompressors. For the oxygen controlsystem a Siemens PLC is used.

  5. Experience and perspectives of nuclear power plant reliability evaluation at Institute J. Stefan; Izkusnje in perspektive vrednotenja zanesljivosti jedrskih elekrarn na Institutu Jozef Stefan

    Energy Technology Data Exchange (ETDEWEB)

    Susnik, J [Institut Jozef Stefan, Ljubljana (Yugoslavia)

    1979-07-01

    First a short report on development of computer programs for the reliability evaluation and the findings regarding the adequate reliability of Nuclear Power Plant safety systems are given. Then evaluation of the general NPP availability situation is discussed and suggestions for planning and achieving an adequate high availability are presented. (author)

  6. The effect of plant reliability improvement in the cost of generating electricity

    International Nuclear Information System (INIS)

    Nejat, S.; Sanders, R.C.; Tsoulfanidis, N.

    1982-01-01

    The objective of this investigation is to study the economic benefits in operating a nuclear power plant, as a result of improving the availability of the secondary (steam) loop of the plant. A new method has been developed to obtain availability, frequency of failure, probability and frequency of operation, cycle time, and uptime for different capacity states of a parallel series system having components with failure and repair rates distributed exponentially in time. The method has been applied to different subsystems, systems, and the secondary loop of a plant as a whole. The effect of having spare parts for several components, as measured by savings in the generation of electricity, is also studied. The Kettelle algorithm was applied to determine optimal allocation of spare parts to achieve maximum availability or minimum cost of electricity, subject to a fixed spare parts budget. The savings per year for optimal spare parts allocation and different spare parts budgets were obtained. The results show that the utility will save its customers a large amount of money if spare parts are purchased, especially at the beginning of the plant operation, and are allocated judiciously

  7. Nuclear power plant safe operation principles and some topics concerning systems reliability analysis

    International Nuclear Information System (INIS)

    Borsky, M.; Kreim, R.; Stanicek, J.

    1997-01-01

    General safety criteria are specified, and nuclear power plant equipment is classified into systems either important or unimportant for nuclear safety. The former class is subdivided into safety systems and safety related systems. The safety requirements concern earthquakes, storms, fires, floods, man-induced events, and equipment failures. The actual state of systems important for safety is described. (M.D.)

  8. Determination of installation capacity in reservoir hydro-power plants considering technical, economical and reliability indices

    DEFF Research Database (Denmark)

    Hosseini, S.M.H.; Forouzbakhsh, Farshid; Fotouh-Firuzabad, Mahmood

    2008-01-01

    One of the most important issues in planning the ‘‘reservoir” type of hydro-power plants (HPP) is to determine the installation capacity of the HPPs and estimate its annual energy value. In this paper, a method is presented. A computer program has been developed to analyze energy calculation...

  9. Human reliability and plant operating efficiency: Are 12-hour work schedules cause for concern?

    International Nuclear Information System (INIS)

    Baker, T.L.

    1992-01-01

    Since the introduction of 12-h shifts to the US nuclear power industry only 8 yr ago, compressed workweek schedules have proliferated among operations departments at a phenomenal rate. Many plants that continue to use 8-h shifts during normal operations routinely change to scheduled 12-h shifts during refueling or maintenance outages. The most critical issue in the use of extended work shifts is whether alertness, physical stamina, or mental performance are compromised to the point of reducing safety or efficiency of nuclear power plant operation. Laboratory and field research sponsored by the National Institute of Occupational Safety and Health suggests that alertness, measured by self-ratings, and mental performance, measured by computer-based performance tests, are impaired on 12-h shifts compared with 8-h shifts. In contrast to these findings, plant operating efficiency and operator performance have been rated as improved in two field studies conducted in operating nuclear power plants (Fast Flux Test Facility, Washington and Ontario Hydro, Canada). A recent Electric Power Research Institute review of nuclear industry experience with 12-h shifts also suggests an overwhelmingly positive rating of 12-h schedules from both control room operators and management

  10. Productivity of sugarcane plants of ratooning with fertilizing treatment

    Directory of Open Access Journals (Sweden)

    MUHADIONO

    2010-01-01

    Full Text Available Latief AS, Syarief R, Pramudya B, Muhadiono. 2010. Productivity of sugarcane plants of ratooning with various fertilizing treatments. Nusantara Bioscience 2: 43-47. This research aims to determine the sugarcane plants of ratooning productivity with low external input of fertilization treatment towards farmers can increase profits. The method used is the Completely Randomized Block Design (CRBD with four treatments and three repetitions (4x3. Sugarcane varieties R 579 planted in each patch experiment 5x5 m2. Dosage of fertilizer: P0 = 3.6 kg/year plot experiment was 100% dosage usage of chemical fertilizers used by farmers. Further dosages were P1 (75% = 2.7 kg/plot, P2 (50% = 1.8 kg/plot and P3 (0.25% = 0.9 kg/plot, each supplemented with fertilizer 5 mL of liquid organic/patch a year. Sugarcane crops with a variety of treatment showed no significant difference. The highest productivity was achieved at dosages of P2 (50% chemical fertilizers plus organic fertilizer is 21.67 kg per square meter. Chemical fertilizers can be saved 7 quintals per hectare a year or Rp 997,500 per year. Additional costs of liquid organic fertilizer Rp. 100,000 per hectare year and labor Rp 100,000 per hectare, so the additional advantage of saving farmers fertilizer Rp. 797,500 per year.

  11. Anterior Cruciate Ligament Tear: Reliability of MR Imaging to Predict Stability after Conservative Treatment

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Hye Won; Ahn, Jin Hwan; Ahn, Joong Mo; Yoon, Young Cheol; Hong, Hyun Pyo; Yoo, So Young; Kim, Seon Woo [Sungkyunkwan University School of Medicine, Seoul (Korea, Republic of)

    2007-06-15

    The aim of this study is to evaluate the reliability of MR imaging to predict the stability of the torn anterior cruciate ligament (ACL) after complete recovery of the ligament's continuity. Twenty patients with 20 knee injuries (13 males and 7 females; age range, 20 54) were enrolled in the study. The inclusion criteria were a positive history of acute trauma, diagnosis of the ACL tear by both the physical examination and the MR imaging at the initial presentation, conservative treatment, complete recovery of the continuity of the ligament on the follow up (FU) MR images and availability of the KT-2000 measurements. Two radiologists, who worked in consensus, graded the MR findings with using a 3-point system for the signal intensity, sharpness, straightness and the thickness of the healed ligament. The insufficiency of ACL was categorized into three groups according to the KT-2000 measurements. The statistic correlations between the grades of the MR findings and the degrees of ACL insufficiency were analyzed using the Cochran-Mantel-Haenszel test (p < 0.05). The p-values for each category of the MR findings according to the different groups of the KT-2000 measurements were 0.9180 for the MR signal intensity, 1.0000 for sharpness, 0.5038 for straightness and 0.2950 for thickness of the ACL. The MR findings were not significantly different between the different KT-2000 groups. MR imaging itself is not a reliable examination to predict stability of the ACL rupture outcome, even when the MR images show an intact appearance of the ACL.

  12. Bag filters at biofuelled plants, reliability and economy of operation; Slangfilter vid bioeldade anlaeggningar, tillfoerlitlighet och driftsekonomi

    Energy Technology Data Exchange (ETDEWEB)

    Lindau, Leif [SYCON Energikonsult, Malmoe (Sweden)

    2002-04-01

    The background to this work is the increased requirements on dust emission control for smaller (2-50 MW) biofuel plants in Sweden, where established technology consisting of multi cyclones cannot meet the emission demands, and where the specific cost of the large scale established technology (electrostatic precipitators) quickly increases with decreased plant size. Operational experience of bag filters on Swedish biofuel plants down to a size of 2 MW has been collected. The operational experience is remarkably uniform and positive and availability is high. Bag life, being the most important operational cost factor, is between two and eleven years. Most frequent material used is aramide, but also PPS is employed and the experience of both materials is good. The cost relation between bag filter (including an upstream skimmer) and electrostatic precipitator has been studied based on supplier quotations. Bag filter always has the lowest first cost. At one year bag life, the total cost of a bag filter is less than that for an electrostatic precipitator for plants smaller than 15 MW, and at more than one year's bag life, the bag filter has the lowest total cost for plants up to 50 MW. For plants smaller than 5-10 MW, the difference in total cost is very high. With some simple means for quality assurance of new bags, premature failure rate can be reduced. Following up cleaning interval and/or emission during operation time, gives information about the development of bag condition and necessary bag change can be foreseen. Since bag filters are more prone to damage by fire than electrostatic precipitators, the process of damage due to entrained sparks has been analysed based on practical observations and a thermal calculation. This consideration shows that this damage mode can be eliminated by an upstream skimmer having moderate but reliable performance. The result is well in coherence with the practical operational experience found that with an adequate skimmer

  13. Life Cycle Management for Equipments in Nuclear Plants Based on Reliability

    International Nuclear Information System (INIS)

    Wang Dalin; Sun Jinlong

    2012-01-01

    Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (author)

  14. Life cycle management for equipments in nuclear plants based on reliability and actual conditions

    International Nuclear Information System (INIS)

    Dalin, Wang; Jingquan, Liu; Peng, Liu

    2010-01-01

    Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (authors)

  15. HTGR plant availability and reliability evaluations. Volume I. Summary of evaluations

    International Nuclear Information System (INIS)

    Cadwallader, G.J.; Hannaman, G.W.; Jacobsen, F.K.; Stokely, R.J.

    1976-12-01

    The report (1) describes a reliability assessment methodology for systematically locating and correcting areas which may contribute to unavailability of new and uniquely designed components and systems, (2) illustrates the methodology by applying it to such components in a high-temperature gas-cooled reactor [Public Service Company of Colorado's Fort St. Vrain 330-MW(e) HTGR], and (3) compares the results of the assessment with actual experience. The methodology can be applied to any component or system; however, it is particularly valuable for assessments of components or systems which provide essential functions, or the failure or mishandling of which could result in relatively large economic losses

  16. An application of possibilistic reliability theory to a subsystem of a nuclear power plant

    International Nuclear Information System (INIS)

    Capelle, B.; Kerre, E.

    1994-01-01

    Since the late seventies, multi-state structure functions have been introduced to overcome the shortcomings of the classical and binary approach of the structural aspects of systems and their components. The uncertainty about the state of a system and its components classically is described by probability theory and possibility theory. The spread and success of these models, however, highly depends upon the development of computer tools that allow the reliability engineer to apply these new methods rather easily. In this paper, the CARA tool, which is able to represent and study the multi-state aspects of systems and their components when only incomplete information is available, is presented

  17. Seismic effects on the reliability of polar cranes for nuclear power plants

    International Nuclear Information System (INIS)

    Kaiser, W.; Friedrich, H.; Knoefel, L.

    1985-01-01

    In order to meet the requirements of nuclear safety reactor components have to be designed aseismically. A model for studying simulated seismic effects on the reliability of containment equipment polar cranes is presented. Based on this model vertical and horizontal motions of the crane are investigated. Emphasis is laid on non-linearities caused by malfunctions such as lift of the crane from the runaway, lift of the trolley from the beams, slackening of the ropes as well as sliding of blocked track wheels. Seismic excitations are simulated by computer produced accelerograms

  18. HTGR plant availability and reliability evaluations. Volume I. Summary of evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, G.J.; Hannaman, G.W.; Jacobsen, F.K.; Stokely, R.J.

    1976-12-01

    The report (1) describes a reliability assessment methodology for systematically locating and correcting areas which may contribute to unavailability of new and uniquely designed components and systems, (2) illustrates the methodology by applying it to such components in a high-temperature gas-cooled reactor (Public Service Company of Colorado's Fort St. Vrain 330-MW(e) HTGR), and (3) compares the results of the assessment with actual experience. The methodology can be applied to any component or system; however, it is particularly valuable for assessments of components or systems which provide essential functions, or the failure or mishandling of which could result in relatively large economic losses.

