WorldWideScience

Sample records for nuclear plant control

  1. Advanced nuclear plant control complex

    International Nuclear Information System (INIS)

    Scarola, K.; Jamison, S.; Manazir, R.M.; Rescorl, R.L.; Harmon, D.L.

    1991-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system which is nuclear qualified for rapid response to changes in plant parameters and a component control system which together provide a discrete monitoring and control capability at a panel in the control room. A separate data processing system, which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs and a large, overhead integrated process status overview board. The discrete indicator and alarm system and the data processing system receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accidental conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof. (author)

  2. Emergency control centers for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

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

  3. Fuzzy logic control of nuclear power plant

    International Nuclear Information System (INIS)

    Yao Liangzhong; Guo Renjun; Ma Changwen

    1996-01-01

    The main advantage of the fuzzy logic control is that the method does not require a detailed mathematical model of the object to be controlled. In this paper, the shortcomings and limitations of the model-based method in nuclear power plant control were presented, the theory of the fuzzy logic control was briefly introduced, and the applications of the fuzzy logic control technology in nuclear power plant controls were surveyed. Finally, the problems to be solved by using the fuzzy logic control in nuclear power plants were discussed

  4. Operation control device for nuclear power plants

    International Nuclear Information System (INIS)

    Suto, Osamu.

    1982-01-01

    Purpose: To render the controlling functions of a central control console more centralized by constituting the operation controls for a nuclear power plant with computer systems having substantially independent functions such as those of plant monitor controls, reactor monitor management and CRT display and decreasing interactions between each of the systems. Constitution: An input/output device for the input of process data for a nuclear power plant and indication data for a plant control console is connected to a plant supervisory and control computer system and a display computer system, the plant supervisory control computer system and a reactor and management computer system are connected with a CRT display control device, a printer and a CRT display input/output device, and the display computer system is connected with the CRT display control device and the CRT display unit on the central control console, whereby process input can be processed and displayed at high speed. (Yoshino, Y.)

  5. Linguistic control of a nuclear power plant

    International Nuclear Information System (INIS)

    Feeley, J.J.; Johnson, J.C.

    1987-01-01

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

  6. Nuclear reactor kinetics and plant control

    CERN Document Server

    Oka, Yoshiaki

    2013-01-01

    Understanding time-dependent behaviors of nuclear reactors and the methods of their control is essential to the operation and safety of nuclear power plants. This book provides graduate students, researchers, and engineers in nuclear engineering comprehensive information on both the fundamental theory of nuclear reactor kinetics and control and the state-of-the-art practice in actual plants, as well as the idea of how to bridge the two. The first part focuses on understanding fundamental nuclear kinetics. It introduces delayed neutrons, fission chain reactions, point kinetics theory, reactivit

  7. Control system security in nuclear power plant

    International Nuclear Information System (INIS)

    Li Jianghai; Huang Xiaojin

    2012-01-01

    The digitalization and networking of control systems in nuclear power plants has brought significant improvements in system control, operation and maintenance. However, the highly digitalized control system also introduces additional security vulnerabilities. Moreover, the replacement of conventional proprietary systems with common protocols, software and devices makes these vulnerabilities easy to be exploited. Through the interaction between control systems and the physical world, security issues in control systems impose high risks on health, safety and environment. These security issues may even cause damages of critical infrastructures and threaten national security. The importance of control system security by reviewing several control system security incidents that happened in nuclear power plants was showed in recent years. Several key difficulties in addressing these security issues were described. Finally, existing researches on control system security and propose several promising research directions were reviewed. (authors)

  8. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    Klevans, E.H.

    1992-01-01

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

  9. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  10. Autonomous Control of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Basher, H.

    2003-01-01

    A nuclear reactor is a complex system that requires highly sophisticated controllers to ensure that desired performance and safety can be achieved and maintained during its operations. Higher-demanding operational requirements such as reliability, lower environmental impacts, and improved performance under adverse conditions in nuclear power plants, coupled with the complexity and uncertainty of the models, necessitate the use of an increased level of autonomy in the control methods. In the opinion of many researchers, the tasks involved during nuclear reactor design and operation (e.g., design optimization, transient diagnosis, and core reload optimization) involve important human cognition and decisions that may be more easily achieved with intelligent methods such as expert systems, fuzzy logic, neural networks, and genetic algorithms. Many experts in the field of control systems share the idea that a higher degree of autonomy in control of complex systems such as nuclear plants is more easily achievable through the integration of conventional control systems and the intelligent components. Researchers have investigated the feasibility of the integration of fuzzy logic, neural networks, genetic algorithms, and expert systems with the conventional control methods to achieve higher degrees of autonomy in different aspects of reactor operations such as reactor startup, shutdown in emergency situations, fault detection and diagnosis, nuclear reactor alarm processing and diagnosis, and reactor load-following operations, to name a few. With the advancement of new technologies and computing power, it is feasible to automate most of the nuclear reactor control and operation, which will result in increased safety and economical benefits. This study surveys current status, practices, and recent advances made towards developing autonomous control systems for nuclear reactors

  11. Autonomous Control of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Basher, H.

    2003-10-20

    A nuclear reactor is a complex system that requires highly sophisticated controllers to ensure that desired performance and safety can be achieved and maintained during its operations. Higher-demanding operational requirements such as reliability, lower environmental impacts, and improved performance under adverse conditions in nuclear power plants, coupled with the complexity and uncertainty of the models, necessitate the use of an increased level of autonomy in the control methods. In the opinion of many researchers, the tasks involved during nuclear reactor design and operation (e.g., design optimization, transient diagnosis, and core reload optimization) involve important human cognition and decisions that may be more easily achieved with intelligent methods such as expert systems, fuzzy logic, neural networks, and genetic algorithms. Many experts in the field of control systems share the idea that a higher degree of autonomy in control of complex systems such as nuclear plants is more easily achievable through the integration of conventional control systems and the intelligent components. Researchers have investigated the feasibility of the integration of fuzzy logic, neural networks, genetic algorithms, and expert systems with the conventional control methods to achieve higher degrees of autonomy in different aspects of reactor operations such as reactor startup, shutdown in emergency situations, fault detection and diagnosis, nuclear reactor alarm processing and diagnosis, and reactor load-following operations, to name a few. With the advancement of new technologies and computing power, it is feasible to automate most of the nuclear reactor control and operation, which will result in increased safety and economical benefits. This study surveys current status, practices, and recent advances made towards developing autonomous control systems for nuclear reactors.

  12. Digital control in nuclear power plants

    International Nuclear Information System (INIS)

    Bouzon, B.

    1984-01-01

    This document presents the latest automatic control structures used in the programmable control systems of 13.00 MW nuclear power plants constructed by Electricite de France. The impact of this technological innovation goes beyond a straightforward design modification; in addition to the new range of processes made possible, it permits far-reaching changes in the working method employed at the design office and in the field. (author)

  13. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    Klevans, E.H.

    1993-01-01

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

  14. Occupational dose control in Nuclear Power Plants

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  15. Nuclear material control systems for nuclear power plants

    International Nuclear Information System (INIS)

    1975-06-01

    Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

  16. Radiation control system of nuclear power plants

    International Nuclear Information System (INIS)

    Kapisovsky, V.; Kosa, M.; Melichar, Z.; Moravek, J.; Jancik, O.

    1977-01-01

    The SYRAK system is being developed for in-service radiation control of the V-1 nuclear power plant. Its basic components are an EC 1010 computer, a CAMAC system and communication means. The in-service release of radionuclides is measured by fuel can failure detection, by monitoring rare gases in the coolant, by gamma spectrometric coolant monitoring and by iodine isotopes monitoring in stack disposal. (O.K.)

  17. Nuclear reactor plants and control systems therefor

    International Nuclear Information System (INIS)

    de Boer, G.A.; de Hex, M.

    1976-01-01

    A nuclear reactor plant is described comprising at least two hydraulically separated but thermally interconnected heat conveying circuits, of which one is the reactor circuit filled with a non-water medium and the other one is the water-steam-circuit equipped with a steam generator, a feed water conduit controlled by a valve and a steam turbine, and a control system mainly influenced by the pressure drop caused in said feed water conduit and its control valve and having a value of at least 10 bars at full load

  18. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    Klevans, E.H.

    1991-01-01

    In September of 1989 work began on the DOE University Program grant DE-FG07-89ER12889. The grant provides support for a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this First Annual Technical Progress report summarizes the first year tasks while the appendices provide detailed information presented at conference meetings. One major addendum report, authored by M.A. Schultz, describes the ultimate goals and projected structure of an automatic distributed control system for EBR-2. The remaining tasks of the project develop specific implementations of various components required to demonstrate the intelligent distributed control concept

  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. Nuclear Power Plant Control and Instrumentation 1989

    International Nuclear Information System (INIS)

    1990-11-01

    The meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) was organized in order to summarize operating experience of nuclear power plant control systems, gain a general overview of activities in development of modern control systems and receive recommendations on the further directions and particular measures within the Agency's programme. The meeting was held at the IAEA Headquarters in Vienna and was attended by 21 national delegates and observers from 18 countries. The present volume contains: (1) report on the meeting of the IWG-NPPCI, Vienna, 8-10 May 1989, (2) report of the scientific secretary on the major activities of IAEA during 1987-89 in the NPPCI area, (3) terms of reference International Working Group on NPPCI and (4) reports of the national representatives to the International Working Group on NPPCI. The paper and discussions with practical experience and described actual problems encountered. Emphasis was placed on the technical, industrial and economical aspects of the introduction of modern control systems and on the improvement of plant availability and safety. A separate abstract was prepared for each of the 19 papers presented by members of the International Working Group. Refs, figs and tabs

  1. Controlled procurement for nuclear power plants

    International Nuclear Information System (INIS)

    MacFarlane, I.S.

    1985-01-01

    A method is presented for establishing a controlled materials management system that facilitates materials procurement at nuclear power plants. This method is based on the determination of informational data requirements, appropriate input and approvals, and extent of administrative controls. Implementation of the techniques described herein will ensure that the accuracy of important procurement information is not compromised by unauthorized initial input or changes and/or failure to maintain the information. Needed material can thus be ordered through the materials management system with a high degree of confidence that the correct items are ordered, with minimal internal lead time and minimum delays during the receiving process

  2. Regulatory control of nuclear power plants

    International Nuclear Information System (INIS)

    2002-01-01

    The purpose of this book is to support IAEA training courses and workshops in the field of regulatory control of nuclear power plants as well as to support the regulatory bodies of Member States in their own training activities. The target group is the professional staff members of nuclear safety regulatory bodies supervising nuclear power plants and having duties and responsibilities in the following regulatory fields: regulatory framework; regulatory organization; regulatory guidance; licensing and licensing documents; assessment of safety; and regulatory inspection and enforcement. Important topics such as regulatory competence and quality of regulatory work as well as emergency preparedness and public communication are also covered. The book also presents the key issues of nuclear safety such as 'defence-in-depth' and safety culture and explains how these should be taken into account in regulatory work, e.g. during safety assessment and regulatory inspection. The book also reflects how nuclear safety has been developed during the years on the basis of operating experience feedback and results of safety research by giving topical examples. The examples cover development of operating procedures and accident management to cope with complicated incidents and severe accidents to stress the importance of regulatory role in nuclear safety research. The main target group is new staff members of regulatory bodies, but the book also offers good examples for more experienced inspectors to be used as comparison and discussion basis in internal workshops organized by the regulatory bodies for refreshing and continuing training. The book was originally compiled on the basis of presentations provided during the two regulatory control training courses in 1997 and 1998. The textbook was reviewed at the beginning of the years 2000 and 2002 by IAEA staff members and consistency with the latest revisions of safety standards have been ensured. The textbook was completed in the

  3. Nuclear fuel control in fuel fabrication plants

    International Nuclear Information System (INIS)

    Seki, Yoshitatsu

    1976-01-01

    The basic control problems of measuring uranium and of the environment inside and outside nuclear fuel fabrication plants are reviewed, excluding criticality prevention in case of submergence. The occurrence of loss scraps in fabrication and scrap-recycling, the measuring error, the uranium going cut of the system, the confirmation of the presence of lost uranium and the requirement of the measurement control for safeguard make the measurement control very complicated. The establishment of MBA (material balance area) and ICA (item control area) can make clearer the control of inventories, the control of loss scraps and the control of measuring points. Besides the above basic points, the following points are to be taken into account: 1) the method of confirmation of inventories, 2) the introduction of reliable NDT instruments for the rapid check system for enrichment and amount of uranium, 3) the introduction of real time system, and 4) the clarification of MUF analysis and its application to the reliability check of measurement control system. The environment control includes the controls of the uranium concentration in factory atmosphere, the surface contamination, the space dose rate, the uranium concentration in air and water discharged from factories, and the uranium in liquid wastes. The future problems are the practical restudy of measurement control under NPT, the definite plan of burglary protection and the realization of the disposal of solid wastes. (Iwakiri, K.)

  4. Optimal estimation and control in nuclear power plants

    International Nuclear Information System (INIS)

    Purviance, J.E.; Tylee, J.L.

    1982-08-01

    Optimal estimation and control theories offer the potential for more precise control and diagnosis of nuclear power plants. The important element of these theories is that a mathematical plant model is used in conjunction with the actual plant data to optimize some performance criteria. These criteria involve important plant variables and incorporate a sense of the desired plant performance. Several applications of optimal estimation and control to nuclear systems are discussed

  5. Feedwater control system in nuclear power plants

    International Nuclear Information System (INIS)

    Masuyama, Hideo.

    1981-01-01

    Purpose: To enable switching operation for feedwater systems in a short time and with no fluctuations in the reactor water level by increasing or decreasing the flow rate in the feedwater systems during automatic operation by the amount of the fluctuations in the flow rate in the feedwater system during manual operation. Constitution: In a BWR type nuclear power plant having a plurality of feedwater systems to a nuclear reactor, a feedwater control system is constituted with a reactor water level controller, a M/A switcher for switching either of automatic flow rate demand signals or manual flow rate set signals from the reactor level controller to apply flow rate demand signals for each of the feedwater systems, a calculation device for calculating the flow rate set signals in the feedwater systems during manual operation and an adder for subtracting the flow rate set signals in the manual feedwater system calculated in the calculating device from the automatic flow rate demand signals for the feedwater systems during automatic operation. This enables rapid switching for the feedwater systems with no fluctuations in the reactor water level by increasing or decreasing the flow rate in the feedwater systems during automatic operation by the amount of fluctuations in the flow rate in the feedwater systems during manual operation and compensating the effects in upon manual and automatic switching by the M/A switcher. (Seki, T.)

  6. Instrumentation control system in nuclear power plant

    International Nuclear Information System (INIS)

    Hanai, Koi; Tai, Ichiro.

    1982-01-01

    Purpose: To improve the reliability of instrumentation control system in a nuclear power plant by using an optical fiber cable as a transmission path between a multiplexer and a central control room to thereby eliminate noises resulted from electromagnetic inductions or the likes. Constitution: Signals from neutron detectors are sent by way of ceramic-insulated cables to pre-amplifiers disposed outside of the pressure vessel of a nuclear reactor, converted into voltage pulse signals and then sent by way of coaxial cables to a multiplexer. The multiplexer receives a plurality of voltage pulse signals corresponding to the neutron detectors respectively, converts them into a time-shared electric signal train and sends it to an optical pulse transmitter. The transmitter converts the supplied signals into an optical pulse signal train corresponding to the electric signal train from the multiplexer and sends it by way of an optical fiber cable to an optical pulse receiver disposed in a central control room. (Kawakami, Y.)

  7. 78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2013-06-27

    ... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

  8. Nuclear power plant control room operator control and monitoring tasks

    International Nuclear Information System (INIS)

    Bovell, C.R.; Beck, M.G.; Carter, R.J.

    1998-01-01

    Oak Ridge National Laboratory is conducting a research project the purpose of which is to develop the technical bases for regulatory review criteria for use in evaluating the safety implications of human factors associated with the use of artificial intelligence and expert systems, and with advanced instrumentation and control (I and C) systems in nuclear power plants (NPP). This report documents the results from Task 8 of that project. The primary objectives of the task was to identify the scope and type of control and monitoring tasks now performed by control-room operators. Another purpose was to address the types of controls and safety systems needed to operate the nuclear plant. The final objective of Task 8 was to identify and categorize the type of information and displays/indicators required to monitor the performance of the control and safety systems. This report also discusses state-of-the-art controls and advanced display devices which will be available for use in control-room retrofits and in control room of future plants. The fundamental types of control and monitoring tasks currently conducted by operators can be divided into four classifications: function monitoring tasks, control manipulation tasks, fault diagnostic tasks, and administrative tasks. There are three general types of controls used in today's NPPs, switches, pushbuttons, and analog controllers. Plant I and C systems include components to achieve a number of safety-related functions: measuring critical plant parameters, controlling critical plant parameters within safety limits, and automatically actuating protective devices if safe limits are exceeded. The types of information monitored by the control-room operators consist of the following parameters: pressure, fluid flow and level, neutron flux, temperature, component status, water chemistry, electrical, and process and area radiation. The basic types of monitoring devices common to nearly all NPP control rooms include: analog meters

  9. Macrofouling control in nuclear power plants

    International Nuclear Information System (INIS)

    Ekis, E.W. Jr.; Keoplin-Gall, S.M.; McCarthy, R.E.

    1991-01-01

    Macrofouling of cooling-water systems is one of the more significant and costly problems encountered in the nuclear power industry. Both marine and freshwater macroinvertebrates can be responsible for losses in plant availability because of plugged intakes and heat transfer equipment. There is a greater diversity of macrofouling organisms in marine waters than in fresh waters. Marine macrofouling organisms include barnacles, mollusks, bryozoans, and hydroids. Barnacles are crustaceans with feathery appendages, which allow them to attach to a variety of surfaces. They are a major cause of severe macrofouling because they can remain attached even after death. The major freshwater macrofouling organisms include the Asiatic Clam (Corbicula fluminea) and the newest freshwater macrofouler, the Zebra Mussel (Dreissena polymorpha). The introduction of the Zebra Mussel into the Great Lakes has created economic and ecological problems that will not easily be solved. The threat of intercontinental dispersal of the Zebra Mussel in America is serious. Research programs have been initiated around the country to develop control methods for this macrofouling problem. The various control methodologies can be classified in the following categories: biological, chemical, physical, and mechanical. Laboratory experiments were performed to evaluate the efficacy of Actibrom against mature Zebra Mussels

  10. Environmental radioactive contamination and its control for nuclear power plants

    International Nuclear Information System (INIS)

    Shi Zhongqi; Qu Jingyuan; Cui Yongli

    1998-01-01

    The environmental radioactive releases and exposure to human being due to operation of nuclear power plants in the world and in China, environmental contamination and consequences caused by severe nuclear power plant accidents in the history, control of the radioactive contamination in China, and some nuclear laws on the radioactive contamination control established by international organizations and USA etc. are described according to literature investigation and research. Some problems and comments in radioactive contamination control for nuclear power plants in China are presented. Therefore, perfecting laws and regulations and enhancing surveillances on the contamination control are recommended

  11. Automatic control of nuclear power plants

    International Nuclear Information System (INIS)

    Jover, P.

    1976-01-01

    The fundamental concepts in automatic control are surveyed, and the purpose of the automatic control of pressurized water reactors is given. The response characteristics for the main components are then studied and block diagrams are given for the main control loops (turbine, steam generator, and nuclear reactors) [fr

  12. Computerized control and management at the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Mitosinka, J.; Korec, J.

    1992-01-01

    The proposed automation of the nuclear power plant control system includes a division of the control system into three hierarchic levels, supplemented with an additional level. These comprise the automated system of control of technological processes, the all-plant control of the power-generating process, the control of backup activities and of technical and economic activities, and top managerial control. The efficiency of the nuclear power plant operation, i.e. attainment of the maximum electricity output with minimum costs while securing the required safety, is the principal criterion in the design of the data model. Listed are tasks that would lend themselves to automation within the automated system of nuclear power plant control, and the basic scheme of their automation as follows from an analysis performed at the Temelin nuclear power plant. (Z.S). 2 figs., 2 refs

  13. Power control of the Angra-2 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Souza Mendes, J.E. de

    1986-01-01

    The systems for the power control of the Nuclear Power Plant Angra 2 have a high degree of automation so that few operator actions are required during power operation. The power control strategy and the operation principles of the control systems, here presented, make possible a great flexibility of the Plant operation. (Author) [pt

  14. Angra nuclear plant - environmental control program

    International Nuclear Information System (INIS)

    Kircher, E.; Cruz, E.S. da

    1989-01-01

    The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs

  15. New technology in nuclear power plant instrumentation and control

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The primary topic of this book is what can be done to improve nuclear power plant operation safety and the economic benefits that can be gained with the utilization of advance instrumentation and control technology. Other topics discussed are the industry's reluctance to accept new designs determining cost effective improvements, and difficulties in meeting regulatory standards with new technology control. The subjects will be useful when considering the area of instrumentation and control for enhancing plant operation and safety. Contents: Advanced Instrumention, Plant Control and Monitoring, Plant Diagnostics and Failure Detection, Human Factors Considerations in Instrumentation and Control, NRC and Industry Perspective on Advanced Instrumentation and Control

  16. Screen-based process control in nuclear plants

    International Nuclear Information System (INIS)

    Hinz, W.; Arnoldt, C.; Hessler, C.

    1993-01-01

    Requirements, development and conceptual design of a screen-based control room for nuclear power plants are outlined. The control room consists of three or four equally equipped operator workstations comprising screens for process information and manual process control. A plant overview will assist the coordination among the operators. A safety classified backup system (safety control area) is provided to cover postulated failures of the control means. Some aspects of ergonomical validation and of future development trends are discussed. (orig.) [de

  17. Computer-based control systems of nuclear power plants

    International Nuclear Information System (INIS)

    Kalashnikov, V.K.; Shugam, R.A.; Ol'shevsky, Yu.N.

    1975-01-01

    Computer-based control systems of nuclear power plants may be classified into those using computers for data acquisition only, those using computers for data acquisition and data processing, and those using computers for process control. In the present paper a brief review is given of the functions the systems above mentioned perform, their applications in different nuclear power plants, and some of their characteristics. The trend towards hierarchic systems using control computers with reserves already becomes clear when consideration is made of the control systems applied in the Canadian nuclear power plants that pertain to the first ones equipped with process computers. The control system being now under development for the large Soviet reactors of WWER type will also be based on the use of control computers. That part of the system concerned with controlling the reactor assembly is described in detail

  18. Backfitting of the nuclear plant V1 power control system

    International Nuclear Information System (INIS)

    Karpeta, C.; Rubek, J.; Stirsky, P.

    1985-01-01

    The paper deals with some aspects of implementation of modifications into the Czechoslovak nuclear plant V1 control system as called for on the basis of experience gained during the first period of the plant operation. Brief description of the plant power control system and its main functions is given. Some deficiencies in the system performance during abnormal conditions are outlined and measures taken to overcome them are presented. (author)

  19. Dynamics and control of nuclear power plants

    International Nuclear Information System (INIS)

    Tomsic, M.; Mavko, B.; Aleksic, U.; Stritar, A.; Adrinek, R.

    1977-01-01

    A mathematical model of the power plant with a pressurized water reactor has been prepared and tested. The model is intended for a schematic simulator based on a digital computer. The results of the simulation run for various normal transients are in good agreement with literature data. Equipment for computer control of the experimental reactor TRIGA has been completed. The equipment includes two microcomputers and associated interface circuits. Presently, only data logging is performed. The analyses of random signals on the TRIGA reactor have been continued. Measurements of neutron flux, fuel temperature and cooling water duct have been performed

  20. Regulatory control of maintenance activities in Argentine nuclear power plants

    International Nuclear Information System (INIS)

    Calvo, J.C.; Caruso, G.

    2000-01-01

    The main maintenance objective is to assure that the safety features of structures, components and systems of nuclear power plants are kept as designed. Therefore, there is a direct relationship between safety and maintenance. Owing to the above mentioned, maintenance activities are considered a relevant regulatory issue for the Argentine Nuclear Regulatory Authority (ARN). This paper describes the regulatory control to maintenance activities of Argentine nuclear power plants. It also addresses essential elements for maintenance control, routine inspections, special inspections during planned outages, audits and license conditions and requirements. (author)

  1. Nuclear Power Plant Control and Instrumentation in Pakistan

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  2. Retrofit of safety and control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Keiper, J.T.; Fassett, G.B.

    1986-01-01

    The modularity, compactness, compatibility, and licensability of the microcontrol system make it a cost-effective approach to obtain the benefits of digital control technology in the retrofit of nuclear power plants. Retrofit of individual loops or complete systems can be scheduled to meet the operational needs of the plant. The existing racks, panels, and cable systems can be utilized to the maximum extent to minimize the installed cost. Future expansion to total plant control or plant management is supported by the network communication module or gateway. The microcontrol module provides benefits now in improved operation, and future benefits in planned, controlled upgrading

  3. Distributed control system for CANDU 9 nuclear power plant

    International Nuclear Information System (INIS)

    Harber, J.E.; Kattan, M.K.; Macbeth, M.J.

    1996-01-01

    Canadian designed CANDU pressurized heavy water nuclear reactors have been world leaders in electrical power generation. The CANDU 9 project is AECL's next reactor design. The CANDU 9 plant monitoring, annunciation, and control functions are implemented in two evolutionary systems; the distributed control system (DCS) and the plant display system (PDS). The CDS implements most of the plant control functions in a single hardware platform. The DCS communicates with the PDS to provide the main operator interface and annunciation capabilities of the previous control computer designs along with human interface enhancements required in a modern control system. (author)

  4. Dynamic cost control information system for nuclear power plant construction

    International Nuclear Information System (INIS)

    Wang Yongqing; Liu Wei

    1998-01-01

    The authors first introduce the cost control functions of some overseas popular project management software at present and the specific ways of cost control of nuclear power plant construction in China. Then the authors stress the necessity of cost and schedule control integration and present the concept of dynamic cost control, the design scheme of dynamic cost control information system and the data structure modeling. Based on the above, the authors can develop the system which has the functions of dynamic estimate, cash flow management and cost optimization for nuclear engineering

  5. Recent control and instrumentation systems for BWR nuclear power plant

    International Nuclear Information System (INIS)

    Fujii, Hiroaki; Higashikawa, Yuichi; Sato, Hideyuki

    1990-01-01

    For the needs of the more stable operation of nuclear power stations, the upgrading of the measurement and control system for BWRs has been promoted by positively introducing remarkably advancing electronic technology. Further, it is aimed at to construct the synthetic digitized measurement and control system for nuclear power stations to heighten the operation reliability in ABWRs. As the first step of the development in the synthetic digitization, the monitoring and control system for radioactive waste treatment was put in practical use for No.5 plant of Kashiwazaki, Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. Hitachi Ltd. has promoted the development and the application to actual plants of the measurement and control system for BWRs, in which digital control technology, optical information transmission technology and the operation-supporting technology using a computer were utilized. Hereafter, it is intended to expand the application of digital measurement and control aiming at improving the reliability, operation performance and maintainability. The nuclear power plant control complex with advanced man-machine interface-90 (NUCAMM-90) was developed, and its application to actual plants is planned. (K.I.)

  6. Reactor instrumentation and control in nuclear power plants in Germany

    International Nuclear Information System (INIS)

    Aleite, W.

    1993-01-01

    The pertinent legislation, guidelines and standards of importance for nuclear power plant construction as well as the relevant committees in Germany are covered. The impact of international developments on the German regulatory scene is mentioned. A series of 15 data sheets on reactor control, followed by 5 data sheets on instrumentation and control in nuclear power plants, which were drawn up for German plants, are compared and commented in some detail. Digitalization of instrumentation and control systems continues apace. To illustrate the results that can be achieved with a digitalized information system, a picture series that documents a plant test of behavior on simulated steam generator tube rupture is elaborately commented. An outlook on backfitting and upgrading applications concludes this paper. (orig.) [de

  7. Control and automation technology in United States nuclear power plants

    International Nuclear Information System (INIS)

    Sun, B.K.H.