  19. Scientific approach and practical experience for reconstruction of waste water treatment plants in Russia

    Directory of Open Access Journals (Sweden)

    Makisha Nikolay

    2017-01-01

    Full Text Available Protection of water bodies has a strict dependence on reliable operation of engineering systems and facilities for water supply and sewage. The majority of these plants and stations has been constructed in 1970-1980's in accordance with rules and regulations of that time. So now most of them require reconstruction due to serious physical or/and technological wear. The current condition of water supply and sewage systems and facilities frequently means a hidden source of serious danger for normal life support and ecological safety of cities and towns. The article reveals an obtained experience and modern approaches for reconstruction of waste water and sludge treatment plants that proved their efficiency even if applied in limited conditions such as area limits, investments limits. The main directions of reconstruction: overhaul repair and partial modernization of existing facilities on the basis of initial project; - restoration and modernization of existing systems on the basis on the current documents and their current condition; upgrade of waste water treatment plants (WWTPs performance on the basis of modern technologies and methods; reconstruction of sewage systems and facilities and treatment quality improvement.

  20. Scientific approach and practical experience for reconstruction of waste water treatment plants in Russia

    Science.gov (United States)

    Makisha, Nikolay; Gogina, Elena

    2017-11-01

    Protection of water bodies has a strict dependence on reliable operation of engineering systems and facilities for water supply and sewage. The majority of these plants and stations has been constructed in 1970-1980's in accordance with rules and regulations of that time. So now most of them require reconstruction due to serious physical or/and technological wear. The current condition of water supply and sewage systems and facilities frequently means a hidden source of serious danger for normal life support and ecological safety of cities and towns. The article reveals an obtained experience and modern approaches for reconstruction of waste water and sludge treatment plants that proved their efficiency even if applied in limited conditions such as area limits, investments limits. The main directions of reconstruction: overhaul repair and partial modernization of existing facilities on the basis of initial project; - restoration and modernization of existing systems on the basis on the current documents and their current condition; upgrade of waste water treatment plants (WWTPs) performance on the basis of modern technologies and methods; reconstruction of sewage systems and facilities and treatment quality improvement.

  1. Reliability analysis and computation of computer-based safety instrumentation and control used in German nuclear power plant. Final report

    International Nuclear Information System (INIS)

    Ding, Yongjian; Krause, Ulrich; Gu, Chunlei

    2014-01-01

    The trend of technological advancement in the field of safety instrumentation and control (I and C) leads to increasingly frequent use of computer-based (digital) control systems which consisting of distributed, connected bus communications computers and their functionalities are freely programmable by qualified software. The advantages of the new I and C system over the old I and C system with hard-wired technology are e.g. in the higher flexibility, cost-effective procurement of spare parts, higher hardware reliability (through higher integration density, intelligent self-monitoring mechanisms, etc.). On the other hand, skeptics see the new technology with the computer-based I and C a higher potential by influences of common cause failures (CCF), and the easier manipulation by sabotage (IT Security). In this joint research project funded by the Federal Ministry for Economical Affaires and Energy (BMWi) (2011-2014, FJZ 1501405) the Otto-von-Guericke-University Magdeburg and Magdeburg-Stendal University of Applied Sciences are therefore trying to develop suitable methods for the demonstration of the reliability of the new instrumentation and control systems with the focus on the investigation of CCF. This expertise of both houses shall be extended to this area and a scientific contribution to the sound reliability judgments of the digital safety I and C in domestic and foreign nuclear power plants. First, the state of science and technology will be worked out through the study of national and international standards in the field of functional safety of electrical and I and C systems and accompanying literature. On the basis of the existing nuclear Standards the deterministic requirements on the structure of the new digital I and C system will be determined. The possible methods of reliability modeling will be analyzed and compared. A suitable method called multi class binomial failure rate (MCFBR) which was successfully used in safety valve applications will be

  2. Development of A Standard Method for Human Reliability Analysis (HRA) of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kang, Dae Il; Jung, Won Dea; Kim, Jae Whan

    2005-12-01

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME and ANS PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME and ANS HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method

  3. Development of A Standard Method for Human Reliability Analysis of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jung, Won Dea; Kang, Dae Il; Kim, Jae Whan

    2005-12-01

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method

  4. Development of A Standard Method for Human Reliability Analysis of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Won Dea; Kang, Dae Il; Kim, Jae Whan

    2005-12-15

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method.

  5. Development of A Standard Method for Human Reliability Analysis (HRA) of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dae Il; Jung, Won Dea; Kim, Jae Whan

    2005-12-15

    According as the demand of risk-informed regulation and applications increase, the quality and reliability of a probabilistic safety assessment (PSA) has been more important. KAERI started a study to standardize the process and the rules of HRA (Human Reliability Analysis) which was known as a major contributor to the uncertainty of PSA. The study made progress as follows; assessing the level of quality of the HRAs in Korea and identifying the weaknesses of the HRAs, determining the requirements for developing a standard HRA method, developing the process and rules for quantifying human error probability. Since the risk-informed applications use the ASME and ANS PSA standard to ensure PSA quality, the standard HRA method was developed to meet the ASME and ANS HRA requirements with level of category II. The standard method was based on THERP and ASEP HRA that are widely used for conventional HRA. However, the method focuses on standardizing and specifying the analysis process, quantification rules and criteria to minimize the deviation of the analysis results caused by different analysts. Several HRA experts from different organizations in Korea participated in developing the standard method. Several case studies were interactively undertaken to verify the usability and applicability of the standard method.

  6. Nuclear power plants electrical retrofitting for cost effectiveness, reliability and operating efficiency

    International Nuclear Information System (INIS)

    Ciufu, L.; Popescu, M. O.

    2016-01-01

    In the context of continuous fast growing of the energy demand the current power plants retrofitting concept may represent an important step in the emission reduction, being able to offer in the same time a maximum operating efficiency. This desideratum can be obtained by implementing a rigorous energy management plan, based on an increased energy production capacity of non-pollutant electrical power plants and future-oriented frame on extending their lifetime operation. This management is focused on using state-of-art electronic, electrical and industrial control equipments, which can represent a real key factor. Thus, in this paper an analysis of the electrical system retrofitting is presented. As a part of this research the authors propose and simulate ambitious ways to upgrade actual control and command of the electrical operating systems, by promoting variable speed for large pumps and also computer software, as SCADA, for an intelligent control and monitoring of these studied processes. (authors)

  7. In-plant reliability data system (IPRDS) - a utility-oriented data base

    International Nuclear Information System (INIS)

    Borkowski, R.J.; Kahl, W.K.

    1983-01-01

    Currently, there are data from six operating units comprising four nuclear power plants in the data base. There are an additional seven units (4 plants) that are ready for data collection and encoding. Overall, approximately 120,000 maintenance records have been reviewed and 24,000 records of corrective maintenance actions have been extracted. The components for which data encoding has been completed include pumps and valves. The pump data base contains 1468 pumps and 3100 maintenance records on these pumps spanning almost 24 reactor-years of commercial operation. An additional 900 pump maintenance records for years prior to commercial operation have also been entered. The valve data base contains 24,825 valve population records and approximately 5800 valve maintenance records

  8. Nuclear power plant safety and reliability improvements derived from operational experience analysis

    International Nuclear Information System (INIS)

    Zebroski, E.L.; Rosen, S.L.

    1983-01-01

    The frequency and distribution of significant events at operating nuclear power plants can be used as one of several indices to obtain a preliminary indication of unit and/or utility performance in the development and implementation of improvements aimed at reducing the probability or consequences of troublesome events. Initial data of this type are presented along with qualifications on the validity of such indicators. Planned further steps to improve this as a performance indicator are noted

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

    International Nuclear Information System (INIS)

    1983-01-01

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

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  11. The effect of water quality on reliability of boiler plants performance

    Directory of Open Access Journals (Sweden)

    Gajić Anto S.

    2010-01-01

    Full Text Available This paper presents sources and types of corrosion processes of boiler tube system of the Thermal Power Plant "Ugljevik". The main goal in the electric power production is to achieve lower prices, which can only be done by providing low maintenance costs. While it is not possible to completely stop corrosion, it could be slowed down and it's effects could be reduced. In order to reduce corrosion to a minimum on thermal power plants' vital equipment, particularly boilers, it is necessary to determine in each particular case the acting mechanism of corrosion and agents that cause it. Damages and failures on thermal power plants are largely caused by the development of various types of corrosion processes. Special attention is given to the preparation of water, considering its importance to the occurrence of corrosion. The following types of corrosion were detected on the screen tube boiler by visual examination on the side of water and steam: erosive, pitting and impact corrosion. The inner surface of screen pipes, from which the scale layer was removed, indicates that the erosive corrosion with the thinning of pipe walls occurs. Perforation of the welded screen pipes shows that stress corrosion occurred on the screen pipe with formation of cracks and that pipe exploded. Pits on the inner surface of the screen pipes, visible after the removal of scale and corrosion products, are proof that pitting corrosion occurred. The causes of corrosion were discovered and proposed measures for their elimination were given.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  13. Advanced diagnostics and predictive maintenance to improve availability and reliability of ENEL plants

    Energy Technology Data Exchange (ETDEWEB)

    Cenci, V.; Ghironi, M.; Guidi, L.; Lauro, M.; Pestonesi, D. [ENEL (Italy). Generation and Energy Management Division

    2007-07-01

    This paper reviews the ENEL Generation and Energy Management strategy for diagnostics and predictive maintenance of power plants and provides a comprehensive description of effective applications and systems. Exploiting the most advanced information and communication technologies makes it possible to capture weak and hidden signals and powerful processing can be used to discover forewarning symptoms and identify anomalies both in the process and, above all, inside the devices. The following systems and applications are presented together with results and impact on plant profitability: expert system for the diagnostics of plant main machinery; advanced diagnostics of 'intelligent' fieldbus devices such as on/off valve motor-driven actuators, control-valve positioners and pneumatic actuators, transmitters; control loop and control valve diagnostics in order to investigate valve friction with an estimation of the residual time to failure; multisensorial diagnostics for coal transport and storage systems aimed at preventing firing and structural damages; and wireless sensor networks for the diagnostics of medium and small size components. 4 refs., 14 figs., 1 tab.

  14. Proposal of a concept and reliability analysis for a fusion plant magnet protection system

    International Nuclear Information System (INIS)

    Schnauder, H.; Pamfilie, E.

    1993-05-01

    The unavailability for the current switch down in case of a demand in the magnet coils of a fusion demonstration plant must be decreased by a few orders of magnitude as compared to the one of experimental facilities. The safety requirements to prevent initiation of event sequences which might lead to the release of radioactivity and energy by the plant must be fulfilled with the same standards as applied in a normally applicable plant. On the basis of this proven technology a general usable magnet protection system will be proposed, which achieves some considerable improvements in the failure detectability as compared to the conventional protection systems. It will be demonstrated by fault tree analysis that the principal demands on safety can be satisfied by that approach. The improvements are achieved by the use of an additional microprocessor supported system for failure detection without being used for initiation of any safety related actions. An influence on a safety action by the additional system therefore is excluded. (orig.) [de

  15. Semi-Markov reliability analysis of alternating systems in a nuclear power plant

    International Nuclear Information System (INIS)

    Lee, K.N.; Cho, N.Z.

    1992-01-01

    Nuclear power plant operations that follow current testing and maintenance requirements sometimes result in inadvertent reactor trips, and operating staffs devote a significant amount of time and effort in complying with these requirements. Significant benefits could result from changes in current technical specifications. In this paper the benefits and impacts of changes in allowed outage times (AOTs) and surveillance test intervals (STIs) are evaluated for an alternative system that consists of multiple trains and whose operation is alternated train by train. because of testing and AOT requirements, the alternating system exhibits semi-Markovian characteristics that change states in accordance with a Markov process but take an arbitrarily distributed amount of time between changes. The state probabilities are quantified by memorizing the necessary number of past state probabilities. Two measures of plant performance, namely, core damage probability and plant unavailability (reactor downtime), were calculated for the evaluation of AOT and STI. Results indicate that there is an optimal point that gives the lowest core damage probability and that the methodology developed in this study can be applied to existing alternating systems to evaluate accurately the various alternatives in the technical specifications

  16. Limited dissemination of the wastewater treatment plant core resistome

    OpenAIRE

    Munck, Christian; Albertsen, Mads; Telke, Amar; Ellabaan, Mostafa M Hashim; Nielsen, Per Halkjær; Sommer, Morten Otto Alexander

    2015-01-01

    Horizontal gene transfer is a major contributor to the evolution of bacterial genomes and can facilitate the dissemination of antibiotic resistance genes between environmental reservoirs and potential pathogens. Wastewater treatment plants (WWTPs) are believed to play a central role in the dissemination of antibiotic resistance genes. However, the contribution of the dominant members of the WWTP resistome to resistance in human pathogens remains poorly understood. Here we use a combination of...