    1997-01-01

    The need to use computers for nuclear power plant design, engineering, operation and maintenance has been growing since the inception of commercial nuclear power electricity generation in the 1960s. The needs have intensified in recent years as the demands of safety and reliability, as well as economic competition, have become stronger. The rapid advance of computer hardware and software technology in the last two decades has greatly enlarged the potential of computer applications to plant instrumentation and control of future plants, as well as those needed for operation of existing plants. The traditional role of computers for mathematical calculations and data manipulation has been expanded to automate plant control functions and to enhance human performance and productivity. The major goals of using computers for instrumentation and control of nuclear power plants are (1) to improve safety; (2) to reduce challenges to the power plant; (3) to reduce the cost of operations and maintenance; (4) to enhance power production, and (5) to increase productivity of people. Many functions in nuclear power plants are achieved by a combination of human action and automation. Increasingly, computer-based systems are used to support operations and maintenance personnel in the performance of their tasks. There are many benefits which can accrue from the use of computers but it is important to ensure that the design and implementation of the support system and the human task places the human in the correct role in relation to the machine; that is, in a management position, with the computer serving the human. In addition, consideration must be given to computer system integrity, software validation and verification, consequences of error, etc., to ensure its reliability for nuclear power plant applications. (author). 31 refs

  8. Control and automation technology in United States nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Sun, B K.H. [Sunutech, Inc., Los Altos, CA (United States)

    1997-07-01

    The need to use computers for nuclear power plant design, engineering, operation and maintenance has been growing since the inception of commercial nuclear power electricity generation in the 1960s. The needs have intensified in recent years as the demands of safety and reliability, as well as economic competition, have become stronger. The rapid advance of computer hardware and software technology in the last two decades has greatly enlarged the potential of computer applications to plant instrumentation and control of future plants, as well as those needed for operation of existing plants. The traditional role of computers for mathematical calculations and data manipulation has been expanded to automate plant control functions and to enhance human performance and productivity. The major goals of using computers for instrumentation and control of nuclear power plants are (1) to improve safety; (2) to reduce challenges to the power plant; (3) to reduce the cost of operations and maintenance; (4) to enhance power production, and (5) to increase productivity of people. Many functions in nuclear power plants are achieved by a combination of human action and automation. Increasingly, computer-based systems are used to support operations and maintenance personnel in the performance of their tasks. There are many benefits which can accrue from the use of computers but it is important to ensure that the design and implementation of the support system and the human task places the human in the correct role in relation to the machine; that is, in a management position, with the computer serving the human. In addition, consideration must be given to computer system integrity, software validation and verification, consequences of error, etc., to ensure its reliability for nuclear power plant applications. (author). 31 refs.

  9. Water quality control method and device for nuclear power plant and nuclear power plant

    International Nuclear Information System (INIS)

    Nagase, Makoto; Asakura, Yamato; Uetake, Naoto; Sawa, Toshio; Uchida, Shunsuke; Takeda, Renzo; Osumi, Katsumi.

    1993-01-01

    In a BWR type nuclear power plant, water quality of coolants is controlled so as to lower deposition rate of Co ions in reactor water on a fuel cladding tube. The water quality control method includes (1) decreasing an iron concentration in feedwater to less than 0.1ppb, (2) adjusting coolants weakly acidic and (3) controlling dissolved oxygen concentration in reactor water to 20ppb. This can decrease 60 Co ion concentration even if 60 Co ion concentration is increased by the change of environment for the operation in future, such as an operation with hydrogen injection and extention of fuel burnup degree. (T.M.)

  10. Control and automation technology in United States nuclear power plants

    International Nuclear Information System (INIS)

    Sun, B.K.H.

    1995-01-01

    The need to use computers for nuclear power plant design, engineering, operation and maintenance has been growing since the inception of commercial nuclear power electricity generation in the 1960s. The needs have intensified in recent years as the demands of safety and reliability, as well as economic competition, have become stronger. The rapid advanced of computer hardware and software technology in the last two decades has greatly enlarged the potential of computer applications to plant instrumentation and control of future plants, as well as those needed for operation of existing plants. The traditional role of computers for mathematical calculations and data manipulation has been expanded to automate plant control functions and to enhance human performance and productivity. The major goals of using computers for instrumentation and control of nuclear power plants are: (1) to improve safety; (2) to reduce challenges to capital investments; (3) to reduce the cost of operations and maintenance; (4) to enhance power production; and (5) to increase productivity of people. Many functions in nuclear power plants are achieved by a combination of human action and automation. Increasingly, computer-based systems are used to support operations and maintenance personnel in the performance of their tasks. There are many benefits which can accrue from the use of computers but it is important to ensure that the design and implementation of the support system, and the human task places the human in the correct role in the relation to the machine; that is, in a management position, with the computer serving the human. In addition, consideration must be given to computer system integrity, software validation and verification, consequences of error, etc., to ensure its reliability for nuclear power plant applications. (author). 31 refs

  11. Tangible interfaces for virtual nuclear power plant control desk

    Energy Technology Data Exchange (ETDEWEB)

    Aghina, Mauricio Alves C.; Mol, Antonio Carlos A.; Jorge, Carlos Alexandre F.; Lapa, Celso M.F. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Nomiya, Diogo [Engenharia Eletrica (UFRJ), Universidade Federal do Rio de Janeiro, RJ (Brazil); Cunha, Gerson G.; Landau, Luiz [Programa de Engenharia Civil (PEC/COPPE/UFRJ), Universidade Federal do Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Due to the high safety requirements for nuclear power plant operation, control desks must be designed in such a way operators can take all the procedures safely, with a good overview of all variable indicators and easy access to actuator controls. Also, operators must see alarms indication in a way they can easily identify any abnormal conditions and bring the NPP back to normal operation. The ergonomics and human factors fields have helped evaluations to improve the design of nuclear power plant control systems. Lately, the use of virtual control desks have helped even more such evaluations, by integrating in one platform both nuclear power plant dynamics simulator with a high visual fidelity control desk proto typing. Operators can interact with these virtual control desks in a similar way as with real ones. Such a virtual control desk has been under development at Instituto de Engenharia Nuclear, IEN/CNEN. This paper reports the latest improvements, with the use of more interaction modes, to turn operation a friendlier task. An automatic speech recognition interface has been implemented as a self-contained system, by accessing directly MS Windows Application Interface, and with online neural network training for spoken commend recognition. Thus, operators can switch among different desk views. Besides this, head tracking interfaces have been integrated with the virtual control desk, to move within desk views according to users head movements. Both marker and markerless-based head tracking interfaces have been implemented. Results are shown and commented. (author)

  12. Tangible interfaces for virtual nuclear power plant control desk

    International Nuclear Information System (INIS)

    Aghina, Mauricio Alves C.; Mol, Antonio Carlos A.; Jorge, Carlos Alexandre F.; Lapa, Celso M.F.; Nomiya, Diogo; Cunha, Gerson G.; Landau, Luiz

    2011-01-01

    Due to the high safety requirements for nuclear power plant operation, control desks must be designed in such a way operators can take all the procedures safely, with a good overview of all variable indicators and easy access to actuator controls. Also, operators must see alarms indication in a way they can easily identify any abnormal conditions and bring the NPP back to normal operation. The ergonomics and human factors fields have helped evaluations to improve the design of nuclear power plant control systems. Lately, the use of virtual control desks have helped even more such evaluations, by integrating in one platform both nuclear power plant dynamics simulator with a high visual fidelity control desk proto typing. Operators can interact with these virtual control desks in a similar way as with real ones. Such a virtual control desk has been under development at Instituto de Engenharia Nuclear, IEN/CNEN. This paper reports the latest improvements, with the use of more interaction modes, to turn operation a friendlier task. An automatic speech recognition interface has been implemented as a self-contained system, by accessing directly MS Windows Application Interface, and with online neural network training for spoken commend recognition. Thus, operators can switch among different desk views. Besides this, head tracking interfaces have been integrated with the virtual control desk, to move within desk views according to users head movements. Both marker and markerless-based head tracking interfaces have been implemented. Results are shown and commented. (author)

  13. Control system for nuclear power plant

    International Nuclear Information System (INIS)

    Sato, Takahisa; Kawahara, Haruo.

    1979-01-01

    Purpose: To save man power and improve operation reliability by enabling automatic selection and operation of control rods from a central processing unit by the input operation of an operator. Constitution: An input operation for the control information corresponding to the running conditions such as operation sequence of control rods and loading-unloading positions is effected using a light pen or the like on a CRT display device. The signal from the light pen is supplied by way of the CRT control device to the input of a central processing unit and the control rod selection signal and the load-unload signal are supplied to the input of a control rod driving circuit. A control signal is sent out from the above circuit so as to enable the same operation as set by the operator, whereby the control rod is driven. The control rod is displaced on the cathode ray tube. (Furukawa, Y.)

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

    International Nuclear Information System (INIS)

    1983-01-01

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

  15. Robust control technique for nuclear power plants

    International Nuclear Information System (INIS)

    Murphy, G.V.; Bailey, J.M.

    1989-03-01

    This report summarizes the linear quadratic Guassian (LQG) design technique with loop transfer recovery (LQG/LTR) for design of control systems. The concepts of return ratio, return difference, inverse return difference, and singular values are summarized. The LQG/LTR design technique allows the synthesis of a robust control system. To illustrate the LQG/LTR technique, a linearized model of a simple process has been chosen. The process has three state variables, one input, and one output. Three control system design methods are compared: LQG, LQG/LTR, and a proportional plus integral controller (PI). 7 refs., 20 figs., 6 tabs

  16. Position control of a floating nuclear power plant

    International Nuclear Information System (INIS)

    Motohashi, K.; Hamamoto, T.; Sasaki, R.; Kojima, M.

    1993-01-01

    In spite of the increasing demand of electricity in Japan, the sites of nuclear power plants suitable for conventional seismic regulations become severely limited. Under these circumstances, several types of advanced siting technology have been developed. Among them, floating power plants have a great advantage of seismic isolation that leads to the seismic design standardization and factory fabrication. The feasibility studies or preliminary designs of floating power plants enclosed by breakwaters in the shallow sea have been carried out last two decades in U.S. and Japan. On the other hand, there are few investigations on the dynamic behavior of floating power plants in the deep sea. The offshore floating nuclear power plants have an additional advantage in that large breakwaters are not required, although the safety checking is inevitable against wind-induced waves. The tension-leg platforms which have been constructed for oil drilling in the deep sea seem to be a promising offshore siting technology of nuclear power plants. The tension-leg mooring system can considerably restrain the heave and pitch of a floating power plant because of significant stiffness in the vertical direction. Different from seismic effects, wind-induced waves may be predicted in advance by making use of ocean weather forecasts using artificial satellites. According to the wave prediction, the position of the floating plant may be controlled by adjusting the water content in ballast tanks and the length of tension-legs before the expected load arrives. The position control system can reduce the wave force acting on the plant and to avoid the unfavorable response behavior of the plant. In this study a semi-submerged circular cylinder with tension-legs is considered as a mathematical model. The configuration of circular cylinder is effective because the dynamic behavior does not depend on incident wave directions. It is also unique in that it can obtain the closed-form solution of

  17. Control rooms in German nuclear power plants

    International Nuclear Information System (INIS)

    Hoffmann, E.

    1999-01-01

    The paper explains and illustrates the dissimilarity in design and equipment of control rooms in German NPPs, as well as a historical survey of the general principles and approaches applied in the evolution of control room technology, including backfitting activities. Experience obtained from daily operation as well training at the simulators is taken as a basis to formulate fundamental requirements for modification or novel design approaches. (orig./CB) [de

  18. Control room habitability in Spanish Nuclear Power Plants

    International Nuclear Information System (INIS)

    Mediavilla, F.; Sierra, J. J.

    2007-01-01

    Since the NRC published in 2003 the Generic Letter 2003-01 Control room Habitability and the Regulatory guide 1.197 Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors, where it is emphasized the importance of verifying the control room habitability by means of alternative methods, Spanish Nuclear Power Plants are undertaking the different necessary activities to fulfill the requirements of the regulatory commission. This paper describes the main mechanisms included in NEI 99-03 Nuclear Energy Institute publication Control room Habitability Assessment guidance, to demonstrate and maintain Control room Habitability. In addition, in this article it Ds shown the theoretical principle of the test used to quantify air in-leakage in a control room envelope by using tracer gas techniques. The necessary activities to perform the initial in leakage testing are also put forward. Since 2006 Tecnatom, S. A. has performed the baseline testing in four Spanish Units, all of them with successful results. The rest of the Plants are scheduled to perform the tests during the second half of this year. Finally, this document summarises the more important aspects to be taken into account in the development of control room Habitability Programs, which are expected to ensure the integral maintenance of the Control room Envelope during the life a plant. (Author)

  19. Reactor control device for controlling load of nuclear power plant

    International Nuclear Information System (INIS)

    Hirota, Tadakuni; Yokoyama, Terukuni; Masuda, Jiro.

    1981-01-01

    Purpose: To improve the load follow-up capacity of a nuclear reactor by automatically controlling the width of the not-sensing band of a control rod inserting and removing discriminator circuit. Constitution: When load control operations such as automatic load control, automatic frequency control, governor free operation and so forth are conducted, the width of a not sensing band of a control rod inserting and removing discriminator circuit is ao automatically controlled that the not sensing band width may return to ordinary value in a normal operation by avoiding the fast repetition of inserting and removing control rods by increasing the width of the insensing band if the period of a control deviation signal produced due to the variation in the load is quickly repeated and varied in correspondence to the control deviation signal. That is, a circuit for varying the insensing band of the control circuit for driving a control mechanism is provided to reduce the amount of driving the control rods in a load control operation and to reduce the strain of the power distribution of the nuclear reactor, thereby improving the load control capacity. (Yoshihara, H.)

  20. The computerized radiation control system for the nuclear power plant

    International Nuclear Information System (INIS)

    Hunamoto, H.; Sato, T.; Taniguchi, K.

    1993-01-01

    Major works of Radiation control in nuclear power plant consist of occupational exposure control, radiation monitoring of working areas and surveillance of monitoring equipment, environmental monitoring and so on. Since a large amount of data will be generated from these works, therefore use of high performance computers will be indispensable. The systematization is presently being advanced in The Japan Atomic Power Company from this viewpoint and the project is being realized smoothly. The actual state is introduced

  1. Design of a Load Following Controller for APR+ Nuclear Plants

    International Nuclear Information System (INIS)

    Lee, Sim Won; Kim, Jae Hwan; Kim, Dong Su; Na, Man Gyun; Yu, Keuk Jong

    2011-01-01

    The load-following operation of an APR+ nuclear plants is required to restrain the adjustment of boric acid concentration and to efficiently control the control rods for the flexibility of the operation. Especially, axial flux distribution disproportion that is usually caused by load-following operation in a reactor core induces xenon oscillation because the absorption cross-section of xenon is extremely large and its effects in a reactor are delayed by the iodine precursor. Rapid and smooth power maneuvering has its benefits in view of the economical and safe operation of reactors, so it is required that the controller is efficiently designed. Therefore, the load-following operation of an APR+ nuclear plants needs the ultimate automatic control and the advanced control method that satisfies the conditions such as the flexibility, safety and convenience. A model predictive control (MPC) method is applied to design an automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control for an APR+ nuclear plants. Some tracking controllers use only the current tracking command. On the other hand, since MPC considers future commands in addition to the current tracking command, the MPC can achieve better tracking performance. Therefore, the MPC has been applied very much to the control of industrial process systems. The basic concept of the MPC is to solve an optimization problem for generating finite future control inputs at current time and to implement as the current control input only the first control input among the solutions of the finite time steps. At the next time step, the second control input is not implemented and the procedure to solve the optimization problem is then repeated. The power level and the ASI are controlled by the regulating control banks and part-strength control banks together with the automatic adjustment of boric acid concentration. The 3-dimensional MASTER code, which models the APR+ nuclear

  2. Design of a Load Following Controller for APR+ Nuclear Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sim Won; Kim, Jae Hwan; Kim, Dong Su; Na, Man Gyun [Chosun University, Gwnagju (Korea, Republic of); Yu, Keuk Jong [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2011-08-15

    The load-following operation of an APR+ nuclear plants is required to restrain the adjustment of boric acid concentration and to efficiently control the control rods for the flexibility of the operation. Especially, axial flux distribution disproportion that is usually caused by load-following operation in a reactor core induces xenon oscillation because the absorption cross-section of xenon is extremely large and its effects in a reactor are delayed by the iodine precursor. Rapid and smooth power maneuvering has its benefits in view of the economical and safe operation of reactors, so it is required that the controller is efficiently designed. Therefore, the load-following operation of an APR+ nuclear plants needs the ultimate automatic control and the advanced control method that satisfies the conditions such as the flexibility, safety and convenience. A model predictive control (MPC) method is applied to design an automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control for an APR+ nuclear plants. Some tracking controllers use only the current tracking command. On the other hand, since MPC considers future commands in addition to the current tracking command, the MPC can achieve better tracking performance. Therefore, the MPC has been applied very much to the control of industrial process systems. The basic concept of the MPC is to solve an optimization problem for generating finite future control inputs at current time and to implement as the current control input only the first control input among the solutions of the finite time steps. At the next time step, the second control input is not implemented and the procedure to solve the optimization problem is then repeated. The power level and the ASI are controlled by the regulating control banks and part-strength control banks together with the automatic adjustment of boric acid concentration. The 3-dimensional MASTER code, which models the APR+ nuclear

  3. Distributed Control Systems in New Nuclear Power Plants

    International Nuclear Information System (INIS)

    Doerfler, Joseph

    2008-01-01

    With the growing demand for energy many countries have expressed interest in constructing new plants over the next 15 to 20 years. These expectations have presented a challenge to the nuclear industry to provide a high volume of construction. A key strategy to meet this challenge is developing an advanced nuclear power plant design that allows for a modular construction, a high level of standardization, passive safety features, reduced number of components, and a short bid-to-build time. In addition, the implementation of the plant control system has evolved as new technologies emerge to support these goals. The purpose of this paper is to discuss the ways that the distributed control and information systems in the new generation of nuclear power plants will differ from those currently in service. The new designs provide opportunities to improve overall performance through the use of bus technology, a video display driven Human System Interface, enhanced diagnostics and improved maintenance features. However, the new technologies must fully address requirements for cyber security and high reliability. This paper will give an overview of new technology, improvements, as well as emerging issues in new plant design. (authors)

  4. Distributed Control Systems in New Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Doerfler, Joseph [Westinghouse Electric Company, 4350 Northern Pike, Monroeville, PA 15146 (United States)

    2008-07-01

    With the growing demand for energy many countries have expressed interest in constructing new plants over the next 15 to 20 years. These expectations have presented a challenge to the nuclear industry to provide a high volume of construction. A key strategy to meet this challenge is developing an advanced nuclear power plant design that allows for a modular construction, a high level of standardization, passive safety features, reduced number of components, and a short bid-to-build time. In addition, the implementation of the plant control system has evolved as new technologies emerge to support these goals. The purpose of this paper is to discuss the ways that the distributed control and information systems in the new generation of nuclear power plants will differ from those currently in service. The new designs provide opportunities to improve overall performance through the use of bus technology, a video display driven Human System Interface, enhanced diagnostics and improved maintenance features. However, the new technologies must fully address requirements for cyber security and high reliability. This paper will give an overview of new technology, improvements, as well as emerging issues in new plant design. (authors)

  5. Control room systems design for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This publication provides a resource for those who are involved in researching, managing, conceptualizing, designing, manufacturing or backfitting power plant control room systems. It will also be useful to those responsible for performing reviews or evaluations of the design and facilities associated with existing power plant control room systems. The ultimate worth of the publication, however, will depend upon how well it can support its users. Readers are invited to provide comments and observations to the IAEA, Division of Nuclear Power. If appropriate, the report will subsequently be re-issued, taking such feedback into account. Refs, figs and tabs.

  6. Control room systems design for nuclear power plants

    International Nuclear Information System (INIS)

    1995-07-01

    This publication provides a resource for those who are involved in researching, managing, conceptualizing, designing, manufacturing or backfitting power plant control room systems. It will also be useful to those responsible for performing reviews or evaluations of the design and facilities associated with existing power plant control room systems. The ultimate worth of the publication, however, will depend upon how well it can support its users. Readers are invited to provide comments and observations to the IAEA, Division of Nuclear Power. If appropriate, the report will subsequently be re-issued, taking such feedback into account. Refs, figs and tabs

  7. Automated control system for the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Labik, V.

    1990-01-01

    Instrumentation of the automated control system of the Temelin nuclear power plant in the section of the main production unit and of the major auxiliary equipment is described, the results of testing are reported, and the present status of design activities is assessed. The suitability of application of Czechoslovak automation facilities to the instrumentation of the automated control system of the power plant was confirmed by the Soviet designer and supplier based on favorable results of polygonal testing. Capacity problems in the development of the designs and user software are alleviated by extensive cooperation. It is envisaged that all tasks will be fulfilled as planned. (P.A.). 1 fig., 5 refs

  8. Advanced control room design for nuclear power plants

    International Nuclear Information System (INIS)

    Scarola, K.

    1987-01-01

    The power industry has seen a continuous growth of size and complexity of nuclear power plants. Accompanying these changes have been extensive regulatory requirements resulting in significant construction, operation and maintenance costs. In response to related concerns raised by industry members, Combustion Engineering developed the NUPLEX 80 Advanced Control Room. The goal of NUPLEX 80 TM is to: reduce design and construction costs; increase plant safety and availability through improvements in the man-machine interface; and reduce maintenance costs. This paper provides an overview of the NUPLEX 80 Advanced Control Room and explains how the stated goals are achieved. (author)

  9. Monitor and control device in a nuclear power plant

    International Nuclear Information System (INIS)

    Neda, Toshikatsu.

    1980-01-01

    Purpose: To facilitate and ensure monitor and control, as well as improve the operation efficiency and save man power, by render the operation automatic utilizing a process computer and centralizing the monitor and control functions. Constitution: All of the operations from the start up to stop in a nuclear power plant are conducted by way of a monitor and control board. The process data for the nuclear power plant are read into the process computer and displayed on a CRT display. Controls are carried out respectively for the control rod on a control rod panel, for the feedwater rate on a feedwater control panel, for the recycling flow rate on a recycling control panel and for the turbine generator on a turbine control panel. When the operation is conducted by an automatic console, operation signals from the console are imputted into the process computer and the state of the power plant is monitored and automatic operation is carried out based on the operation signals and from signals from each of the panels. (Moriyama, K.)

  10. Perception of tomorrow's nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Meyer, O.R.

    1986-01-01

    Major development programs are upgrading today's light water reactor nuclear power plant (NPP) control rooms. These programs involve displays, control panel architecture, procedures, staffing, and training, and are supported by analytical efforts to refine the definitions of the dynamics and the functional requirements of NPP operation. These programs demonstrate that the NPP control room is the visible command/control/communications center of the complex man/machine system that operates the plant. These development programs are primarily plant specific, although the owners' groups and the Institute of Nuclear Power Operations (INPO) do provide some standardization. The Idaho National Engineering Laboratory recently completed a project to categorize control room changes and estimate the degree of change. That project, plus related studies, provides the basis for this image of the next generation of NPP control rooms. The next generation of NPP control rooms is envisioned as being dominated by three current trends: (1) application of state-of-the-art computer hardware and software; (2) use of NPP dynamic analyses to provide the basis for the control room man/machine system design; and (3) application of empirical principles of human performance

  11. An expert display system and nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Beltracchi, L.

    1988-01-01

    An expert display system controls automatically the display of segments on a cathode ray tube's screen to form an image of plant operations. The image consists of an icon of: 1) the process (heat engine cycle), 2) plant control systems, and 3) safety systems. A set of data-driven, forward-chaining computer stored rules control the display of segments. As plant operation changes, measured plant data are processed through the rules, and the results control the deletion and addition of segments to the display format. The icon contains information needed by control rooms operators to monitor plant operations. One example of an expert display is illustrated for the operator's task of monitoring leakage from a safety valve in a steam line of a boiling water reactor (BWR). In another example, the use of an expert display to monitor plant operations during pre-trip, trip, and post-trip operations is discussed as a universal display. The viewpoints and opinions expressed herein are the author's personal ones, and they are not to be interpreted as Nuclear Regulatory Commission criteria, requirements, or guidelines

  12. Intelligent control system Cellular Robotics Approach to Nuclear Plant control and maintenance

    International Nuclear Information System (INIS)

    Fukuda, Toshio; Sekiyama, Kousuke; Xue Guoqing; Ueyama, Tsuyoshi.

    1994-01-01

    This paper presents the concept of Cellular Robotic System (CEBOT) and describe the strategy of a distributed sensing, control and planning as a Cellular Robotics Approach to the Nuclear Plant control and maintenance. Decentralized System is effective in large plant and The CEBOT possesses desirable features for realization of Nuclear Plant control and maintenance because of its flexibility and adaptability. Also, as related on going research work, self-organizing manipulator and communication issues are mentioned. (author)

  13. A minimum attention control center for nuclear power plants

    International Nuclear Information System (INIS)

    Meijer, C.H.

    1986-01-01

    Control Centers for Nuclear Power Plants have characteristically been designed for maximum attention by the operating staffs of these plants. Consequently, the monitoring, control and diagnostics oriented cognitive activities by these staffs, were mostly ''data-driven'' in nature. This paper addresses a control center concept, under development by Combustion Engineering, that promotes a more ''information-driven'' cognitive interaction process between the operator and the plant. The more ''intelligent'' and therefore less attentive nature of such interactive process utilizes computer implemented cognitive engineered algorithms. The underlying structure of these algorithms is based upon the Critical Function/Success Path monitoring principle. The paper highlights a typical implementation of the minimum attention concept for the handling of unfamiliar safety related events. (author)

  14. Fuzzy control applied to nuclear power plant pressurizer system

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Mauro V.; Almeida, Jose C.S., E-mail: mvitor@ien.gov.b, E-mail: jcsa@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    In a pressurized water reactor (PWR) nuclear power plants (NPPs) the pressure control in the primary loop is very important for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes, during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study has two main goals: first is to develop a pressurizer model based on artificial neural networks (ANNs); second is to develop a fuzzy controller for the PWR pressurizer pressure, and compare its performance with the P controller. Data from a simulator PWR plant was used to test the ANN and the controllers as well. The reference simulator is a Westinghouse 3-loop PWR plant with a total thermal output of 2785 MWth. The simulation results show that the pressurizer ANN model response are in reasonable agreement with the simulated power plant, and the fuzzy controller built in this study has better performance compared to the P controller. (author)

  15. Fuzzy control applied to nuclear power plant pressurizer system

    International Nuclear Information System (INIS)

    Oliveira, Mauro V.; Almeida, Jose C.S.

    2011-01-01

    In a pressurized water reactor (PWR) nuclear power plants (NPPs) the pressure control in the primary loop is very important for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes, during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study has two main goals: first is to develop a pressurizer model based on artificial neural networks (ANNs); second is to develop a fuzzy controller for the PWR pressurizer pressure, and compare its performance with the P controller. Data from a simulator PWR plant was used to test the ANN and the controllers as well. The reference simulator is a Westinghouse 3-loop PWR plant with a total thermal output of 2785 MWth. The simulation results show that the pressurizer ANN model response are in reasonable agreement with the simulated power plant, and the fuzzy controller built in this study has better performance compared to the P controller. (author)

  16. Nuclear power plant control room operators' performance research

    International Nuclear Information System (INIS)

    Gray, L.H.; Haas, P.M.

    1984-01-01

    A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator capabilities, of procedures and data for specifying and verifying simulator performance, and of methods and applications of task analysis

  17. Communications involving the control room of a nuclear power plant

    International Nuclear Information System (INIS)

    MacGregor, J.; Cunningham, B.; Safayeni, F.; Duimering, R.