  17. Health effects on nearby residents of a wood treatment plant

    International Nuclear Information System (INIS)

    Dahlgren, James; Warshaw, Raphael; Thornton, John; Anderson-Mahoney, P.M.; Takhar, Harpreet

    2003-01-01

    Objectives: The aim of the study was to evaluate the health status of nearby residents of a wood treatment plant who had sustained prolonged low-level environmental exposure to wood processing waste chemicals. Methods: A population of 1269 exposed residents who were plaintiffs or potential plaintiffs in a lawsuit against the wood treatment plant were evaluated by questionnaire for a health history and symptoms. A representative sample of 214 exposed subjects was included in the analysis. One hundred thirty-nine controls were selected from 479 unexposed volunteers and matched to the exposed subjects as closely as possible by gender and age. Subjects and controls completed additional questionnaires and were evaluated by a physician for medical history and physical examination, blood and urine testing, neurophysiological and neuropsychological studies, and respiratory testing. Environmental sampling for wood processing waste chemicals was carried out on soil and drainage ditch sediment in the exposed neighborhood. Results: The exposed subjects had significantly more cancer, respiratory, skin, and neurological health problems than the controls. The subjective responses on questionnaires and by physician histories revealed that the residents had a significantly greater prevalence of mucous membrane irritation, and skin and neurological symptoms, as well as cancer. (Exposed versus unexposed, cancer 10.0% versus 2.08%, bronchitis 17.8% versus 5.8%, and asthma by history 40.5% versus 11.0%) There were significantly more neurophysiologic abnormalities in adults of reaction time, trails A and B, and visual field defects. Conclusions: Adverse health effects were significantly more prevalent in long-term residents near a wood treatment plant than in controls. The results of this study suggest that plant emissions from wood treatment facilities should be reduced

  18. Treatment of pond sludge at the Rocky Flats Plant

    International Nuclear Information System (INIS)

    Wienand, J.; Tyler, R.; Baldwin, C.

    1992-01-01

    The treatment of low-level radioactive/hazardous materials sludges from five inactive solar evaporation settling ponds at the Rocky Flats Plant is discussed. The paper presents information on the following topics: history of the ponds; previous pond cleanout activities; current approach to the problem with respect to water management, sludge management, regulatory actions, and disposal; and future processing technology needs in the areas of polymer solidification, microwave solidification, joule-heated glass melters, and advanced technology incineration

  19. A multipurpose irradiation plant for simultaneous treatment of different foods

    International Nuclear Information System (INIS)

    Carassiti, F.; Tata, A.

    1982-01-01

    An industrial multipurpose irradiation plant with a particularly high effectiveness of radiation utilization is presented. The originality of this conceptual design consists of the simultaneous treatment of two products, which are separately irradiated to either high or low absorbed doses. A pneumatical transport system into appropriate channels with air mixing during irradiation has been proposed for the radappertization of granular animal feed, meanwhile a conventional truck-conveyor system has been suggested for the sprout inhibition treatment of potatoes. Moreover, potatoes pass through the irradiation cell twice at high and low level respectively. (author)

  20. Complete physico-chemical treatment for coke plant effluents.

    Science.gov (United States)

    Ghose, M K

    2002-03-01

    Naturally found coal is converted to coke which is suitable for metallurgical industries. Large quantities of liquid effluents produced contain a large amount of suspended solids, high COD, BOD, phenols, ammonia and other toxic substances which are causing serious pollution problem in the receiving water to which they are discharged. There are a large number of coke plants in the vicinity of Jharia Coal Field (JCF). Characteristics of the effluents have been evaluated. The present effluent treatment systems were found to be inadequate. Physico-chemical treatment has been considered as a suitable option for the treatment of coke plant effluents. Ammonia removal by synthetic zeolite, activated carbon for the removal of bacteria, viruses, refractory organics, etc. were utilized and the results are discussed. A scheme has been proposed for the complete physico-chemical treatment, which can be suitably adopted for the recycling, reuse and safe disposal of the treated effluent. Various unit process and unit operations involved in the treatment system have been discussed. The process may be useful on industrial scale at various sites.

  1. Reliability and validity of the Treatment Satisfaction Questionnaire for Medication among Portuguese-speaking Brazilian patients with hypertension.

    Science.gov (United States)

    Sauer Liberato, Ana Carolina; Cunha Matheus Rodrigues, Roberta; Kim, MyoungJin; Mallory, Caroline

    2016-07-01

    This study examined the reliability and validity of the Brazilian Portuguese version of the Treatment Satisfaction Questionnaire for Medication (version 1.4) among patients with hypertension. Understanding the patient experience with treatment satisfaction will contribute to improved medication adherence and control of hypertension. Hypertension is a serious problem in Brazil that is associated with chronic illness controlled, in part, by consistent adherence to medications. Patient satisfaction with medication treatment is associated with adherence to medication. The Treatment Satisfaction Questionnaire for Medication (version 1.4) is a promising instrument for measuring medication; however, to date there has been no report of the reliability and validity of the instrument with Portuguese-speaking adults with hypertension in Brazil. Cross-sectional descriptive exploratory study. A convenience sample of 300 patients with hypertension in an outpatient setting in the southeast region of São Paulo state in Brazil completed the Treatment Satisfaction Questionnaire for Medication (version 1.4). The instrument, comprised of four subscales, was evaluated for reliability using correlation analyses and internal consistency. Confirmatory factor analysis was used to determine factorial validity. Correlational analyses, internal consistency (Cronbach's alpha) and hierarchical confirmatory factor analysis demonstrate adequate support for the four-factor dimensionality, reliability and factorial validity of the Treatment Satisfaction Questionnaire for Medication (version 1.4). This study provides modest evidence for internal consistency and factorial validity of the Treatment Satisfaction Questionnaire for Medication (version 1.4) in Portuguese-speaking adult Brazilians with hypertension. Future testing should focus on extending reliability testing, discriminant validity and potential translation and literacy issues in this population. Within known limitations, clinicians will

  2. Membrane bio-reactor for textile wastewater treatment plant upgrading.

    Science.gov (United States)

    Lubello, C; Gori, R

    2005-01-01

    Textile industries carry out several fiber treatments using variable quantities of water, from five to forty times the fiber weight, and consequently generate large volumes of wastewater to be disposed of. Membrane Bio-reactors (MBRs) combine membrane technology with biological reactors for the treatment of wastewater: micro or ultrafiltration membranes are used for solid-liquid separation replacing the secondary settling of the traditional activated sludge system. This paper deals with the possibility of realizing a new section of one existing WWTP (activated sludge + clariflocculation + ozonation) for the treatment of treating textile wastewater to be recycled, equipped with an MBR (76 l/s as design capacity) and running in parallel with the existing one. During a 4-month experimental period, a pilot-scale MBR proved to be very effective for wastewater reclamation. On average, removal efficiency of the pilot plant (93% for COD, and over 99% for total suspended solids) was higher than the WWTP ones. Color was removed as in the WWTP. Anionic surfactants removal of pilot plant was lower than that of the WWTP (90.5 and 93.2% respectively), while the BiAS removal was higher in the pilot plant (98.2 vs. 97.1). At the end cost analysis of the proposed upgrade is reported.

  3. Study of wastewater treatment plants efficiency using radiotracers

    International Nuclear Information System (INIS)

    Dawi, W. D. A.

    2010-11-01

    This study was performed to investigate and diagnose hydrodynamic behavior of the Military Hospital wastewater treatment plant. The plant comprises two units of treatment, each of them has a separate system. The investigation was carried out using ''1''3''1I as a radiotracer. The concept of residence time distribution (RTD) was used to investigate the efficiency of the aeration tanks, secondary clarifiers and chlorine tanks. Preliminary treatment and modeling of the trace data was performed using two software package applied by the International Atomic Energy Agency (IAEA) namely 4621 counter version 1.0.0 and RTD software. Plug flow pattern (parallel flow) was detected in the aeration tank and secondary clarifier of system 1 in one unit, while no homogeneous mixing was observed in the chlorine tank. Short - circuiting (by - passing) was evident in the aeration tank of system 2 in the other unit, which significantly reduced the operating efficiency. The percentage of dead volumes clearly suggests that the aeration tank and secondary clarifier were well utilized in the whole plant. (Author)

  4. Microbial contamination of the air at the wastewater treatment plant

    Directory of Open Access Journals (Sweden)

    Monika Vítězová

    2012-01-01

    Full Text Available Wastewater treatment plants (WWTPs primarily serve to protect the environment. Their task is to clean waste water from the agglomerations. On the other hand wastewater treatment plants can also negatively affect the environment in their neighbourhood. These include emissions of odour and microorganisms. This article discusses the microbial contamination of the air, called bioaerosols in selected wastewater treatment plant for 18 000 p.e. From results of the work is evident that the largest group of microorganisms in the monitored air were psychrophilic and mesophilic bacteria and microscopic fungi. The number of psychrophilic bacteria ranged from 14 to 12 000 CFU/m3 (colony forming units in 1 m3, the number of mesophilic bacteria varied in the range from 20 to 18 500 CFU/m3 and the fungi from 25 to 32 000 CFU/m3 in the air. The amount of actinomycetes ranged from 1 to 1 030 CFU/m3 and faecal coliform bacteria from 0 to 2 500 CFU/m3. Furthermore, it was confirmed that the highest air contamination was around the activation tank, area for dewatered sludge and around the building of mechanical cleaning, depending on the season. The density of studied microorganisms correlated with air temperature.

  5. Technologies for improving the availability and reliability of current and future water cooled nuclear power plants. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    One of the activities of the IAEA is to provide all Member States with an international source of balanced, objective information on advanced in technology for water cooled reactors. Since the global nuclear industry has a common interest in improving plant availability and reliability to assure specific individual plant and country perspective as well as to have an image of well managed competitive industry, the IAEA held a Technical Committee Meeting on Technologies for Improving the Availability and Reliability of Current and Future Water Cooled Nuclear Power Plants in September 1997. The basic aim to was to identify, review and exchange information on international developments in technologies for achieving high availability and reliability and to suggest areas where further technical advances could contribute to improvement of performance. Designs for future plants were presented in the context of how they can accommodate both the organizational and technical means for reaching even higher levels of performance. This proceedings contains the contributed papers presented at this Meeting each with a separate abstract. Four sessions were concerned with: policies, practices and procedures for achieving high reliability and availability; improving availability and reliability through better use of today`s technologies; recent advances in technologies for improving availability and reliability; achieving high availability for new plants Refs, figs, tabs

  6. Technologies for improving the availability and reliability of current and future water cooled nuclear power plants. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-11-01

    One of the activities of the IAEA is to provide all Member States with an international source of balanced, objective information on advanced in technology for water cooled reactors. Since the global nuclear industry has a common interest in improving plant availability and reliability to assure specific individual plant and country perspective as well as to have an image of well managed competitive industry, the IAEA held a Technical Committee Meeting on Technologies for Improving the Availability and Reliability of Current and Future Water Cooled Nuclear Power Plants in September 1997. The basic aim to was to identify, review and exchange information on international developments in technologies for achieving high availability and reliability and to suggest areas where further technical advances could contribute to improvement of performance. Designs for future plants were presented in the context of how they can accommodate both the organizational and technical means for reaching even higher levels of performance. This proceedings contains the contributed papers presented at this Meeting each with a separate abstract. Four sessions were concerned with: policies, practices and procedures for achieving high reliability and availability; improving availability and reliability through better use of today's technologies; recent advances in technologies for improving availability and reliability; achieving high availability for new plants

  7. The obscure factor analysis on the vibration reliability of the internals of nuclear power plant reactor and anti-vibration measures

    International Nuclear Information System (INIS)