    1992-04-01

    This study investigated communications within the operations component of a nuclear power plant, with a primary emphasis on control room communications. A structured interview technique was developed following preliminary interviews at the plant, and pretested at AECB headquarters. Patterns were identified from questions asked on communications links, work relationships, miscommunications, procedures, instrumentation and responses to problems. The study was an exploratory one, conducted under a limited budget, to provide background information and to identify areas for further investigation. The report offers recommendations about areas for further research

  18. Safety implications of computerized process control in nuclear power plants

    International Nuclear Information System (INIS)

    1991-02-01

    Modern nuclear power plants are making increasing use of computerized process control because of the number of potential benefits that accrue. This practice not only applies to new plants but also to those in operation. Here, the replacement of both conventional process control systems and outdated computerized systems is seen to be of benefit. Whilst this contribution is obviously of great importance to the viability of nuclear electricity generation, it must be recognized that there are major safety concerns in taking this route. However, there is the potential for enhancing the safety of nuclear power plants if the full power of microcomputers and the associated electronics is applied correctly through well designed, engineered, installed and maintained systems. It is essential that areas where safety can be improved be identified and that the pitfalls are clearly marked so that they can be avoided. The deliberations of this Technical Committee Meeting are a step on the road to this goal of improved safety through computerized process control. This report also contains the papers presented at the technical committee meeting by participants. A separate abstract was prepared for each of these 15 presentations. Refs, figs and tabs

  19. Control and data processing systems in UK nuclear power plant and nuclear facilities

    International Nuclear Information System (INIS)

    Baldwin, J.A.; Wall, D.N.

    1997-01-01

    This note identifies some of the data processing and control systems in UK nuclear power plant, with emphasis on direct digital control systems and sequence control. A brief indication is also given of some of the associated research activities on control systems and software. (author). 2 figs

  20. Control and data processing systems in UK nuclear power plant and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Baldwin, J A; Wall, D N [AEA Technology, Winfrith, Dorchester (United Kingdom)

    1997-07-01

    This note identifies some of the data processing and control systems in UK nuclear power plant, with emphasis on direct digital control systems and sequence control. A brief indication is also given of some of the associated research activities on control systems and software. (author). 2 figs.

  1. Malaysian Preparation for Nuclear Power Plant Instrumentation and Control System

    International Nuclear Information System (INIS)

    Mohd Idris Taib; Nurfarhana Ayuni Joha; Kamarudin Sulaiman; Izhar Abu Hussin

    2011-01-01

    Instrumentation and Control System is required in Nuclear Power Plant for their safe and effective operation. The system is combination and integrated from detectors, actuators, analog system as well as digital system. Current design of system definitely follows of electronic as well as computer technology, with strictly follow regulation and guideline from local regulator as well as International Atomic Energy Agency. Commercial Off-The-Shelf products are extensively used with specific nucleonic instrumentation. Malaysian experiences depend on Reactor TRIGA PUSPATI Instrumentation and Control, Power Plant Instrumentation and Control as well as Process Control System. However Malaysians have capabilities to upgrade themself from Electronics, Computers, Electrical and Mechanical based. Proposal is presented for Malaysian preparation. (author)

  2. Fact sheet on nuclear power plant instrumentation and control technologies

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear power plants (NPPs) are facing challenges in several instrumentation and control (I and C) areas with ageing and obsolete components and equipment. With license renewals and power uprates, the long-term operation and maintenance of obsolete I and C systems may not be a cost-effective and reliable option. The effort needed to maintain or increase the reliability and useful life of existing I and C systems may be greater in the long run than modernizing I and C systems or replacing them completely with new digital systems. The increased functionality of the new I and C systems can also open up new possibilities to better support the operation and maintenance activities in the plant. The IAEA recognizes the importance of the profound role the I and C systems play in the reliable, safe, efficient, and cost-effective operations of NPPs by supporting the activities of the Department of Nuclear Energy's Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI). The group was established in March 1970. Its membership currently includes thirty Member States and three international organizations. The most recent meeting of the TWG-NPPCI was held in May 2005 in Vienna. The meeting report is available at http://www.iaea.org/OurWork/ST/NE/NENP/twg_nppc.html. The next meeting of the TWGNPPCI will be the 21st meeting of the advisory body, and it will be held in May 2007

  3. Inventory Control of Spare Parts for Operating Nuclear Power plants

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong-Hyuck; Jang, Se-Jin; Hwang, Eui-Youp; Yoo, Sung-Soo; Yoo, Keun-Bae; Lee, Sang-Guk; Hong, Sung-Yull [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    Inventory control of spare parts plays an increasingly important role in operation management. The trade-off is clear: on one hand a large number of spare parts ties up a large amount of capital, while on the other hand too little inventory may result in extremely costly emergency actions. This is why during the last few decades inventory of spare parts control has been the topics of many publications. Recently management systems such as manufacturing resources planning (MRP) and enterprise resource planning (ERP) have been added. However, most of these contributions have similar theoretical background. This means the concepts and techniques are mainly based on mathematical assumptions and modeling inventory of spare parts situations Nuclear utilities in Korea have several problems to manage the optimum level of spare parts though they used MRP System. Because most of items have long lead time and they are imported from United States, Canada, France and so on. In this paper, we will examine the available inventory optimization models which are applicable to nuclear power plant and then select optimum model and assumptions to make inventory of spare parts strategies. Then we develop the computer program to select and determine optimum level of spare parts which should be automatically controlled by KHNP ERP system. The main contribution of this paper is an inventory of spare parts control model development, which can be applied to nuclear power plants in Korea.

  4. Inventory Control of Spare Parts for Operating Nuclear Power plants

    International Nuclear Information System (INIS)

    Park, Jong-Hyuck; Jang, Se-Jin; Hwang, Eui-Youp; Yoo, Sung-Soo; Yoo, Keun-Bae; Lee, Sang-Guk; Hong, Sung-Yull

    2006-01-01

    Inventory control of spare parts plays an increasingly important role in operation management. The trade-off is clear: on one hand a large number of spare parts ties up a large amount of capital, while on the other hand too little inventory may result in extremely costly emergency actions. This is why during the last few decades inventory of spare parts control has been the topics of many publications. Recently management systems such as manufacturing resources planning (MRP) and enterprise resource planning (ERP) have been added. However, most of these contributions have similar theoretical background. This means the concepts and techniques are mainly based on mathematical assumptions and modeling inventory of spare parts situations Nuclear utilities in Korea have several problems to manage the optimum level of spare parts though they used MRP System. Because most of items have long lead time and they are imported from United States, Canada, France and so on. In this paper, we will examine the available inventory optimization models which are applicable to nuclear power plant and then select optimum model and assumptions to make inventory of spare parts strategies. Then we develop the computer program to select and determine optimum level of spare parts which should be automatically controlled by KHNP ERP system. The main contribution of this paper is an inventory of spare parts control model development, which can be applied to nuclear power plants in Korea

  5. Nuclear power plant control and instrumentation 1993. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    The regular meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) was organized in order to summarize operating experience of nuclear power plant control systems, gain a general overview of activities in development of modern control systems and receive recommendations on the further directions and particular measures within the Agency's programme. The meeting was held at the Merlin-Gerin Headquarters in Paris and was attended by twenty one national delegates and observers from 17 countries. The present volume contains: (1) report on the meeting of the IWG-NPPCI, Paris, 21-22 October 1993, (2) report by the scientific secretary on the major activities of IAEA during 1991-1993 in the NPPCI area, and (3) reports of the national representatives to the International Working Group on NPPCI. The papers and discussions with practical experience and described actual problems encountered. Emphasis was placed on the technical, industrial and economic aspects of the introduction of modern control systems and on the improvement of plant availability and safety. Refs, figs and tabs

  6. Changes in control room at Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Kecklund, Lena

    2005-09-01

    The Swedish nuclear power plants were commissioned during a period between 1972 and 1985 and the instrumentation and control equipment are basically from that period. For several years there have been plans made for changes in all the nuclear power plants and to a certain extent the changes in control equipment and monitoring rooms have also been implemented. The object of this project was to make a comprehensive review of the changes in control room design implemented in the Swedish nuclear power plants and to describe how the MTO- (Man-Technology-Organisation) and (Man-Machine-Interface) -issues have been integrated in the process. The survey is intended to give an overall picture of the changes in control room design and man-machine-interface made in the Swedish control rooms, in order to get a deeper knowledge of the change management process and its results as well as of the management of MTO-issues in these projects. The units included in this survey are: Oskarhamn reactor 2 and 3; Ringhals reactor 2, 3 and 4; Forsmark reactor 1, 2 and 3. The Oskarshamn 1 unit has not been included in this report as it has recently undergone an extensive modernisation program as well as a detailed inspection by the SKI (Swedish Nuclear Power Inspectorate). At Ringhals 2 the modernisation work is carried out at present and the unit is also subjected to extensive inspection activities carried out by SKI and is therefore not part of this survey. This report also includes a short description of relevant standards and requirements. Then follows a presentation of the results of the plant survey, presented as case studies for three companies OKG, Ringhals and FKA. Control room changes are summarized as well as the results on specific MTO issues which has been surveyed. In all the power companies there is a joint way of working with projects concerning plant modifications. This process is described for each company separately. In the concluding of the report the strengths and

  7. Toward risk-based control of nuclear power plant configurations

    International Nuclear Information System (INIS)

    Samanta, P.K.; Veseley, W.E.; Kim, I.S.

    1992-01-01

    This paper presents an evaluation of the configuration risks associated with the operation of a nuclear power plant and the approaches to control these risks using risk-based configuration control considerations. In that context, the actual and maximum potential configuration risks at a plant are analyzed and the alternative types criteria for a risk-based configuration control systems are described. The risk-based configuration calculations which are studied here focus on the core-melt frequency impacts from given plant configurations, the configurations which cause large core-melt frequency increases can be identified and controlled. The duration time in which the configuration can exist can then be limited or the core-melt frequency level associated with the configuration can be reduced by various actions. Futhermore, maintenances and tests can be scheduled to avoid the configurations which cause large core-melt frequency increases. Present technical specifications do not control many of these configurations which can cause large core-melt frequency increases but instead focus on many risk-unimportant allowed outage times. Hence, risk-based configuration management can be effectively used to reduce core-melt frequency associated risks at a plant and at the same time can provide flexibility in plant operation. The alternative strategies for controlling the core-melt frequency and other risk contributions include: (1) controlling the increased risk level which is associated with the configuration; (2) controlling the individual configuration risk which is associated with a given duration of a configuration; (3) controlling the time period configuration risk from configurations which occur in a time period. (orig.)

  8. Experience feedback of computerized controlled nuclear power plants

    International Nuclear Information System (INIS)

    Poizat, F.

    2004-01-01

    The N4 step of French PWR-type nuclear power plants is characterized by an instrumentation and control system entirely computerized (operation procedures including normal and accidental operation). Four power plants of this type (Chooz and Civaux sites) of 1450 MWe each were connected to the power grid between August 1996 and December 1999. The achievement of this program make it possible and necessary to carry out an experience feedback about the development, successes and difficulties encountered in order to draw out some lessons for future realizations. This is the aim of this article: 1 - usefulness and difficulties of such an experience feedback: evolution of instrumentation and control systems, necessary cautions; 2 - a successful computerized control: checking of systems operation, advantages, expectations; 3 - efficiency of computerized systems: demonstration of operation safety, profitability; 4 - conclusions and interrogations: system approach instead of 'micro-software' approach, commercial or 'made to measure' products, contract agreement with a supplier, when and how upgrading. (J.S.)

  9. Report on nuclear power plant instrumentation and control in Germany

    International Nuclear Information System (INIS)

    Bastl, W.

    1992-01-01

    The paper describes the status of the NPP control and instrumentation in Germany. The general technology underlying most aspects of NPP C and I in Germany has not altered since the last progress report although there has been many improvements in detail. Since the beginning of 1990 the GRS carried out the safety investigations of NPPs in East Germany. The USSR as the vendor of the plants and France were also involved in the project. The following fields are briefly described: Status of nuclear power in Germany; training simulators; backfitting of computers and information systems; operator support/new control rooms. (author). 6 refs, 1 tab

  10. Advanced instrumentation and control techniques for nuclear power plants

    International Nuclear Information System (INIS)

    Hayakawa, Hiroyasu; Makino, Maomi

    1989-01-01

    Toshiba has been promoting the development and improvement of control and instrumentation (C and I) systems employing the latest technologies, to fulfill the requirements of nuclear power plants for increased reliability, the upgrading of functions, improved maintainability, and reasonable cost. Such development has been systematically performed based on a schematic view of integrated digital control and instrumentation systems, actively adopting state-of-the-art techniques such as the latest man-machine interfaces, digital and optical multiplexing techniques, and artificial intelligence. In addition, comprehensive feedback has been obtained from the accumulation of operating experience. This paper describes the purpose, contents and status of applications of representative newly-developed systems. (author)

  11. Nuclear techniques in plant pathology 1. Plant disease control and physiology of parasitism

    International Nuclear Information System (INIS)

    Menten, J.O.M.; Ando, A.; Tulmann Neto, A.

    1986-01-01

    Nuclear techniques are advantageously used in several areas of plant pathology. Among them are: induction of mutation for disease resistance, studies with pesticides, disease control through pathogen inactivation, induction of variability and stimulation in pathogens and natural enemies, studies of microorganism physiology and diseased plant physiology, effect of gamma radiation on pesticides, technology of pesticides application, etc. (Author) [pt

  12. Nuclear Power Plant Control and Instrumentation activities in Czechoslovakia

    International Nuclear Information System (INIS)

    Stirsky, P.; Karpeta, C.; Rubek, J.

    1990-01-01

    After giving a survey of the Czechoslovak nuclear power plants a description of I and C systems of the operating plants is presented together with a brief outlook for future developments to be implemented at plants which are under construction. Special attention is paid to the adopted techniques for power distribution investigation and control in the WWER 1000 reactor core in the case of load changes. Basic futures of the in-core measurement systems are outlined. Measures implemented in the I and C systems of the operating units to improve their performance are described. Information on the country's approach to NPP personnel training and training aids usage as well as information on development work in the area of surveillance and monitoring systems completes the paper. (author). 9 refs, 1 tab

  13. The Remotely Controlled Robot System for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Koh, Kwangill; Lee, Gwangnam; Lim, Kyeyoung

    1993-01-01

    The problem of radioactivity has been our major concern. So, it makes the needs of remotely controlled robot system necessary for maintenance and repair services. Up to now, several foreign companies have been contracted for the maintenance of the steam generators of nuclear power plants in Korea, to acquire its own capability of maintaining the steam generators of it impossible for Korea to acquire its own capability of maintaining the steam generators. In case of emergency, it is difficult to take appropriate steps on its own. In order to resolve the above problems, it seems inevitable to develop the robot system for the inspection and repair of steam generator. This project intends to acquire domestic capabilities of maintaining steam generators, so that this advanced skills could be applied to the related areas. As a result, it will save immense money in the future. the purposes of development of the remotely controlled robot system are : to perform the desired tasks at the polluted area without requiring entry of personnel. to closely inspect the steam generator U-tubes at high speed. to inspect the steam generator intelligently and efficiently under the extreme circumstances where radioactivity problem is very severe. to use for the repair of steam generator tube. Considering from the social and technical standpoint, we can say that the development of the remotely controlled robot system for nuclear power plants resulted in great achievements. From the social standpoint, it should be recognized that domestic robot for nuclear power plant was successfully developed and operator was protected against radioactivity. Also, we advanced our skills in the area of mechanical and control system design for an articulated robot. Using the robot controller in hierarchical structure, it was possible to control the robot remotely. In addition, resolver feedback typed A C servo drive was proven to be sturdy in hazardous environment. Now we are confident that our robot will

  14. 3D visualization based customer experiences of nuclear plant control room

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  15. NPAR approach to controlling aging in nuclear power plants

    International Nuclear Information System (INIS)

    Christensen, J.A.

    1990-01-01

    Aging degradation in nuclear power plants must be controlled to prevent safety margins from declining below limits provided in plant design bases. The NPAR Program and other aging-related programs conducted under the auspices of the Nuclear Regulatory Commission (NRC) Office of Research are developing needed technical guidance for control of aging. Results from these programs, together with relevant information developed by industry and elsewhere, are implemented through various ongoing NRC and industry programs and initiatives as well as by means of conventional regulatory instruments. The aging control process central to these efforts consists of three key elements: (1) selection of components, systems, and structures (CSS) in which aging must be controlled, (2) understanding of the mechanisms and rates of degradation in these CSS, and (3) managing degradation through effective surveillance and maintenance. These elements are addressed in Good Practices Guidance that integrates information developed under NPAR and other studies of aging into a systems-oriented format that tracks directly with the safety analysis reports

  16. Assessment of control rooms of nuclear power plants

    International Nuclear Information System (INIS)

    Norros, L.; Ranta, J.; Wahlstroem, B.

    1983-05-01

    To identify and correct the lacks in control rooms of operating power plants and plants under construction an extensive program has been started in the USA. In Finland as in other countries using nuclear power, the development in the USA particularly with regard to the requirements imposed on nuclear power plants is carefully followed. The changes in these requirements are sooner or later also reflected in the guidelines given by the Finnish authorities. It is therefore important to be able to form a notion of how the new requirements apply to Finnish conditions. Especially it is important to review the latest assessment guidelines for control room implementation (NUREG-0700). Thus we can avoid possible over hasty conclusions. The aim of the analysis of the method and experiments presented in NUREG 0700 report was to create a basis for assessment of the suitability of the method for Finnish control room implementation. The task group has made a general methodical analysis of the method, and partly tried it in assessment of the TVO2 control room. It is obvious that direct conclusions from the American situation are misleading. It can be considered unfeasible to follow the American requirements as such, because they can lead to unwanted results. If the review is limited to control room details, the NRC program (checklist) can be considered successful. It can also be used during planning to observation of small discrepancies. However, we can question the applicability of some requirements. It is, though, more essential that the control room entity has neither in this nor in several other programs been reached or standardized. In spite of the difficulties we should try to reach this most important goal. (author)

  17. Applications of modern control systems in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-10-01

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

  18. Applications of modern control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Wilhelm, H.

    1980-01-01

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

  19. Optimization of the control of contamination at nuclear power plants

    International Nuclear Information System (INIS)

    Khan, T.A.; Baum, J.W.

    1988-05-01

    A methodology is described for the optimization of the actions taken to control contamination. It deals with many aspects of contamination, such as the monetary value assigned to a unit of radiation dose, the treatment of skin and extremity dose, and the inefficiencies introduced from working in a contaminated environemnt. The optimization method is illustrated with two case studies based on cleanup projects at nuclear power plants. Guidelines for the use of protective apparel, and for monitoring radiation and contamination at various levels of contamination are presented. The report concludes that additional research is required to quantify the effect of a contaminated environment on work efficiencies

  20. Nuclear Power Plant Control and Instrumentation activities in Finland

    International Nuclear Information System (INIS)

    Haapanen, P.; Wahlstroem, B.

    1990-01-01

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

  1. A computerized diagnostic system for nuclear plant control rooms based on statistical quality control

    International Nuclear Information System (INIS)

    Heising, C.D.; Grenzebach, W.S.

    1990-01-01

    In engineering science, statistical quality control techniques have traditionally been applied to control manufacturing processes. An application to commercial nuclear power plant maintenance and control is presented that can greatly improve safety. As a demonstration of such an approach to plant maintenance and control, a specific system is analyzed: the reactor coolant pumps of the St. Lucie Unit 2 nuclear power plant located in Florida. A 30-day history of the four pumps prior to a plant shutdown caused by pump failure and a related fire within the containment was analyzed. Statistical quality control charts of recorded variables were constructed for each pump, which were shown to go out of statistical control many days before the plant trip. The analysis shows that statistical process control methods can be applied as an early warning system capable of identifying significant equipment problems well in advance of traditional control room alarm indicators

  2. Programmable logic controller (PLC) for safety systems of nuclear plants

    International Nuclear Information System (INIS)

    Sen, S.K.; Karmakar, G.; Joseph, Jose; Patil, R.K.

    2002-01-01

    Full text: A programmable logic controller (PLC) has been developed by RCnD, BARC for use in the safety critical systems in nuclear power plants. This PLC uses qualified hardware developed in RCnD for use in NPP. The programming software conforms to IEC-61131 part 3. The application programming is done on function block diagram (FBD) editor and the FBD is automatically converted into code in high level language (C / C++). This feature makes the application easily decipherable and therefore easily subjected to reviews and other validation techniques. The key to make quality software for use in nuclear systems is to enforce various standards in the design and development of the software, something, which is not possible to do with a commercially available PLC. This PLC with its software completely transparent lends itself to rigorous verification and validation easily

  3. Minimum critical power ratio control device for nuclear power plants

    International Nuclear Information System (INIS)

    Kurosawa, Tsuneo.

    1991-01-01

    Reactor core flowrate is determined by comparing a minimum critical power ratio calculated based on the status amount of a nuclear power plant and a control value for the minimum critical power ratio that depends on the reactor core flowrate. Further, the minimum critical power ratio and a control value for the minimum critical power ratio that depends on the reactor thermal power are compared to set a reactor thermal power converted to a reactor core flowrate. Deviation between the thus determined reactor core flowrate and the present reactor core flowrate is calculated. When the obtained deviation is lower than a rated value, a reactor core flowrate set signal is generated to a reactor flowrate control means, to control the reactor power by a recycling flowrate control system of the reactor. On the other hand, when the deviation exceeds the determined value, the reactor core flowrate set signal is converted into a reactor thermal power, to control the position of control rods and control the reactor power. Then, monitor and control can be conducted safely and automatically without depending on operator's individual ability over the entire operation range corresponding to load following operation. (N.H.)

  4. Water chemistry control in thermal and nuclear power plants. 9. Nuclear fuel management

    International Nuclear Information System (INIS)

    2008-01-01

    The chemical management of fuels in nuclear power plants aims at maintenance of the soundness of nuclear fuels and at reduction of the radiation exposure of the working employees. With regard to the former, particular attention should be paid to the fabrication process of fuel assembly, mainly for chemical management for fuel cladding tubes together with fuel pellet-clad chemical interactions, and to the outer tubes in the power plants. With regard to the latter, the fabrication process should be carefully controlled to prevent radioactive impurity increase in primary cooling water systems by maintaining cleaning level and decreasing surface contamination. Reactions of zircalloy with water or hydrogen forming ZrH 2 , sintered density of UO 2 pellet controlling water content, pellet-clad interactions, stress corrosion cracking, crud induced fuel failure, behaviors of such fission products as I, Xe, Kr, and Cs in plants are also important to water and chemical management of nuclear fuels. (S. Ohno)

  5. Advanced Instrumentation and control techniques for nuclear power plants

    International Nuclear Information System (INIS)

    Mori, Nobuyuki; Makino, Maomi; Naito, Norio

    1992-01-01

    Toshiba has been promoting the development of an advanced instrumentation and control system for nuclear power plants to fulfill the requirements for increased reliability, improved functionality and maintainability, and more competitive economic performance. This system integrates state-of-the-art technologies such as those for the latest man-machine interface, digital processing, optical multiplexing signal transmission, human engineering, and artificial intelligence. Such development has been systematically accomplished based on a schematic view of integrated digital control and instrumentation systems, and the development of whole systems has now been completed. This paper describes the purpose, design philosophy, and contents of newly developed systems, then considers the future trends of advanced man-machine systems. (author)

  6. Isolation valve control device for nuclear power plant

    International Nuclear Information System (INIS)

    Yukinori, Shigeru.

    1990-01-01

    The present invention provides an isolation valve control device for detecting pipeline rupture accidents in a BWR type nuclear power plant at an early stage to close an isolation valve thereby reducing the amout of radioactivity released to the circumstance. That is, isolation valves are disposed in the pipeline for each of the systems in the nuclear power plant and flow ratemeters are disposed to at least two positions in each of the pipelines. If a meaningful difference is shown for the measured values by these flow ratemeters, the isolation valve is closed. In this way, if pipeline rupture such as leak before break (LBB) is caused to a portion of a system pipelines, the measured value from the flow ratemeters at the downstream of the pipeline is lowered. Accordingly, when a meaningful difference is formed between the value of the flow ratematers at the upstream and the downstream, occurrence of pipe rutpture between both of the flow ratemeters can be detected. As a result, the isolation valves of the system can be closed. According to the present invention, it is possible to detect the pipeline rupture at an early stage irrespective of the kind of the systems, diameter of the pipelines and the magnitude of the ruptured area, and the isolation valve can be closed. (I.S.)

  7. Managing modernization of nuclear power plant instrumentation and control systems

    International Nuclear Information System (INIS)

    2004-02-01

    There are many reasons why I and C systems need to be modernized in nuclear power plants, including obsolescence, results of aging technology, failure rates, and the need for additional functionality and improved performance. For many plants, Instrumentation and Control (I and C) modernization will be one of the largest and most important activities over the next decade or longer. Modernization of I and C systems will represent a major capital investment for the plants in the future. Therefore, good and informed management to determine what needs to be modernized, how it should be modernized, and then to do the actual modernization is essential in order to minimize the costs and maximize the benefits. While many reports have discussed I and C modernization topics, one topic that needs more work is how to management I and C modernization projects efficiently. In order to have an efficient modernization project, it is essential that the plant does strategic planning to determine what needs to be done with I and C systems in the context of the overall plant goals, objectives, and commitments. This includes determining what features the the overall I and C, and control room, of the plant should look like at the end of the time period considered by the strategic planning effort, what systems need to be modernized, what systems can be maintained, the priority order of the systems to be modernized, how the systems should be modernized, and so on. To ensure that the individual I and C and control room modernization projects are done consistently with the strategic plan and the overall plant goals, objectives, and commitments, it is important that management establishes a set of plant specific guidelines and generic requirements and processes that the project will need to follow and that can be used as part of the requirements specifications for the new systems. High level management leadership and support is needed for I and C modernization in order to maintain the high

  8. Managing modernization of nuclear power plant instrumentation and control systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-02-01

    There are many reasons why I and C systems need to be modernized in nuclear power plants, including obsolescence, results of aging technology, failure rates, and the need for additional functionality and improved performance. For many plants, Instrumentation and Control (I and C) modernization will be one of the largest and most important activities over the next decade or longer. Modernization of I and C systems will represent a major capital investment for the plants in the future. Therefore, good and informed management to determine what needs to be modernized, how it should be modernized, and then to do the actual modernization is essential in order to minimize the costs and maximize the benefits. While many reports have discussed I and C modernization topics, one topic that needs more work is how to management I and C modernization projects efficiently. In order to have an efficient modernization project, it is essential that the plant does strategic planning to determine what needs to be done with I and C systems in the context of the overall plant goals, objectives, and commitments. This includes determining what features the the overall I and C, and control room, of the plant should look like at the end of the time period considered by the strategic planning effort, what systems need to be modernized, what systems can be maintained, the priority order of the systems to be modernized, how the systems should be modernized, and so on. To ensure that the individual I and C and control room modernization projects are done consistently with the strategic plan and the overall plant goals, objectives, and commitments, it is important that management establishes a set of plant specific guidelines and generic requirements and processes that the project will need to follow and that can be used as part of the requirements specifications for the new systems. High level management leadership and support is needed for I and C modernization in order to maintain the high

  9. Potential utilities of optimal estimation and control in nuclear power plants

    International Nuclear Information System (INIS)

    Tylee, J.L.; Purviance, J.E.

    1983-01-01

    Optimal estimation and control theories offer the potential for more precise control and diagnosis of nuclear power plants. The important element of these theories is that a mathematical plant model is used in conjunction with the actual plant data to optimize some performance criteria. These criteria involve important plant variables and incorporate a sense of the desired plant performance. Several applications of optimal estimation and control to nuclear systems are discussed

  10. Vibration control and monitoring in nuclear power plants

    International Nuclear Information System (INIS)

    Theodor, P.

    1989-01-01

    Nuclear Power Plants are operated with a computer system support. The computer system for a nuclear power plant is designed to reliably monitor plant parameters and perform a series of operations and calculations designed to allow increased plant operation efficiency. Rotating machinery surveillance methods for the recognition of damage are particularly important in Nuclear Power Plants. Deviation of the vibration behavior from normal conditions is an indicator of the development of incipient faults and can be reliably recognized by the use of vibration monitoring systems. Machinery Condition Monitoring is defined as a method or methods of surveillance designed to recognize changes from a norm and is also a warning or it initiates an automatic shutdown when the changes exceed limiting values or safety limits. This paper reports that it is important to distinguish between surveillance and diagnostics. Whereas the former is necessary for protection, the latter is not generally required until it becomes necessary to identify the source of a known anomaly

  11. Control room, emergency control system and local control panels in nuclear power plants

    International Nuclear Information System (INIS)

    1988-01-01

    The requirements on planning and construction of control boards including ergonomic-technical designing are specified in this rule. The specifications put the requirements on the design of place, process and environment of work, which are mentioned in the sections 90 and 91 of the labor-management relations act, into more concrete terms for the safety-relevant control panels as work places in a nuclear power station. The work places at control panels are not considered as video workstations in the sense of the 'Safety Rules for Video Workstations in the Office Sector' published by the General Association of the Industrial Trade Associations. The requirements are based on the operation and information technology realized at present in control panels of stationary nuclear power plants. (orig./HP) [de

  12. Water chemistry control of PWR nuclear power plant

    International Nuclear Information System (INIS)

    Hino, Yuichi; Makino, Ichiro; Yamauchi, Sumio; Fukuda, Fumihito.