    Fu Geyan; Zhu Qirong

    1998-11-01

    It is pointed out that the main reason making nuclear power plants reactors leak is the vibration of internals of reactors. The factors which lead the vibration all have randomness and obscureness. The obscure reliability theory is introduced to the vibration system of internals of nuclear power reactor. Based on a quantity of designing and moving data, the obscure factors effecting the vibration reliability of the internals of nuclear power plant reactor are analyzed and the anti-vibration reliability criteria and the evaluating model are given. And the anti-vibration reliability measures are advanced from different quarters of the machine design and building, the thermohydraulics design, the control of reactivity, etc.. They may benefit the theory and practice for building and perfecting the vibration obscure reliability model of the reactor internals

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-08-01

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

  9. Hydraulic reliability of a horizontal wetland for wastewater treatment in Sicily.

    Science.gov (United States)

    Marzo, A; Ventura, D; Cirelli, G L; Aiello, R; Vanella, D; Rapisarda, R; Barbagallo, S; Consoli, S

    2018-09-15

    The purpose of this study was to evaluate how the hydraulic behavior of a horizontal subsurface wetland (HF), that is part of the hybrid wetland (hybrid-TW) of the IKEA® store in Eastern Sicily (Italy), influences the overall wastewater treatment performance. The HF unit experiences frequent overloading peaks due to the extreme variability in the number of visitors at the store, and after 2 years of operation it showed signals of partial clogging at the inlet area. The hydraulics of the HF unit has been monitored through measurements of hydraulic conductivity at saturation (Ks), tracer tests, and geophysical (i.e. electrical resistivity tomography-ERT) measurements carried out during the years 2016 and 2017. Results indicated a general good agreement between the performed measurement techniques, thus their combination, if adequately performed and calibrated, might be a reliable tool for detecting those wetland areas mainly affected by clogging conditions. The results also indicated that partial clogging had no significant effect on the quality of the discharged water. Copyright © 2018 Elsevier B.V. All rights reserved.

  10. Research on the sewage treatment in high altitude region based on Lhasa Sewage Treatment Plant

    Science.gov (United States)

    Xu, Jin; Li, Shuwen

    2017-12-01

    Sewage treatment is of great significance to enhance environmental quality, consolidate pollution prevention and ecological protection, and ensure sustainable economic and social development in high altitude region. However, there are numerous difficulties in sewage treatment due to the alpine climate, the relatively low economic development level, and the backward operation and management styles, etc. In this study, the characteristics of influent quality in the sewage treatment plant in Lhasa are investigated by analysing the influent BOD5/COD and BOD5/TN, comparing key indexes recorded from 2014 to 2016 with the hinterland. Results show that the concentration of influent COD, BOD5, NH3-N and SS in the Lhasa sewage treatment plant, in which the sewage belongs to low-concentration urban sewage, is smaller than that in the domestic sewage treatment plants in the mainland. The concentration ratio of BOD5/COD and BOD5/TN is below 0.4 and 4, which indicates that the biodegradation is poor and the carbon sources are in bad demand. The consequences obtained play a vital role in the design, operation and management of sewage treatment plants in high altitude region.

  11. Validation study on reliability analysis of main safety system in Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Nam Jin; Cho, Chang Keun; Kim, Yong Hui; Kim, Tae Hyeong; Hong, Seo Kee; Park, Keon Woo; Park, Chang Jea [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Cheong, Woo Sik [Institute for Advanced Engineering, Yongin (Korea, Republic of); Park, Moon Kyu [KEPRI, Taejon (Korea, Republic of)

    1993-12-15

    The scope and contents of this validation study are to review the design changes of the four main safety systems in Wolsong 2/3/4 Nuclear Power Plants, to review the consideration of the above design changes in the AECL reports, the structure of fault trees, and the data base used in the quantification of the fault trees, to quantify the unavailabilities of main safety systems and check them if they meet the requirements, and to recommend desirable design changes in the emergency core cooling system to reduce the unavailability.

  12. Cost-effective and reliable design of a solar thermal power plant

    International Nuclear Information System (INIS)

    Aliabadi, A.A.; Wallace, J.S.

    2009-01-01

    A design study was conducted to evaluate the cost-effectiveness of solar thermal power generation in a 50 kWe power plant that could be used in a remote location. The system combines a solar collector-thermal storage system utilizing a heat transfer fluid and a simple Rankine cycle power generator utilizing R123 refrigerant. Evacuated tube solar collectors heat mineral oil and supply it to a thermal storage tank. A mineral oil to refrigerant heat exchanger generates superheated refrigerant vapor, which drives a radial turbogenerator. Supplemental natural gas firing maintains a constant thermal storage temperature irregardless of solar conditions enabling the system to produce a constant 50 kWe output. A simulation was carried out to predict the performance of the system in the hottest summer day and the coldest winter day for southern California solar conditions. A rigorous economic analysis was conducted. The system offers advantages over advanced solar thermal power plants by implementing simple fixed evacuated tube collectors, which are less prone to damage in harsh desert environment. Also, backed up by fossil fuel power generation, it is possible to obtain continued operation even during low insolation sky conditions and at night, a feature that stand-alone PV systems do not offer. (author)

  13. Development of an improved compact package plant for small community waste-water treatment

    CSIR Research Space (South Africa)

    Hulsman, A

    1993-01-01

    Full Text Available The challenges facing the design and operation of small community wastewater treatment plants are discussed. The package plant concept is considered and the consequent development of a compact intermittently aerated activated sludge package plant...

  14. Sludge Reduction by Lumbriculus Variegatus in Ahvaz Wastewater Treatment Plant

    Directory of Open Access Journals (Sweden)

    Tim Hendrickx

    2012-08-01

    Full Text Available Sludge production is an avoidable problem arising from the treatment of wastewater. The sludge remained after municipal wastewater treatment contains considerable amounts of various contaminants and if is not properly handled and disposed, it may produce extensivehealth hazards. Application of aquatic worm is an approach to decrease the amount of biological waste sludge produced in wastewater treatment plants. In the present research reduction of the amount of waste sludge from Ahvaz wastewater treatment plant was studied with the aquatic worm Lumbriculus variegatus in a reactor concept. The sludge reduction in the reactor with worm was compared to sludge reduction in a blank reactor (without worm.The effects of changes in dissolved oxygen (DO concentration up to 3 mg/L (run 1 and up to 6 mg/L (run 2 were studied in the worm and blank reactors. No meaningful relationship was found between DO concentration and the rate of total suspended solids reduction. Theaverage sludge reductions were obtained as 33% (run 2 and 32% (run 1 in worm reactor,and 16% (run 1 and 12% (run 2 in the blank reactor. These results showed that the worm reactors may reduce the waste sludge between 2 and 2.75 times higher than in the blankconditions. The obtained results showed that the worm reactor has a high potential for use in large-scale sludge processing.

  15. Innovative waste treatment and conditioning technologies at nuclear power plants

    International Nuclear Information System (INIS)

    2006-05-01

    The objective of this publication is to provide Member States with information on the most innovative technologies and strategies used in waste treatment and conditioning. At present, some of those technologies and strategies might not be widely implemented at nuclear power plants (NPP), but they have an important potential for their use as part of the long range NPP, utility, or national strategy. Thus, the target audience is those decision makers at the national and organizational level responsible for selecting waste processing technologies and strategies over a period of three to ten years. Countries and individual nuclear plants have limited financial resources which can be applied toward radioactive waste processing (treatment and conditioning). They are challenged to determine which of the many available technologies and strategies are best suited to meet national or local needs. This publication reduces the selection of processes for wastes generated by nuclear power plants to those technologies and strategies which are considered innovative. The report further identifies the key benefits which may derive from the adoption of those technologies, the different waste streams to which each technology is relevant, and the limitations of the technologies. The technologies and strategies identified have been evaluated to differentiate between (1) predominant technologies (those that are widely practiced in multiple countries or a large number of nuclear plants), and (2) innovative technologies (those which are not so widely used but are considered to offer benefits which make them suitable for broader application across the industry). Those which fall into the second category are the primary focus of this report. Many IAEA publications address the technical aspects of treatment and conditioning for radioactive wastes, covering research, technological advances, and safety issues. These studies and reports primarily target the research and technical staff of a

  16. Structured information analysis for human reliability analysis of emergency tasks in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Won Dea; Kim, Jae Whan; Park, Jin Kyun; Ha, Jae Joo [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-02-01

    More than twenty HRA (Human Reliability Analysis) methodologies have been developed and used for the safety analysis in nuclear field during the past two decades. However, no methodology appears to have universally been accepted, as various limitations have been raised for more widely used ones. One of the most important limitations of conventional HRA is insufficient analysis of the task structure and problem space. To resolve this problem, we suggest SIA (Structured Information Analysis) for HRA. The proposed SIA consists of three parts. The first part is the scenario analysis that investigates the contextual information related to the given task on the basis of selected scenarios. The second is the goals-means analysis to define the relations between the cognitive goal and task steps. The third is the cognitive function analysis module that identifies the cognitive patterns and information flows involved in the task. Through the three-part analysis, systematic investigation is made possible from the macroscopic information on the tasks to the microscopic information on the specific cognitive processes. It is expected that analysts can attain a structured set of information that helps to predict the types and possibility of human error in the given task. 48 refs., 12 figs., 11 tabs. (Author)

  17. Task analysis and computer aid development for human reliability analysis in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, W. C.; Kim, H.; Park, H. S.; Choi, H. H.; Moon, J. M.; Heo, J. Y.; Ham, D. H.; Lee, K. K.; Han, B. T. [Korea Advanced Institute of Science and Technology, Taejeon (Korea)

    2001-04-01

    Importance of human reliability analysis (HRA) that predicts the error's occurrence possibility in a quantitative and qualitative manners is gradually increased by human errors' effects on the system's safety. HRA needs a task analysis as a virtue step, but extant task analysis techniques have the problem that a collection of information about the situation, which the human error occurs, depends entirely on HRA analyzers. The problem makes results of the task analysis inconsistent and unreliable. To complement such problem, KAERI developed the structural information analysis (SIA) that helps to analyze task's structure and situations systematically. In this study, the SIA method was evaluated by HRA experts, and a prototype computerized supporting system named CASIA (Computer Aid for SIA) was developed for the purpose of supporting to perform HRA using the SIA method. Additionally, through applying the SIA method to emergency operating procedures, we derived generic task types used in emergency and accumulated the analysis results in the database of the CASIA. The CASIA is expected to help HRA analyzers perform the analysis more easily and consistently. If more analyses will be performed and more data will be accumulated to the CASIA's database, HRA analyzers can share freely and spread smoothly his or her analysis experiences, and there by the quality of the HRA analysis will be improved. 35 refs., 38 figs., 25 tabs. (Author)

  18. Improving human reliability through better nuclear power plant system design. Final report

    International Nuclear Information System (INIS)

    Golay, Michael W.

    1998-01-01

    Increasing task complexity is claimed to be responsible for causing human operating errors, while a significant number of system failures are due to operating errors. An experimental study reported here was conducted to isolate varying task complexity as an important factor affecting human performance quality. Earlier work concerning problems of nuclear power plants has shown that human capability declined when dealing with increasing system complexity. The goal of this study was to investigate further the relationship between human operator performance quality and the complexity of tasks served to human operators. This was done by using a simple, interactive, dynamic and generalizable computer model to simulate the behavior of a human-operated dynamic fluid system. Twenty-two human subjects participated

  19. Summary of project to develop handbook of human reliability analysis for nuclear power plant operations

    International Nuclear Information System (INIS)

    Swain, A.D.