    1992-01-01

    In PWR power plants, the primary system taking heat out of nuclear reactors and the secondary system generating steam and driving turbines are completely separated by steam generators, accordingly, by mutually independent water treatment, both systems are to be maintained in the optimal conditions. Namely, primary system is the closed water circulation circuit of simple liquid phase though under high temperature, high pressure condition, therefore, water shows the stable physical and chemical properties, and the minute water treatment for restraining the corrosion of structural materials and reducing radioactivity can be done. Secondary system is similar to the condensate and feedwater system of thermal power plants, and is the circuit for liquid-vapor two-phase transformation, but due to the local concentration of impurities by evaporation, the strict requirement is set for secondary water quality. However, secondary system can be treated in the state without radioactivity, and this is a great merit. The outline, basic concept and execution of primary water quality control, and the outline, concept, control criteria, facilities and execution of secondary water quality control are reported. (K.I.)

  13. Nonlinear Fuzzy Model Predictive Control for a PWR Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Xiangjie Liu

    2014-01-01

    Full Text Available Reliable power and temperature control in pressurized water reactor (PWR nuclear power plant is necessary to guarantee high efficiency and plant safety. Since the nuclear plants are quite nonlinear, the paper presents nonlinear fuzzy model predictive control (MPC, by incorporating the realistic constraints, to realize the plant optimization. T-S fuzzy modeling on nuclear power plant is utilized to approximate the nonlinear plant, based on which the nonlinear MPC controller is devised via parallel distributed compensation (PDC scheme in order to solve the nonlinear constraint optimization problem. Improved performance compared to the traditional PID controller for a TMI-type PWR is obtained in the simulation.

  14. Nuclear power and heating plant control rooms. I

    International Nuclear Information System (INIS)

    Malaniuk, B.

    1983-01-01

    The questions are discussed of memory capacity, vigilance, speed of data processing, decision-making quality and other demands placed on operators of nuclear power and heating plants. On the example of the accident at the Three Mile Island-2 nuclear power plant, the instants are shown when failure of the human factor owing to a stress situation resulted in the accident not being coped with in time. It is therefore necessary to place high demands on the choice of operators and to devote equal attention to the human factor as to the safety of the technical equipment of the power plant. (J.B.)

  15. Distributed control and instrumentation systems for future nuclear power plants

    International Nuclear Information System (INIS)

    Yan, G.; L'Archeveque, J.V.R.

    1976-01-01

    The centralized dual computer system philosophy has evolved as the key concept underlying the highly successful application of direct digital control in CANDU power reactors. After more than a decade, this basis philosophy bears re-examination in the light of advances in system concepts--notably distributed architectures. A number of related experimental programs, all aimed at exploring the prospects of applying distributed systems in Canadian nuclear power plants are discussed. It was realized from the outset that the successful application of distributed systems depends on the availability of a highly reliable, high capacity, low cost communications medium. Accordingly, an experimental facility has been established and experiments have been defined to address such problem areas as interprocess communications, distributed data base design and man/machine interfaces. The design of a first application to be installed at the NRU/NRX research reactors is progressing well

  16. Information Foraging in Nuclear Power Plant Control Rooms

    International Nuclear Information System (INIS)

    Boring, R.L.

    2011-01-01

    nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

  17. Information Foraging in Nuclear Power Plant Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    R.L. Boring

    2011-09-01

    nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

  18. Game-based training environment for nuclear plant control room

    International Nuclear Information System (INIS)

    Hung Tamin; Sun Tienlung; Yang Chihwei; Yang Lichen; Cheng Tsungchieh; Wang Jyhgang

    2011-01-01

    Nuclear power plant's safety is very important problem. In this very conscientious environment if operator has a little mistake, they may threaten with many people influence their safety. Therefore, operating training of control room is very important. However, the operator training is in limited space and time. Each operator must go to simulative control room do some training. If we can let each trainee having more time to do training and does not go to simulative control room. It may have some advantages for trainee. Moreover, in the traditional training ways, each operator may through the video, teaching manual or through the experienced instructor to learn the knowledge. This training way may let operator feel bored and stressful. So, in this paper aims, we hope utilizing virtual reality technology developing a game-based virtual training environment of control room. Finally, we will use presence questionnaire evaluating realism and feasibility of our virtual training environment. Expecting this initial concept of game-based virtual training environment can attract trainees having more learning motivation to do training in off-hour. (author)

  19. Report from the Netherlands [nuclear power plant control and instrumentation

    International Nuclear Information System (INIS)

    Plas, Y. van der

    2007-01-01

    A view is given on status and developments of NPP instrumentation and control related subjects in The Netherlands. Induced by a first periodic safety review NPP Borssele finalised an extensive upgrading programme in summer 1997. An additional optimisation in smaller parts of the I and C was completed in the 1998 outage. A second periodic safety review of Borssele was finished in 2004, concluding the plant applies to the current rules and regulations and to the state of the art. Nevertheless an improvement plan describing technical design and operational modifications by which nuclear safety has almost been finished now. The job was done in the long outage of autumn 2006 in combination with a turbine and turbine control upgrade. The latter led to a nett electric power output increase of around 7%. Also the HFR research reactor in Petten was subjected to an extensive first periodic safety review, leading to a new license. A major part of the resulting modification plan has been implemented now. Realisation of some safety enhancements in Petten are not easy and remained longer than expected in a stage of innovation. The electricity market was subjected to a liberalisation process. Production and transmission of electric energy has been separated. Electricity is produced now in a rather free market and many power plants have been sold to foreign investors. Only the Borssele power plants remained self- reliant in a period with a threat of closing. NPP Dodewaard is in decommissioning since 1997. It has been partially dismantled and entered a preservation period of 40 years. The radioactive waste storage organisation COVRA is further expanded for low radiating waste and also for storage of rest products from the Urenco enrichment facilities. This article concludes with mentioning some topics for IAEA's attention. (author)

  20. Bus-oriented digital control techniques in nuclear power plants

    International Nuclear Information System (INIS)

    Salm, M.

    1987-01-01

    The author states the conservative principles which govern the authorization procedures for nuclear reactor control systems. Using the example of a feedwater supply regulator, employing a digital, bus-oriented control system, he describes how the stigma attached to the word nuclear can be alleviated. (G.T.H.)

  1. Nuclear power plant control and instrumentation activities in Finland

    International Nuclear Information System (INIS)

    Haapanen, P.; Wahlstroem, B.

    1992-01-01

    Finland has remarkable achievements in nuclear power. The existing four plants have some of the best operating records in the world - high capacity factors, low occupational doses and short refuelling outages. Public opinion was strongly turned against nuclear power after Chernobyl accident, and the previous government decided not to allow for the construction of a fifth nuclear unit during its period of reign. The opposition has however slowly been diminishing. According to the latest polls the opinion is almost balanced. Finnish power companies are going to file an application for a decision-in-principle to build a new plant to the new government appointed in April 1991. A readiness to start new construction project immediately after a positive political decision is made has been maintained during the intermediate period. Continuous research, development, modification and upgrading work provide important components of the good operational history of the Finnish nuclear power plants. Efforts have also been devoted to identifying possible new problems arising from the use of distributed digital C and I technology. The following a short description is summarizing recent activities related to the C and I-systems of the nuclear power plants. (author). 3 tab

  2. Research on control function switch of nuclear power plant control room

    International Nuclear Information System (INIS)

    Mei Shibo; Mao Ting; Cheng Bo; Zhang Gang

    2014-01-01

    The nuclear power plant provides main control room (MCR) to the unit operators for the plant monitoring and control, and provides the remote shutdown station (RSS) as the back-up control room, which is used only when MCR is unavailable. The RSS could be used to monitor and control the plant, bring the plant into shutdown state and remove the residual heat. The command from MCR and RSS is blocked by each other and can not be executed at the same time. The operation mode switch function between MCR and RSS is carried out by MCR/RSS mode switches. The operation mode switch scheme of CPR1000, ERP and AP1000 were compared and researched, and some design bases for new nuclear power plant were submitted in this paper. These design bases could be referred during the design of control function switch for the new nuclear power plants, in order to put forward a more practical, simple, safe and convenient scheme. (authors)

  3. Jurisdictional control of administrative acts related to the safety of nuclear plants

    International Nuclear Information System (INIS)

    Fernandez Plasencia, S.

    1983-01-01

    This paper stresses the importance of jurisdictional control over nuclear power plants to ensure their safe operation. It also describes examples of case law concerning such plants in France, the Federal Republic of Germany, Italy and Spain. (NEA) [fr

  4. Status of radioiodine control for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Burger, L.L.; Scheele, R.D.

    1983-07-01

    This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used

  5. Upgrading instrumentation and control in nuclear power plants. Design criteria

    International Nuclear Information System (INIS)

    Rodriguez Rodriguez, M.C.; Alvarez Menendez, A.

    1997-01-01

    The use of programmed digital technology in Protection, Control, Monitoring and Information Systems in new generation nuclear power plants, or the use of this technology to replace or upgrade existing systems based on wired analog instrumentation and electromechanical relays, has led to new international standards which establish new design requirements or adapt existing requirements to this technology. Additionally, both regulatory organisations and the industry are discussing the reliability of this technology, regarding common mode failures that may occur in redundant protection channels, due to the use of equipment and software with the same characteristics. The first part of this paper addresses the most important aspects of new international standards regarding classification criteria for I and C systems, equipment and functions, depending on their importance to safety and the design criteria applicable to each category. Special attention is drawn to requirements concerning software quality assurance and the design of new control rooms. The paper then goes on to discuss the different technical solutions being implemented, using equipment and software diversification, in order to prevent the possibility of common mode failures affecting the protection function. (Author)

  6. Application of digital control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Keiper, J.T.

    1993-01-01

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

  7. Nuclear power plant outages

    International Nuclear Information System (INIS)

    1998-01-01

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

  8. Design of an automatic control system of a district heating nuclear plant

    International Nuclear Information System (INIS)

    Zebiri, Abderrahim.

    1980-06-01

    This paper presents the synthesis of the control system of a nuclear/oil fuelled district heating plant. Operating criteria take into account the economical background of the problem. Nuclear reactor control loops were specially conceived, due to the specific perturbations to which is submitted a district heating plant [fr

  9. Informatization of items quality control for NI in nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Jiankui; Zang Baiqi

    2010-01-01

    Design ideas, implementation methods and some key techniques for item quality control of NI in nuclear power plant are illustrated in this article according to item quality management mode. The item quality control method can improve the quality of NI, ensure the safety and lower the construction and operation cost of nuclear power plant. (authors)

  10. Applying Online Monitoring for Nuclear Power Plant Instrumentation and Control

    Science.gov (United States)

    Hashemian, H. M.

    2010-10-01

    This paper presents a practical review of the state-of-the-art means for applying OLM data acquisition in nuclear power plant instrumentation and control, qualifying or validating the OLM data, and then analyzing it for static and dynamic performance monitoring applications. Whereas data acquisition for static or steady-state OLM applications can require sample rates of anywhere from 1 to 10 seconds to 1 minutes per sample, for dynamic data acquisition, higher sampling frequencies are required (e.g., 100 to 1000 Hz) using a dedicated data acquisition system capable of providing isolation, anti-aliasing and removal of extraneous noise, and analog-to-digital (A/D) conversion. Qualifying the data for use with OLM algorithms can involve removing data `dead' spots (for static data) and calculating, examining, and trending amplitude probability density, variance, skewness, and kurtosis. For static OLM applications with redundant signals, trending and averaging qualification techniques are used, and for single or non-redundant signals physical and empirical modeling are used. Dynamic OLM analysis is performed in the frequency domain and/or time domain, and is based on the assumption that sensors' or transmitters' dynamic characteristics are linear and that the input noise signal (i.e., the process fluctuations) has proper spectral characteristics.

  11. Quality control of concrete structures in nuclear power plant, (4)

    International Nuclear Information System (INIS)

    Takahashi, Hisao; Kawaguchi, Tohru; Oike, Takeshi; Morimoto, Shoichi; Takeshita, Shigetoshi.

    1979-01-01

    This report describes the result of an investigation to clarify the effect of concrete temperature as mixed in the summer season on the strength gain characteristics of mass concrete such as used in construction of nuclear power plants. It is pointed out that the low strength gain of control cylinders in summer is caused by two main factors, viz., the absence of water modification in the mix design according to concrete temperature as mixed and high curing temperature after placing up to mold removal rather than concrete temperature itself as mixed. On the other hand, it has been clarified that high strength gain in mass concrete can be realized by lowering concrete temperature as mixed so as to lower the subsequent curing temperature at early age. Furthermore, it is explained that the larger the size of the member is, the more effect can be expected from lowering concrete temperature. The effect of concrete temperature as mixed on high strength concrete to be used in PCCV is discussed in the Appendix. (author)

  12. Nuclear power plant pressure vessels. Control of piping

    International Nuclear Information System (INIS)

    2000-01-01

    The guide presents requirements for the pipework of nuclear facilities in Finland. According to the section 117 of the Finnish Nuclear Energy Degree (161/88), the Radiation and Nuclear Safety Authority of Finland (STUK) controls the pressure vessels of nuclear facilities in accordance with the Nuclear Energy Act (990/87) and, to the extent applicable in accordance with the Act of Pressure Vessels (98/73) and the rules and regulations issued by the virtue of these. In addition STUK is an inspecting authority of pressure vessels of nuclear facilities in accordance with the Pressure Vessel Degree (549/1973). According to the section of the Pressure Vessel Degree, a pressure vessel is a steam boiler, pressure container, pipework of other such appliance in which the pressure is above or may come to exceed the atmospheric pressure. Guide YVL 3.0 describes in general terms how STUK controls pressure vessels. STUK controls Safety Class 1, 2 and 3 piping as well as Class EYT (non-nuclear) and their support structures in accordance with this guide and applies the provisions of the Decision of the Ministry of Trade and Industry on piping (71/1975) issued by virtue of the Pressure Vessel Decree

  13. Intelligent control system for nuclear power plant mobile robot

    International Nuclear Information System (INIS)

    Koenig, A.; Lecoeur-Taibi, I.; Crochon, E.; Vacherand, F.