    1978-01-01

    For the past two years Alan Swain and Henry E. Guttmann, of the Statistics, Computing, and Human Factors Division, Sandia Laboratories, have been developing a handbook to aid qualified persons to evaluate the effect of human error on the availability of engineered safety systems and features in nuclear power plants. The handbook includes a mathematical model, procedures, derived human failure data, and principles of human behavior and ergonomics. The handbook is expanding the human error analyses which were presented in WASH--1400. The work, under the sponsorship of Probabilistic Analysis Staff, NRC Office of Nuclear Regulatory Research (Dr. M.C. Cullingford, NRC Program Manager), is about half completed. An outline of the handbook contents is given in copies of vugraphs (attached), followed by copies of human performance model abstractors (also attached). A first draft of the handbook is scheduled for NRC review by July 1, 1979

  20. Equipment reliability and life cycle optimization of a nuclear plant feedwater heater

    International Nuclear Information System (INIS)

    Thomas, Daniel; Coakley, Michael; Catapano, Michael; Svensson, Eric

    2006-01-01

    Many papers published over the last 25 years have strongly emphasized the need for an ongoing program of inspection and testing with subsequent failure cause analysis of feedwater heaters. Plants must be run more competitively; therefore, Utilities must lower operation and maintenance costs, while optimizing overall plant efficiency and capacity factor. One recognized area that needs to be addressed in accomplishing this goal is the heat cycle. This paper specifically deals with the feedwater heating system. Utility engineers must monitor feedwater heater performance in order to recognize degradation, identify and mitigate failure mechanisms, and prevent in-service failures thereby optimizing availability. Periodic tube plugging without complete analysis of the degraded/failed areas resolves the immediate need for return to service; however, heater life will not be optimized. This paper illustrates a complete life cycle management inspection, testing, and maintenance program implemented at Peach Bottom Atomic Power Station (PBAPS). Concerns that tubes may have been too conservatively plugged due to insufficient data and lack of root cause analysis, justified a program that included: - Removal of previously installed plugs; - Video-probe inspection of failed areas; - Extraction of tube samples for further analysis; - Eddy current testing of selected tubes; - Evaluation of the condition of 'insurance' plugged tubes for return to service; - Hydrostatic testing of selected individual tubes; - Final repair plan based on the results of the above program. This paper concludes that no single method of inspection or testing should solely be relied upon in establishing: - The extent of actual degraded conditions; - The mechanism(s) of failure; - The details of repair to be implemented. Evaluating all data affords the best chance in arresting problems and optimizing feedwater heater life. Problem heaters should be continuously monitored and inspected over time until the facts

  1. Job analysis of maintenance-mechanic position for the nuclear power plant maintenance personnel reliability model

    International Nuclear Information System (INIS)

    Siegel, A.I.; Bartter, W.D.; Kopstein, F.F.

    1982-06-01

    The task list method of job survey was used. In collaboration with BWR and PWR personnel, a list of 107 tasks performed by maintenance mechanics was developed, grouped into: remove and install, test and repair, inspect and perform preventive maintenance, miscellaneous, communication, and report preparation. For each listed task, the questionnaire form inquired into: frequency of performance, task completion time, safety consequences of improper performance, and the amount of training required to perform the task proficiently. Scaled information was requested about seven abilities: (1) visual speed, accuracy, and recognition; (2) gross motor coordination; (3) fine manual dexterity; (4) strength and stamina; (5) cognition; (6) memory; and (7) problem solving required for function completion. Survey forms were distributed to 27 nuclear power plants. Thirty-one maintenance mechanics representing 17 plants returned the completed forms. Frequency of performing tasks was bimodally distributed: (1) between once a year and once every six months, and (2) about once a week. More than half of the tasks have potential risk consequences if improperly performed. The five tasks with the greatest risk implications in the case of inadequate performance were: (1) remove and install reactor and dry-well heads, (2) test and repair reactor system components, (3) remove and install pressurizer mechanical relief valves, (4) test and repair pressurizer relief valves, (5) remove and install core spray pumps, seals, and valves. Hierarchically, the public risk associated with the various functions was: (1) remove and install, (2) test and repair, (3) preventive maintenance, (4) miscellaneous tasks, (5) communication, and (6) report preparation

  2. Raffinate treatment at the Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Acox, T.A.

    1983-01-01

    Raffinate solutions, which contain uranium, technetium, nitrates, and lesser amounts of heavy metals, are produced in the decontamination and uranium recovery operations at the Portsmouth Gaseous Diffusion Plant. These solutions are presently being placed in temporary storage until three treatment facilities are constructed which will produce an environmentally acceptable effluent from the raffinate. These facilities are: (1) The Heavy Metals Precipitation Facility; (2) The Technetium Ion Exchange Facility; and (3) The Biodenitrification Pilot Plant. When the facilities are completed, the raffinate will be treated in 500 gallon batches. The first treatment is the heavy metals precipitation by caustic addition and filtering. The effluent proceeds to the ion exchange columns where the technetium is removed by adsorption onto a strongly basic, anion exchange resin which has been converted to the hydroxyl form. Following ion exchange, the solution is transported to the biodenitrification pilot plant. The biodenitrification column is a fluidized-bed using bacteria-laden coal particles as the denitrifying media. The resulting effluent should meet the limits established by the US EPA for all metals and nitrate. Technetium will be 98+% removed and the uranium concentration will be less than one milligram per liter. 13 references

  3. Perfluoroalkyl substances (PFASs) in wastewater treatment plants and drinking water treatment plants: Removal efficiency and exposure risk.

    Science.gov (United States)

    Pan, Chang-Gui; Liu, You-Sheng; Ying, Guang-Guo

    2016-12-01

    Perfluoroalkyl substances (PFASs) are a group of chemicals with wide industrial and commercial applications, and have been received great attentions due to their persistence in the environment. The information about their presence in urban water cycle is still limited. This study aimed to investigate the occurrence and removal efficiency of eighteen PFASs in wastewater treatment plants (WWTPs) and drinking water plants (DWTPs) with different treatment processes. The results showed that both perfluorobutane sulfonic acid (PFBS) and perfluorooctane sulfonic acid (PFOS) were the predominant compounds in the water phase of WWTPs and DWTPs, while PFOS was dominant in dewatered sludge of WWTPs. The average total PFASs concentrations in the three selected WWTPs were 19.6-232 ng/L in influents, 15.5-234 ng/L in effluents, and 31.5-49.1 ng/g dry weight in sludge. The distribution pattern of PFASs differed between the wastewater and sludge samples, indicating strong partition of PFASs with long carbon chains to sludge. In the WWTPs, most PFASs were not eliminated efficiently in conventional activated sludge treatment, while the membrane bio-reactor (MBR) and Unitank removed approximately 50% of long chain (C ≥ 8) perfluorocarboxylic acids (PFCAs). The daily mass loads of total PFASs in WWTPs were in the range of 1956-24773 mg in influent and 1548-25085 mg in effluent. PFASs were found at higher concentrations in the wastewater from plant A with some industrial wastewater input than from the other two plants (plant B and plant C) with mainly domestic wastewater sources. Meanwhile, the average total PFASs concentrations in the two selected DWTPs were detected at 4.74-14.3 ng/L in the influent and 3.34-13.9 ng/L in the effluent. In DWTPs, only granular activated carbon (GAC) and powder activated carbon (PAC) showed significant removal of PFASs. The PFASs detected in the tap water would not pose immediate health risks in the short term exposure. The findings from this

  4. Reliability calculations

    International Nuclear Information System (INIS)

    Petersen, K.E.

    1986-03-01

    Risk and reliability analysis is increasingly being used in evaluations of plant safety and plant reliability. The analysis can be performed either during the design process or during the operation time, with the purpose to improve the safety or the reliability. Due to plant complexity and safety and availability requirements, sophisticated tools, which are flexible and efficient, are needed. Such tools have been developed in the last 20 years and they have to be continuously refined to meet the growing requirements. Two different areas of application were analysed. In structural reliability probabilistic approaches have been introduced in some cases for the calculation of the reliability of structures or components. A new computer program has been developed based upon numerical integration in several variables. In systems reliability Monte Carlo simulation programs are used especially in analysis of very complex systems. In order to increase the applicability of the programs variance reduction techniques can be applied to speed up the calculation process. Variance reduction techniques have been studied and procedures for implementation of importance sampling are suggested. (author)

  5. B Plant treatment, storage, and disposal (TSD) units inspection plan

    International Nuclear Information System (INIS)

    Beam, T.G.

    1996-01-01

    This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ''Dangerous Waste Regulations'' (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements

  6. Optimization of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plant (FUWAC)

    International Nuclear Information System (INIS)

    2011-10-01

    This report presents the results of the Coordinated Research Project (CRP) on Optimization of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plants (FUWAC, 2006-2009). It provides an overview of the results of the investigations into the current state of water chemistry practice and concerns in the primary circuit of water cooled power reactors including: corrosion of primary circuit materials; deposit composition and thickness on the fuel; crud induced power shift; fuel oxide growth and thickness; radioactivity buildup in the reactor coolant system (RCS). The FUWAC CRP is a follow-up to the DAWAC CRP (Data Processing Technologies and Diagnostics for Water Chemistry and Corrosion Control in Nuclear Power Plants 2001-2005). The DAWAC project improved the data processing technologies and diagnostics for water chemistry and corrosion control in nuclear power plants (NPPs). With the improved methods for controlling and monitoring water chemistry now available, it was felt that a review of the principles of water chemistry management should be undertaken in the light of new materials, more onerous operating conditions, emergent issues such as CIPS, also known as axial offset anomaly (AOA) and the ageing of operating power plant. In the framework of this CRP, water chemistry specialists from 16 nuclear utilities and research organizations, representing 15 countries, exchanged experimental and operational data, models and insights into water chemistry management. The CD-ROM attached to this IAEA-TECDOC includes the report itself, detailed progress reports of three Research Coordination Meetings (RCMs) (Annexes I-III) and the reports and presentations made during the project by the participants.

  7. Seabrook, N.H. Wastewater Treatment Plant Chief Operator Recognized for Outstanding Service

    Science.gov (United States)

    Dustin Price, a resident of Berwick Maine and the Chief Operator of the Seabrook, N.H. Wastewater Treatment Plant, was honored by EPA with a 2016 Regional Wastewater Treatment Plant Operator of the Year Excellence Award.

  8. On the application of nonhomogeneous Poisson process to the reliability analysis of service water pumps of nuclear power plants

    International Nuclear Information System (INIS)

    Cruz Saldanha, Pedro Luiz da.

    1995-12-01

    The purpose of this study is to evaluate the nonhomogeneous Poisson process as a model to rate of occurrence of failures when it is not constant, and the times between failures are not independent nor identically distributed. To this evaluation, an analyse of reliability of service water pumps of a typical nuclear power plant is made considering the model discussed in the last paragraph, as long as the pumps are effectively repairable components. Standard statistical techniques, such as maximum likelihood and linear regression, are applied to estimate parameters of nonhomogeneous Poisson process model. As a conclusion of the study, the nonhomogeneous Poisson process is adequate to model rate of occurrence of failures that are function of time, and can be used where the aging mechanisms are present in operation of repairable systems. (author). 72 refs., 45 figs., 21 tabs

  9. Feasibility study for adding a demand failure data collection system to the Nuclear Plant Reliability Data System. Final report

    International Nuclear Information System (INIS)

    Tashjian, B.M.; Logan, B.W.

    1983-07-01

    Southwest Research Institute (SwRI) is pleased to submit to Sandia National Laboratories this technical report as fulfillment of Task 5 of the proposal entitled A Feasibility Study for Adding a Duty Cycle Data Collection System to the Nuclear Plant Reliability Data System. The purpose of this report is to summarize the work as delineated in the proposal tasks and to recommend follow-on activities. Technical support for this work was provided by Duke Power Company (Duke), subcontractor to SwRI. The four tasks to be performed in conjunction with the Duty Cycle Data Collection Study (renamed in this report Demand Data Collection) were: define component population and measurable parameters; develop data collection and assessment methodologies; assess the impact on utilities; and assess the impact on NPRDS

  10. The nuclear power plant maintenance personnel reliability prediction (NPP/MPRP) effort at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Knee, H.E.; Haas, P.M.; Siegel, A.I.

    1982-01-01

    Human errors committed during maintenance activities are potentially a major contribution to the overall risk associated with the operation of a nuclear power plant (NPP). An NRC-sponsored program at Oak Ridge National Laboratory is attempting to develop a quantitative predictive technique to evaluate the contribution of maintenance errors to the overall NPP risk. The current work includes a survey of the requirements of potential users to ascertain the need for and content of the proposed quantitative model, plus an initial job/task analysis to determine the scope and applicability of various maintenance tasks. In addition, existing human reliability prediction models are being reviewed and assessed with respect to their applicability to NPP maintenance tasks. This paper discusses the status of the program and summarizes the results to date

  11. Process waste treatment system upgrades: Clarifier startup at the nonradiological wastewater treatment plant

    International Nuclear Information System (INIS)

    Lucero, A.J.; McTaggart, D.R.; Van Essen, D.C.; Kent, T.E.; West, G.D.; Taylor, P.A.

    1998-07-01

    The Waste Management Operations Division at Oak Ridge National Laboratory recently modified the design of a reactor/clarifier at the Nonradiological Wastewater Treatment Plant, which is now referred to as the Process Waste Treatment Complex--Building 3608, to replace the sludge-blanket softener/clarifier at the Process Waste Treatment Plant, now referred to as the Process Waste Treatment Complex-Building 3544 (PWTC-3544). This work was conducted because periodic hydraulic overloads caused poor water-softening performance in the PWTC-3544 softener, which was detrimental to the performance and operating costs of downstream ion-exchange operations. Over a 2-month time frame, the modified reactor/clarifier was tested with nonradiological wastewater and then with radioactive wastewater to optimize softening performance. Based on performance to date, the new system has operated more effectively than the former one, with reduced employee radiological exposure, less downtime, lower costs, and improved effluent quality

  12. Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde; Implementacion del proyecto de confiabilidad de equipo en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rios O, J. E.; Martinez L, A. G. [CFE, Central Laguna Verde, Subgerencia General de Operacion, Veracruz (Mexico)]. e-mail: jrios@cfe.gob.mx

    2008-07-01

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

  13. Treatment Of Wastewater For Reuse With Mobile Electron Beam Plant

    International Nuclear Information System (INIS)

    Han, B.; Kim, J.K.; Kim, Y.R.; Zommer, N.

    2012-01-01

    The use of alternative disinfectants to chlorine for the wastewater treatment has received increasing attention in recent years to treat either liquid or solids streams within wastewater treatment plants for pathogens and trace organics (TOrCs). Although several technologies have come to the forefront as an alternative to chlorine (e.g., ultraviolet [UV] and hydrogen peroxide), the majority of these technologies are chemically based, with the exception of UV. An attractive physical disinfection approach is by electron beam (EB) irradiation. EB treatment of wastewater leads to their purification from various pollutants. It is caused by the decomposition of pollutants as a result of their reactions with highly reactive species formed from water radiolysis: hydrated electron, OH free radical and H atom [Pikaev (1986)]. Sometimes methods such as EB with biological treatment, adsorption and others improve the effect of EB treatment of the wastewater purification. In the process of EB treatment of wastewater there are utilized chemical transformations of pollutants induced by ionizing radiation. At sufficiently high absorbed doses these transformations can result in complete decomposition (removal) of the substance. Under real conditions, i.e., at rather high content of pollutants in a wastewater and economically acceptable doses, partial decomposition of pollutant takes place as well as transformations of pollutant molecules that result in improving subsequent purification stages, efficiency of the process being notably influenced by irradiation conditions and wastewater composition [Woods and Pikaev (1994)]. (author)

  14. Treatment Of Wastewater For Reuse With Mobile Electron Beam Plant

    Energy Technology Data Exchange (ETDEWEB)

    Han, B.; Kim, J. K.; Kim, Y. R. [EB TECH Co., Ltd., Daejeon (Korea, Republic of); Zommer, N. [Pele Inc., Milpitas Californaa (United States)

    2012-07-01

    The use of alternative disinfectants to chlorine for the wastewater treatment has received increasing attention in recent years to treat either liquid or solids streams within wastewater treatment plants for pathogens and trace organics (TOrCs). Although several technologies have come to the forefront as an alternative to chlorine (e.g., ultraviolet [UV] and hydrogen peroxide), the majority of these technologies are chemically based, with the exception of UV. An attractive physical disinfection approach is by electron beam (EB) irradiation. EB treatment of wastewater leads to their purification from various pollutants. It is caused by the decomposition of pollutants as a result of their reactions with highly reactive species formed from water radiolysis: hydrated electron, OH free radical and H atom [Pikaev (1986)]. Sometimes methods such as EB with biological treatment, adsorption and others improve the effect of EB treatment of the wastewater purification. In the process of EB treatment of wastewater there are utilized chemical transformations of pollutants induced by ionizing radiation. At sufficiently high absorbed doses these transformations can result in complete decomposition (removal) of the substance. Under real conditions, i.e., at rather high content of pollutants in a wastewater and economically acceptable doses, partial decomposition of pollutant takes place as well as transformations of pollutant molecules that result in improving subsequent purification stages, efficiency of the process being notably influenced by irradiation conditions and wastewater composition [Woods and Pikaev (1994)]. (author)

  15. [Fasciocutaneous flap reliable by deep femoral artery perforator for the treatment of ischial pressure ulcers].

    Science.gov (United States)

    Gebert, L; Boucher, F; Lari, A; Braye, F; Mojallal, A; Ismaïl, M

    2018-04-01

    The surgical management of pressure ulcers in the paraplegic or quadriplegic population is marked by the high risk of recurrence in the long-term. In the current era of perforator flaps, newer reconstructive options are available for the management of pressure ulcers, decreasing the need to use the classically described muscular or musculocutaneous locoregional flaps. The coverage of ischial sores described in this article by a pedicled flap based on a deep femoral artery perforator, appears to be an effective first-line reconstructive option for the management of limited size pressure ulcers. A number of fifteen paraplegic or quadriplegic patients having at least one ischial bed sore with underlying osteomyelitis were included in this series. The approximate location of the deep femoral artery perforator was initially identified using the "The Atlas of the perforator arteries of the skin, the trunk and limbs", which was confirmed, with the use of a Doppler device. A fasciocutaneous transposition flap was elevated, with the pivot point based on the cutaneous bridge centered on the perforator, and then transposed to cover the area of tissue loss. The donor site was closed primarily. A total of fifteen patients were operated from November 2015 to November 2016. The series comprised of 16 first presentations of a stage 4 pressure ulcers associated with underlying osteomyelitis that were subsequently reconstructed by the pedicled deep femoral artery perforator flap. The healing rate and functional results were both satisfactory. Fasciocutaneous flap reliable by deep femoral artery perforator appears to have a promising role in the treatment of ischial pressure sores. It is an attractive option to spare the use of musculocutaneous flaps in the area. Thus this flap could be used as a first-line option to cover ischial pressure ulcers of limited size. Copyright © 2017 Elsevier Masson SAS. All rights reserved.

  16. Hybrid instrument applied to human reliability study in event of loss of external electric power in a nuclear power plant

    International Nuclear Information System (INIS)

    Martins, Eduardo Ferraz

    2015-01-01

    The study projects in highly complex installations involves robust modeling, supported by conceptual and mathematical tools, to carry out systematic research and structured the different risk scenarios that can lead to unwanted events from occurring equipment failures or human errors. In the context of classical modeling, the Probabilistic Safety Analysis (PSA) seeks to provide qualitative and quantitative information about the project particularity and their operational facilities, including the identification of factors or scenarios that contribute to the risk and consequent comparison options for increasing safety. In this context, the aim of the thesis is to develop a hybrid instrument (CPP-HI) innovative, from the integrated modeling techniques of Failure Mode and Effect Analysis (FMEA), concepts of Human Reliability Analysis and Probabilistic Composition of Preferences (PCP). In support of modeling and validation of the CPP-HI, a simulation was performed on a triggering event 'Loss of External Electric Power' - PEEE, in a Nuclear Power plant. The results were simulated in a virtual environment (sensitivity analysis) and are robust to the study of Human Reliability Analysis (HRA) in the context of the PSA. (author)

  17. Optimal design methods for a digital human-computer interface based on human reliability in a nuclear power plant

    International Nuclear Information System (INIS)

    Jiang, Jianjun; Zhang, Li; Xie, Tian; Wu, Daqing; Li, Min; Wang, Yiqun; Peng, Yuyuan; Peng, Jie; Zhang, Mengjia; Li, Peiyao; Ma, Congmin; Wu, Xing

    2017-01-01

    Highlights: • A complete optimization process is established for digital human-computer interfaces of Npps. • A quick convergence search method is proposed. • The authors propose an affinity error probability mapping function to test human reliability. - Abstract: This is the second in a series of papers describing the optimal design method for a digital human-computer interface of nuclear power plant (Npp) from three different points based on human reliability. The purpose of this series is to explore different optimization methods from varying perspectives. This present paper mainly discusses the optimal design method for quantity of components of the same factor. In monitoring process, quantity of components has brought heavy burden to operators, thus, human errors are easily triggered. To solve the problem, the authors propose an optimization process, a quick convergence search method and an affinity error probability mapping function. Two balanceable parameter values of the affinity error probability function are obtained by experiments. The experimental results show that the affinity error probability mapping function about human-computer interface has very good sensitivity and stability, and that quick convergence search method for fuzzy segments divided by component quantity has better performance than general algorithm.

  18. Effectiveness of different pre-treatments in recovering pre-burial isotopic ratios of charred plants.

    Science.gov (United States)

    Brinkkemper, O; Braadbaart, F; van Os, B; van Hoesel, A; van Brussel, A A N; Fernandes, R

    2018-02-15

    Isotopic analysis of archaeological charred plant remains offers useful archaeological information. However, adequate sample pre-treatment protocols may be necessary to provide a contamination-free isotopic signal while limiting sample loss and achieving a high throughput. Under these constraints, research was undertaken to compare the performance of different pre-treatment protocols. Charred archaeological plant material was selected for isotopic analysis (δ 13 C and δ 15 N values) by isotope ratio mass spectrometry from a variety of plant species, time periods and soil conditions. Preservation conditions and the effectiveness of cleaning protocols were assessed through Fourier transform infrared spectroscopy and X-ray fluorescence (XRF) spectrometry. An acid-base-acid protocol, successfully employed in radiocarbon dating, was used to define a contamination-free isotopic reference. Acid-base-acid isotopic measurements were compared with those obtained from untreated material and an acid-only protocol. The isotopic signals of untreated material and the acid-only protocol typically did not differ more than 1‰ from those of the acid-base-acid reference. There were no significant isotopic offsets between acid-base-acid and acid-only or untreated samples. Sample losses in the acid-base-acid protocol were on average 50 ± 17% (maximum = 98.4%). Elemental XRF measurements showed promising results in the detection of more contaminated samples albeit with a high rate of false positives. For the large range of preservation conditions described in the study, untreated charred plant samples, water cleaned of sediments, provide reliable stable isotope ratios of carbon and nitrogen. The use of pre-treatments may be necessary under different preservation conditions or more conservative measurement uncertainties should be reported. Copyright © 2017 John Wiley & Sons, Ltd.

  19. Anammox biofilm in activated sludge swine wastewater treatment plants.

    Science.gov (United States)

    Suto, Ryu; Ishimoto, Chikako; Chikyu, Mikio; Aihara, Yoshito; Matsumoto, Toshimi; Uenishi, Hirohide; Yasuda, Tomoko; Fukumoto, Yasuyuki; Waki, Miyoko

    2017-01-01

    We investigated anammox with a focus on biofilm in 10 wastewater treatment plants (WWTPs) that use activated sludge treatment of swine wastewater. In three plants, we found red biofilms in aeration tanks or final sedimentation tanks. The biofilm had higher anammox 16S rRNA gene copy numbers (up to 1.35 × 10 12 copies/g-VSS) and higher anammox activity (up to 295 μmoL/g-ignition loss/h) than suspended solids in the same tank. Pyrosequencing analysis revealed that Planctomycetes accounted for up to 17.7% of total reads in the biofilm. Most of them were related to Candidatus Brocadia or Ca. Jettenia. The highest copy number and the highest proportion of Planctomycetes were comparable to those of enriched anammox sludge. Thus, swine WWTPs that use activated sludge treatment can fortuitously acquire anammox biofilm. Thus, concentrated anammox can be detected by focusing on red biofilm. Copyright © 2016 Elsevier Ltd. All rights reserved.

  20. Reliability and validity enhancement: a treatment package for increasing fidelity of self-report.

    Science.gov (United States)

    Bornstein, P H; Hamilton, S B; Miller, R K; Quevillon, R P; Spitzform, M

    1977-07-01

    This study investigated the effects of reliability and validity "enhancers" on fidelity of self-report data in an analogue therapy situation. Under the guise of a Concentration Skills Training Program, 57 Ss were assigned randomly to one of the following conditions: (a) Reliability Enhancement; (b) Truth Talk; (c) No Comment Control. Results indicated significant differences among groups (p less than .05). In addition, tests of multiple comparisons revealed that Reliability Enhancement was significantly different from Truth Talk in occurrences of unreliability (p less than .05). These findings are discussed in light of the increased reliance on self-report data in behavioral intervention, and recommendations are made for future research.

  1. Cooling intensification during quenching of power plant components - the way to increase reliability

    International Nuclear Information System (INIS)

    Borisov, I.A.

    1989-01-01

    To enchance the complex of mechanical properties and to increase operation time of large components of power facilities, regimes of accelerated cooling are developed. Results of heat treatment with accelerated cooling of turbine rotor of steel 26KhN3M2FAA, disks of turbine welded rotor of steel 20KhN2MFAA, components of steel 35KhN3MFA, are given. Special steels with carbon content less than 0.30% for details of power machine-building are developed

  2. Characterization of NORM material produced in a water treatment plant

    Energy Technology Data Exchange (ETDEWEB)

    Suursoo, S.; Kiisk, M.; Jantsikene, A.; Koch, R.; Isakar, K.; Realo, E. [University of Tartu, Institute of Physics (Estonia); Lumiste, L. [Tallinn University of Technology (Estonia)

    2014-07-01

    In February 2012 a water treatment plant was opened in Viimsi, Estonia. The plant is designed for removal of iron, manganese, and radium from groundwater. The first 2 years of operation have shown that the purification process generates significant amounts of materials with elevated radium levels. The treatment plant is fed by nine wells, which open to radium-rich aquifers. Purification is achieved by aeration and filtration processes. Aerated water is led through two successive filter columns, first of them is filled with MnO{sub 2} coated material FMH and filtration sand, the second one with zeolite. The plant has five parallel treatment lines with a total of 95 tons of FMH + filtration sand, and 45 tons of zeolite. The average capacity of the facility has been 2400 m{sup 3}/day. Yearly input of radium to the plant is estimated to be 325 MBq for Ra-226, and 420 MBq for Ra-228. Most of the radium (about 90%) accumulates in the filter columns. Some 8-9% of it is removed by backwash water during regular filter backwash cycles. To characterize radium accumulation and its removal by backwash in detail, treatment line no. 5 is sampled monthly for filter materials and backwash water. A steady growth of radium activity concentrations is apparent in both filter materials. In the top layer of the first stage filter (FMH+sand), Ra-226 and Ra-228 activity concentrations (per unit dry weight) reached (1540 ± 60) Bq/kg and (2510 ± 50) Bq/kg (k=2), respectively, by April 2013. At the same time, radium content in the top layer of the second stage filter (zeolite) was an order of magnitude higher: (19 600 ± 130) Bq/kg for Ra-226, and (22 260 ± 170) Bq/kg for Ra-228 (k=2). Radium is not evenly distributed throughout the filter columns. A rough estimate can be given that after 1.25 years of operation (by April 2013) the accumulated activities in treatment line no. 5 reached 1000 MBq for Ra-226 and 1200 MBq for Ra-228. Although filters are the most important type of NORM

  3. Strategies to Combat Antibiotic Resistance in the Wastewater Treatment Plants

    Directory of Open Access Journals (Sweden)

    Fateme Barancheshme

    2018-01-01

    Full Text Available The main goal of this manuscript is to review different treatment strategies and mechanisms for combating the antibiotic resistant bacteria (ARB and antibiotic resistant genes (ARGs in the wastewater environment. The high amount of antibiotics is released into the wastewater that may promote selection of ARB and ARGs which find their way into natural environments. Emerging microbial pathogens and increasing antibiotic resistance among them is a global public health issue. The propagation and spread of ARB and ARGs in the environment may result in an increase of antibiotic resistant microbial pathogens which is a worldwide environmental and public health concern. A proper treatment of wastewater is essential before its discharge into rivers, lake, or sewage system to prevent the spread of ARB and ARGs into the environment. This review discusses various treatment options applied for combating the spread of ARB and ARGs in wastewater treatment plants (WWTPs. It was reported that low-energy anaerobic–aerobic treatment reactors, constructed wetlands, and disinfection processes have shown good removal efficiencies. Nanomaterials and biochar combined with other treatment methods and coagulation process are very recent strategies regarding ARB and ARGs removal and need more investigation and research. Based on current studies a wide-ranging removal efficiency of ARGs can be achieved depending on the type of genes present and treatment processes used, still, there are gaps that need to be further investigated. In order to find solutions to control dissemination of antibiotic resistance in the environment, it is important to (1 study innovative strategies in large scale and over a long time to reach an actual evaluation, (2 develop risk assessment studies to precisely understand occurrence and abundance of ARB/ARGs so that their potential risks to human health can be determined, and (3 consider operating and environmental factors that affect the

  4. Improving the reliability of service-water systems at nuclear power plants

    International Nuclear Information System (INIS)

    Neitzel, D.A.; Johnson, K.I.; Daling, P.M.; Chang, T.Y.

    1989-01-01

    Fouling and clogging caused by sedimentation, corrosion, and the buildup of biological organisms is a persistent problem whenever raw water from a river, lake, or ocean is used as a heat exchange medium. The fouling caused by raw water cooling of service-water systems at nuclear power plants is a particular concern because of the potential for affecting safety-related heat exchangers and components, including online and redundant backup units. Open-cycle service-water, as discussed here, provide cooling to reactor support systems required during shutdown and emergency conditions and relate to those heat exchangers and components cooled directly by raw water. To resolve this issue, the NRC initiated a research program at the Pacific Northwest Laboratory (PNL), to study the conditions that allow fouling and to compare alternative surveillance and control programs to minimize service water system fouling. There is no single solution to biological, sediment, and corrosion fouling. An effective surveillance and control program must satisfy certain criteria to address major areas of the service-water system and the major fouling types. Three fouling program alternatives were developed. Value/impact (or cost/benefit) studies were performed on these three alternatives. The alternative chosen to be most cost effective is a baseline fouling program. It consists of two principal elements of a control program, continuous chlorination (for example during bivalve spawning seasons) and periodic flushing and flow testing of redundant and infrequently used cooling loops, to minimize flow blockage that would result from biofouling and sediment/corrosion product buildup. In addition, a surveillance program is recommended to regularly inspect the intake structure for macroscopic biological fouling organisms, sediment, and corrosion

  5. Limited dissemination of the wastewater treatment plant core resistome.

    Science.gov (United States)

    Munck, Christian; Albertsen, Mads; Telke, Amar; Ellabaan, Mostafa; Nielsen, Per Halkjær; Sommer, Morten O A

    2015-09-30

    Horizontal gene transfer is a major contributor to the evolution of bacterial genomes and can facilitate the dissemination of antibiotic resistance genes between environmental reservoirs and potential pathogens. Wastewater treatment plants (WWTPs) are believed to play a central role in the dissemination of antibiotic resistance genes. However, the contribution of the dominant members of the WWTP resistome to resistance in human pathogens remains poorly understood. Here we use a combination of metagenomic functional selections and comprehensive metagenomic sequencing to uncover the dominant genes of the WWTP resistome. We find that this core resistome is unique to the WWTP environment, with resistome is comparable to that of the soil resistome.

  6. Chemical treatment of ammonium fluoride solution in uranium reconversion plant

    International Nuclear Information System (INIS)

    Carvalho Frajndlich, E.U. de.

    1992-01-01

    A chemical procedure is described for the treatment of the filtrate, produced from the transformation of uranium hexafluoride (U F 6 ) into ammonium uranyl carbonate (AUC). This filtrate is an intermediate product in the U F 6 to uranium dioxide (U O 2 ) reconversion process. The described procedure recovers uranium as ammonium peroxide fluoro uranate (APOFU) by precipitation with hydrogen peroxide (H 2 O 2 ), and as later step, its calcium fluoride (CaF 2 ) co-precipitation. The recovered uranium is recycled to the AUC production plant. (author)

  7. Systems reliability/structural reliability

    International Nuclear Information System (INIS)

    Green, A.E.

    1980-01-01

    The question of reliability technology using quantified techniques is considered for systems and structures. Systems reliability analysis has progressed to a viable and proven methodology whereas this has yet to be fully achieved for large scale structures. Structural loading variants over the half-time of the plant are considered to be more difficult to analyse than for systems, even though a relatively crude model may be a necessary starting point. Various reliability characteristics and environmental conditions are considered which enter this problem. The rare event situation is briefly mentioned together with aspects of proof testing and normal and upset loading conditions. (orig.)

  8. Characterization and possible uses of ashes from wastewater treatment plants

    International Nuclear Information System (INIS)

    Merino, Ignacio; Arevalo, Luis F.; Romero, Fernando

    2005-01-01

    This work, on the ashes from the wastewater treatment plant of Galindo (Vizcaya, Spain), has been outlined with the purpose of finding their physico-chemical properties and suggesting possible applications. Ashes contain important quantities of iron, calcium, silica, alumina and phosphates. X-Ray diffraction data make it possible to estimate the mineralogical compositions of the original ashes and also, after thermal treatment at 1200 and 1300 deg. C, the main reactions occurring in thermal treatment. Particle size analysis makes it possible to classify ashes as a very fine powdered material. The thermal treatment leads to a densification of the material and provokes losses of weight mainly due to the elimination of water, carbon dioxide and sulphur trioxide. Application tests show that ashes are not suitable for landfill and similar applications, because of their plastic properties. Testing for pozzolanic character, after the ashes had been heated at 1200 deg. C, did not lead to a strong material probably due to low contents in silica and alumina or to requiring a higher heating temperature. Thermal treatment leads to densification of the material with a considerable increase of compressive strength of the probes. The use of additives (clays and powdered glass) to improve ceramic properties of ashes will be the aim of a future work

  9. Local desalination treatment plant wastewater reuse and evaluation potential absorption of salts by the halophyte plants

    Directory of Open Access Journals (Sweden)

    Elham Kalantari

    2018-01-01

    Full Text Available The expansion of arid and semi-arid areas and consequently water scarcity are affected by climate change. This can influence on availability and quality of water while demands on food and water are increasing. As pressure on freshwater is increasing, utilization of saline water in a sustainable approach is inevitable. Therefore, bioremediation using salt tolerant plants that is consistent with sustainable development objectives might be an alternative and effective approach. In this study, saline wastewater from a local desalination treatment plant was utilized to irrigate four halophyte plants, including Aloevera, Tamarix aphylla, Rosmarinus officinalis and Matricaria chamomilla. A field experiment was designed and conducted in Zarrindasht, south of Iran in years 2012-2013 accordingly. Two irrigation treatments consisting of freshwater with salinity of 2.04 dS.m-1 and desalination wastewater with salinity of 5.77dSm-1 were applied. The experiment was designed as a split plot in the form of randomized complete block design (RCB with three replications. The results of variance analysis, ANOVA, on salt concentration in Aloevera showed that there was no significant difference between the effects of two irrigation water qualities except for Na. In Rosmarinus officinalis, only the ratio of K/Na showed a significant difference. None of the examined salt elements showed a significant difference in Tamarix aphylla irrigated with both water qualities. In Matricaria chamomilla, only Mg and K/Na ratio showed a significant difference (Duncan 5%. As a result, no significant difference was observed in salt absorption by the examined plants in treatments which were irrigated by desalination wastewater and freshwater. This could be a good result that encourages the use of similar wastewater to save freshwater in a sustainable system.

  10. Arabidopsis seedling flood-inoculation technique: a rapid and reliable assay for studying plant-bacterial interactions

    Directory of Open Access Journals (Sweden)

    Uppalapati Srinivasa R

    2011-10-01

    Full Text Available Abstract Background The Arabidopsis thaliana-Pseudomonas syringae model pathosystem is one of the most widely used systems to understand the mechanisms of microbial pathogenesis and plant innate immunity. Several inoculation methods have been used to study plant-pathogen interactions in this model system. However, none of the methods reported to date are similar to those occurring in nature and amicable to large-scale mutant screens. Results In this study, we developed a rapid and reliable seedling flood-inoculation method based on young Arabidopsis seedlings grown on MS medium. This method has several advantages over conventional soil-grown plant inoculation assays, including a shorter growth and incubation period, ease of inoculation and handling, uniform infection and disease development, requires less growth chamber space and is suitable for high-throughput screens. In this study we demonstrated the efficacy of the Arabidopsis seedling assay to study 1 the virulence factors of P. syringae pv. tomato DC3000, including type III protein secretion system (TTSS and phytotoxin coronatine (COR; 2 the effector-triggered immunity; and 3 Arabidopsis mutants affected in salicylic acid (SA- and pathogen-associated molecular pattern (PAMPs-mediated pathways. Furthermore, we applied this technique to study nonhost resistance (NHR responses in Arabidopsis using nonhost pathogens, such as P. syringae pv. tabaci, pv. glycinea and pv. tomato T1, and confirmed the functional role of FLAGELLIN-SENSING 2 (FLS2 in NHR. Conclusions The Arabidopsis seedling flood-inoculation assay provides a rapid, efficient and economical method for studying Arabidopsis-Pseudomonas interactions with minimal growth chamber space and time. This assay could also provide an excellent system for investigating the virulence mechanisms of P. syringae. Using this method, we demonstrated that FLS2 plays a critical role in conferring NHR against nonhost pathovars of P. syringae, but not to

  11. Design aspects of reverse osmosis plants for rad waste treatment

    International Nuclear Information System (INIS)

    Prabhakar, S.; Panicker, S.T.; Misra, B.M.

    1993-01-01

    The potential of reverse osmosis process has been well established in the nuclear waste treatment. The nuclear wastes are characterised by chemically insignificant levels of radioactive nuclides and small amounts (a few hundred ppm) of inactive ionic species. The basic design objectives in these systems aim at higher volume reduction factors, i.e. corresponding to recovery factor of more than 0.9 and a decontamination factor of at least 10, i.e. corresponding to a solute rejection of more than 90%. In this paper, the salient aspects of the design of a reverse osmosis system for radioactive waste treatment is discussed in the light of the operating experience of an experimental plant based on plate module configuration and utilizing cellulose acetate membranes prepared in our laboratory. (author). 3 refs., 5 figs., 2 tabs

  12. Surface treatments for material protection in nuclear power plants

    International Nuclear Information System (INIS)

    De, P.K.; Gadiyar, H.S.

    1987-01-01

    The paper highlights some of the surface treatment methods used in nuclear power plants to improve their performance. The corrosion resistance of zirconium alloys results from the formation of an adherent and protective film of ZrO 2 . Graphite coating of zircaloy-2 cladding minimizes the susceptibility to environmental induced cracking. Magnetite formation during the hot conditioning operation improves the corrosion resistance of carbon steel as well as controls the spread of radioactivity. It has been illustrated how the surface treatment is helpful for redistributing residual stress to facilitate conversion of tensile stress to compressive stress to mitigate failures due to stress corrosion and fatigue corrosion. Inhibitors and passivators can modify the surface conditions (in situ) of condenser tubes and cooling water systems. These aspects have been dealt in the text of the paper. (author). 8 refs., 3 figures

  13. Perspectives on modelling micropollutants in wastewater treatment plants

    DEFF Research Database (Denmark)

    Clouzot, Ludiwine; Cloutier, Frédéric; Vanrolleghem, Peter A.

    2013-01-01

    Models for predicting the fate of micropollutants (MPs) in wastewater treatment plants (WWTPs) have been developed to provide engineers and decision-makers with tools that they can use to improve their understanding of, and evaluate how to optimize, the removal of MPs and determine their impact......) addressing advancements in WWTP treatment technologies, (iii) making use of common approaches to data acquisition for model calibration and (iv) integrating ecotoxicological effects of MPs in receiving waters....... on the receiving waters. This paper provides an overview of such models, and discusses the impact of regulation, engineering practice and research on model development. A review of the current status of MP models reveals that a single model cannot represent the wide range of MPs that are present in wastewaters...

  14. State estimation for large-scale wastewater treatment plants.

    Science.gov (United States)

    Busch, Jan; Elixmann, David; Kühl, Peter; Gerkens, Carine; Schlöder, Johannes P; Bock, Hans G; Marquardt, Wolfgang

    2013-09-01

    Many relevant process states in wastewater treatment are not measurable, or their measurements are subject to considerable uncertainty. This poses a serious problem for process monitoring and control. Model-based state estimation can provide estimates of the unknown states and increase the reliability of measurements. In this paper, an integrated approach is presented for the optimization-based sensor network design and the estimation problem. Using the ASM1 model in the reference scenario BSM1, a cost-optimal sensor network is designed and the prominent estimators EKF and MHE are evaluated. Very good estimation results for the system comprising 78 states are found requiring sensor networks of only moderate complexity. Copyright © 2013 Elsevier Ltd. All rights reserved.

  15. The Waste Treatment Plant, a Work in Progress

    International Nuclear Information System (INIS)

    Hamel, W. F. Jr.; Duncan, G. M.

    2006-01-01

    There are many challenges in the design and construction of Department of Energy's (DOE) Waste Treatment and Immobilization Plant (WTP) at the Hanford site. The plant is being built to process some 55 million gallons of radioactive waste from 177 underground tanks. Engineering and construction are progressing on this largest project in the DOE complex. This paper describes some of WTP's principal recent challenges and opportunities and how they are being addressed to minimize impact on the project, enhance the capabilities of the facilities, and reduce risk. A significant new development in 2005 was the need to account for higher seismic accelerations than originally specified for the facility structures and equipment. Efforts have centered on continuing design and construction with minimal risk, while the final seismic design spectra was developed. Other challenges include development of an alternative cesium ion exchange resin to minimize the risk from reliance on a single product, implementing advanced analytical techniques to improve laboratory performance, adopting a thinner walled high level waste (HLW) canister to reduce waste volume and mission duration, and commissioning a comprehensive external flowsheet review of the design, along with its underpinning technologies, and projected plant operability. These challenges make it clear that WTP is a work in progress, but the challenges are being successfully resolved as the design and construction move on to completion. (authors)

  16. Engineering study radioactive liquid waste treatment plant refurbishment

    International Nuclear Information System (INIS)

    Suazo, I.L.

    1994-01-01

    This feasibility study will investigate the opportunities, restrictions and cost impact to refurbish the existing Radioactive Liquid Waste Treatment Plant (RLWTP) while utilizing the same basic criteria that was used in the development of the new Radioactive Liquid Waste Treatment Facility (RLWTF). The objective of this study is to perform a more in-depth analysis of refurbishing the existing than has been done in the past so as to provide a basis for comparison between refurbishing the existing or constructing a new. The existing plant is located at Technical Area 50 (TA-50) within the Los Alamos National Laboratory (LANL). The initial structure was built in 1963. Over the ensuing years, the building has been modified and several additions have been constructed. In 1966, laboratories, ion exchange and pretreatment functions were added. The decontamination and decommissioning activities and ventilation equipment were added in 1984. The following assumptions are the basic parameters considered in the development of a design concept to refurbish the RLWTP: (1) Allow continued operation of the during retrofit construction. (2) Design the necessary expansion within the site constraints. (3) Satisfy National Pollutant Discharge Elimination System (NPDES) and National Emission Standards for Hazardous Air Pollutants (NESHAPS) permit conditions and other environmental regulations. (4) Comply with present DOE Orders and building code requirements. The refurbishment concept is a phased demolition and construction process

  17. Fate of pharmaceuticals and personal care products in wastewater treatment plants - Conception of a database and first results

    International Nuclear Information System (INIS)

    Miege, C.; Choubert, J.M.; Ribeiro, L.; Eusebe, M.; Coquery, M.

    2009-01-01

    We created a database in order to quantitatively assess the occurrence and removal efficiency of pharmaceuticals and personal care products (PPCPs) in wastewater treatment plants (WWTPs). From 117 scientific publications, we compiled 6641 data covering 184 PPCPs. Data included the concentrations of PPCPs in WWTP influents and effluents, their removal efficiency and their loads to the aquatic environment. The first outputs of our database allowed to identify the most investigated PPCPs in WWTPs and the most persistent ones, and to obtain reliable and quantitative values on their concentrations, frequency of detection and removal efficiency in WWTPs. We were also able to compare various processes and pointed out activated sludge with nitrogen treatment and membrane bioreactor as the most efficient ones. - By means of a database including information from 117 international scientific papers, we present quantitative conclusions on the concentrations, frequencies of detection and removals of pharmaceutical products in wastewater treatment plants.

  18. Exposure assessment of residents living near a wood treatment plant

    International Nuclear Information System (INIS)

    Dahlgren, James; Warshaw, Raphael; Horsak, Randy D.; Parker, Frank M. III; Takhar, Harpreet

    2003-01-01

    We report the results of environmental sampling and modeling in a neighborhood adjacent to a wood processing plant. This plant used creosote and pentachlorophenol (PCP) to treat wood for over 70 years. Between 1999 and 2001, environmental samples were obtained to quantify the level of environmental contamination from the wood processing plant. Blood from 10 residents was measured for chlorinated dioxins and dibenzofurans. Soil sediment samples from drainage ditches and attic/dust samples from nearby residents' homes were tested for polychlorinated dioxins, furans, and polycyclic aromatic hydrocarbons (PAH). The dioxin congeners analysis of the 10 residents revealed elevated valued for octachlorodibenzo-p-dioxin and heptachlorodibenzo-p-dioxin compatible with PCP as the source. The levels of carcinogenic PAHs were higher than background levels and were similar to soil contamination on wood preserving sites. Wipe sampling in the kitchens of 11 homes revealed that 20 of the 33 samples were positive for octachlorinated dioxins with a mean value of 10.27 ng/m 2 . The soil, ditch samples, and positive wipe samples from the homes indicate a possible ongoing route of exposure to the contaminants in the homes of these residents. Modeled air exposure estimated for the wood processing waste chemicals indicate some air exposure to combustion products. The estimated air levels for benzo(a)pyrene and tetrachlorodibenzodiozin in this neighborhood exceeded the recommended levels for these compounds in some states. The quantitative data presented suggest a significant contamination of a neighborhood by wood processing waste chemicals. These findings suggest the need for more stringent regulations on waste discharges from wood treatment plants

  19. MOBIL CONTAINER UNIT FOR SEWAGE SLUDGE UTILIZATION FROM SMALL AND MEDIUM WASTWATER TREATMENT PLANTS

    OpenAIRE

    Stanisław Ledakowicz; Paweł Stolarek; A. Malinowski

    2016-01-01

    The most wastewater treatment plants in Poland are small and medium plants of flow capacity below 1000 m3/d. These plants are not able to build sludge incineration plants and the transportation costs to the nearest plants increase the total costs of wastewater treatment. Polish company Metal Expert together with the French company ETIA and Lodz University of Technology proposed mobile unit for integrated drying and pyrolysis of sewage sludge in a pilot bench scale with capacity of 100 kg/h ...

  20. Efficiency of domestic wastewater treatment plant for agricultural reuse

    Directory of Open Access Journals (Sweden)

    Claudinei Fonseca Souza

    2015-07-01

    Full Text Available The increasing demand for water has made the treatment and reuse of wastewater a topic of global importance. This work aims to monitor and evaluate the efficiency of a wastewater treatment plant’s (WWTP physical and biological treatment of wastewater by measuring the reduction of organic matter content of the effluent during the treatment and the disposal of nutrients in the treated residue. The WWTP has been designed to treat 2500 liters of wastewater per day in four compartments: a septic tank, a microalgae tank, an upflow anaerobic filter and wetlands with cultivation of Zantedeschia aethiopica L. A plant efficiency of 90% of organic matter removal was obtained, resulting in a suitable effluent for fertigation, including Na and Ca elements that showed high levels due to the accumulation of organic matter in the upflow anaerobic filter and wetlands. The WWTP removes nitrogen and phosphorus by the action of microalgae and macrophytes used in the process. The final effluent includes important agricultural elements such as nitrogen, phosphorus, calcium and potassium and, together with the load of organic matter and salts, meets the determination of NBR 13,969/1997 (Standard of the Brazilian Technical Standards Association for reuse in agriculture, but periodic monitoring of soil salinity is necessary.