    1991-01-01

    In order to fully optimize the efficiency of the perception and navigation components available on a mobile robot, the upper level of a mobile robot control requires intelligence support to unload the work of the teleoperator. This knowledge-based system has to manage a priori data such as the map of the workspace, the mission, the characteristics of sensors and robot, but also, the current environment state and the running mission. It has to issue a plan to drive the sensors to focus on relevant objects or to scan the environment and to select the best algorithms depending on the current situation. The environment workspace is a nuclear power plant building. The teleoperated robot is a mobile wheeled or legged vehicle that moves inside the different floors of the building. There are three types of mission: radio-activity survey, inspection and intervention. To perform these goals the robot must avoid obstacles, pass through doors, possibly climb stairs and recognize valves and pipes. The perception control system has to provide the operator with a synthetic view of the surroundings. It manages background tasks such as obstacle detection and free space map building, and specific tasks such as beacon recognition for odometry relocalization and valve detection for maintenance. To do this, the system solves perception resources conflicts, taking into account the current states of the sensors and the current conditions such as lightness or darkness, cluttered scenes, sensor failure. A perception plan is issued from the mission goals, planned path, relocalization requirements and available perception resources. Basically, the knowledge-based system is implemented on a blackboard architecture which includes two parts: a top-down planning part and a bottom-up perception part. The results of the perception are continuously sent to the operator who can trigger new perception actions. (author)

  14. Distributed computer control systems in future nuclear power plants

    International Nuclear Information System (INIS)

    Yan, G.; L'Archeveque, J.V.R.; Watkins, L.M.

    1978-09-01

    Good operating experience with computer control in CANDU reactors over the last decade justifies a broadening of the role of digital electronic and computer related technologies in future plants. Functions of electronic systems in the total plant context are reappraised to help evolve an appropriate match between technology and future applications. The systems research, development and demonstration program at CRNL is described, focusing on the projects pertinent to the real-time data acquisition and process control requirements. (author)

  15. A modeling and control approach to advanced nuclear power plants with gas turbines

    International Nuclear Information System (INIS)

    Ablay, Günyaz

    2013-01-01

    Highlights: • Load frequency control strategies in nuclear plants are researched. • Nuclear reactor-centered control system may not be suitable for load control. • Local unit controllers improve stability and overall time constant. • Coolant loops in nuclear plants should be controlled locally. - Abstract: Advanced nuclear power plants are currently being proposed with a number of various designs. However, there is a lack of modeling and control strategies to deal with load following operations. This research investigates a possible modeling approach and load following control strategy for gas turbine nuclear power plants in order to provide an assessment way to the concept designs. A load frequency control strategy and average temperature control mechanism are studied to get load following nuclear power plants. The suitability of the control strategies and concept designs are assessed through linear stability analysis methods. Numerical results are presented on an advanced molten salt reactor concept as an example nuclear power plant system to demonstrate the validity and effectiveness of the proposed modeling and load following control strategies

  16. An analytical and experimental study of the behaviour of redundant controllers applied to a nuclear plant

    International Nuclear Information System (INIS)

    Lawrence, L.A.J.

    1964-02-01

    The behaviour of a number of configurations of redundant controllers is examined and the design problems discussed in relation to the engineering of reliable control rod drive systems for nuclear plant. (author)

  17. Design of coordinated controller in nuclear power plant based on digital instrument and control technology

    International Nuclear Information System (INIS)

    Cheng Shouyu; Peng Minjun; Liu Xinkai; Zhao Qiang; Deng Xiangxin

    2014-01-01

    Nuclear power plant (NPP) is a multi-input and multi-output, no-linear and time-varying complex system. The conventional PID controller is usually used in NPP control system which is based on analog instrument. The system parameters are easy to overshoot and the response time is longer in the control mode of the conventional PID. In order to improve this condition, a new coordinated control strategy which is based on expert system and the original controllers in the digital instrument and control technology was presented. In order to verify and validate it, the proposed coordinated control technology was tested by the full-scope real-time simulation system. The results prove that using digital instrument and control technology to achieve coordinated controller is feasible, the coordinated controller can effectively improve the dynamic operating characteristics of the system, and the coordinated controller is superior to the conventional PID controller in control performance. (authors)

  18. Administrative and managerial controls for the operation of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Guidelines are provided for the administrative and managerial controls necessary for the safe and efficient operation of nuclear fuel reprocessing plants. Topics covered include: administrative organization; review and audit; facility administrative policies and procedures; and tests and inspections. Recognizing that administrative practices vary among organizations operating nuclear fuel reprocessing plants, the standard incorporates flexibility that provides for compliance by any organization

  19. Virtual reality applied in the ergonomic evaluation of nuclear power plant control room

    International Nuclear Information System (INIS)

    Gatto, Leandro Barbosa da Silveira

    2012-01-01

    A nuclear power plant control room is a complex system that controls a nuclear and thermodynamic process used to produce electrical energy. The operators interact with the control room through interfaces that have significant implications to nuclear power plant safety and influence the operator activity. The operator activity presents complexity features and shows a series of mechanisms absents from the human factors guidelines, important to the evaluation and update of control rooms. The ergonomics approach considers the operation strategies, the interaction between the operators, the operator-system interaction, and interaction between operators and support groups. The main objective of this paper is propose the modeling of a nuclear control room, with the support of a game engine core. This tool will be used in the ergonomic evaluation of nuclear control room, generating information and data that will make possible the adequacy of control rooms features to the legal requirements of the regulating agency, assisting the nuclear licensing. (author)

  20. Angra nuclear plant - environmental control program; Usina Nuclear de Angra: programa de controle ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Kircher, E; Cruz, E.S. da [FURNAS, Rio de Janeiro, RJ (Brazil)

    1990-12-31

    The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs.

  1. Discussion on verification criterion and method of human factors engineering for nuclear power plant controller

    International Nuclear Information System (INIS)

    Yang Hualong; Liu Yanzi; Jia Ming; Huang Weijun

    2014-01-01

    In order to prevent or reduce human error and ensure the safe operation of nuclear power plants, control device should be verified from the perspective of human factors engineering (HFE). The domestic and international human factors engineering guidelines about nuclear power plant controller were considered, the verification criterion and method of human factors engineering for nuclear power plant controller were discussed and the application examples were provided for reference in this paper. The results show that the appropriate verification criterion and method should be selected to ensure the objectivity and accuracy of the conclusion. (authors)

  2. Quality control of three main materials for civil construction of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Feng

    2011-01-01

    The construction and operation of nuclear power plant is a systematic engineering. To ensure quality and safety of nuclear power plants, each work from design to operation can have certain impact on the quality and safety of the project. The quality of each related work shall be controlled. Starting from the quality control over raw materials for the civil construction of nuclear power plant, this article mainly analyzes how to control the quality and manage the three main materials of steel, concrete and modular parts in the civil construction. (author)

  3. Automated systems for control of technological processes at nuclear power plants and their use in putting the plant into operation

    International Nuclear Information System (INIS)

    Majtan, L.

    1987-01-01

    The systems of testing and control of technological processes in WWER-440 units in nuclear power plants which have so far been constructed in Czechoslovakia have been based on the conceptual principles and hardware used in the USSR. For the Mochovce nuclear power plant an automated process control system is to be introduced which proceeds from experiences gained with new Czechoslovak conventional power plants with 200 MW units. The control system consists of two levels: unit control and the control of the whole power plant the unit control consists of the DERIS-900 decentralized control system and the SM 1804 microcomputer and SM 1420 minicomputer based information and control system. A data processing system based on the SM 52/11.M1 minicomputer system will be used for power plant start-up and commissioning. (Z.M.). 2 figs., 4 refs

  4. Report on the status of instrumentation and control in Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Stroebeck, E.

    1992-01-01

    Nuclear power plants accounted for 46% of the total electric power production in Sweden in 1990. The availability of the Swedish reactors remains at a very high level. The oldest Swedish nuclear power plant has been in operation for nearly 20 years, and in the next 5 to 10 years a large portion of the NPP electrical equipment has to be replaced. The paper presents an overview of activities on control and instrumentation in the following: Future developments; implementation of computer-based systems; training simulators; nuclear safety research. The operating experience in Swedish nuclear power plants in 1991 is also presented. (author)

  5. The main features of control and operation of steam turbines at nuclear power plants

    International Nuclear Information System (INIS)

    Czinkoczky, B.

    1981-01-01

    The output and speed control of steam turbines at nuclear power plants as well as the combination of both controls are reviewed and evaluated. At the same time the tasks of unit control at nuclear power plants, the control of steady main steam pressure and medium pressure of primary circuit, further the connection of reactor and turbine controls and the self-controlling properties of pressurized water reactor are dealt with. Hydraulic and electro-hydraulic speed control, the connection of cach-up dampers and speed control and the application of electro-hydraulic signal converters are discussed. The accomplishment of protection is also described. (author)

  6. Control system design considerations in a modern nuclear power plant

    International Nuclear Information System (INIS)

    Foster, P.; Raiskums, G.; Harber, J.; Tikku, S.

    2010-01-01

    Applying new technologies is a challenge for instrumentation and control (I and C) designers to ensure that the overall principles of defence-in-depth, the independence of safety functions (credited in the safety case), and modern human factors engineering principles are maintained. This paper describes the Advanced CANDU Reactor (ACR-1000) I and C architecture, including the display/control systems and the design approaches employed to ensure that the fundamental premise of independence between safety and process control is not compromised and that the reliability targets for each layer of protection are fulfilled to meet the overall plant safety goals. (author)

  7. Large screen mimic display design research for advanced main control room in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Mingguang; Yang Yanhua; Xu Jijun; Zhang Qinshun; Ning Zhonghe

    2002-01-01

    Firstly the evolution of mimic diagrams or displays used in the main control room of nuclear power plant was introduced. The active functions of mimic diagrams were analyzed on the release of operator psychological burden and pressure, the assistance of operator for the information searching, status understanding, manual actuation, correct decision making as well as the safe and reliable operation of the nuclear power plant. The importance and necessity to use the (large screen) mimic diagrams in advanced main control room of nuclear power plant, the design principle, design details and verification measures of large screen mimic display are also described

  8. Flood control design requirements and flood evaluation methods of inland nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Ailing; Wang Ping; Zhu Jingxing

    2011-01-01

    Effect of flooding is one of the key safety factors and environmental factors in inland nuclear power plant sitting. Up to now, the rule of law and standard systems are established for the selection of nuclear power plant location and flood control requirements in China. In this paper flood control standards of China and other countries are introduced. Several inland nuclear power plants are taken as examples to thoroughly discuss the related flood evaluation methods. The suggestions are also put forward in the paper. (authors)

  9. Multivariable controller for a 600 MWe CANDU nuclear power plant

    International Nuclear Information System (INIS)

    Mensah, S.

    1982-11-01

    The problems of designing a multivariable regulator for a nuclear power station of the Gentilly-2 type are studied. A reduced model, G2LDM, linearized around steady state operating conditions, is derived from the non-linear model G2SIM. The resulting linear model is described by state-space equations. Good agreement is demonstrated between the transient responses of both models. Properties of G2LDM are assessed by performing controllability and observability tests, cyclicity and rank tests, and eigenanalysis. A comprehensive set of application-orinented algorithms which allow multivariable controller design with closed-loop pole-assignment techniques are implemented in a computer-aided design package via several modules. A general scheme for the implementation of a multivariable controller in G2SIM is designed, and simulation tests show satisfactory performance of the controller [fr

  10. A Business Case for Nuclear Plant Control Room Modernization

    International Nuclear Information System (INIS)

    Thomas, Ken; Lawrie, Sean; Niedermuller, Josef M.

    2016-01-01

    This paper presents a generic business case for implementation of technology that supports Control Room Modernization (CRM). The analysis presented in two forms; 1) a standalone technology upgrade, and 2) a technology upgrade that is built upon and incremental to a prior business case created for Mobile Work Packages (MWP). The business case contends that advanced communication and networking and analytical technologies will allow NPP to conduct control room operations with improved focus by reducing human factors and redundant manpower, and therefore operate with fewer errors. While some labor savings can be harvested in terms of overtime, the majority of savings are demonstrated as reduced time to take the plant off line and bring back on line in support of outages. The benefits are quantified to a rough order of magnitude that provides directional guidance to NPPs that are interested in developing a similar business case. This business case focuses on modernization of the operator control room and does not consider a complete overhaul and modernization of a plants instrument and control systems. While operators may be considering such an investment at their plants, the sizable capital investment required is not likely supported by a cost/benefit analysis alone. More likely, it is driven by obsolescence and reliability issues, and requires consideration of mechanical condition of plant systems, capital depreciation, financing, relicensing and overall viability of the plant asset over a 20-year horizon in a competitive market. Prior studies [REF] have indicated that such a modernization of plant I&C systems, alone or as part of a larger modernization effort, can yield very significant reductions in O&M costs. However, the depth of research and analysis required to develop a meaningful business case for a plant modernization effort is well beyond the scope of this study. While CRM as considered in this study can be easily integrated as part of grander plant

  11. A Business Case for Nuclear Plant Control Room Modernization

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, Ken [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lawrie, Sean [Idaho National Lab. (INL), Idaho Falls, ID (United States); Niedermuller, Josef M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-06-01

    This paper presents a generic business case for implementation of technology that supports Control Room Modernization (CRM). The analysis presented in two forms; 1) a standalone technology upgrade, and 2) a technology upgrade that is built upon and incremental to a prior business case created for Mobile Work Packages (MWP). The business case contends that advanced communication and networking and analytical technologies will allow NPP to conduct control room operations with improved focus by reducing human factors and redundant manpower, and therefore operate with fewer errors. While some labor savings can be harvested in terms of overtime, the majority of savings are demonstrated as reduced time to take the plant off line and bring back on line in support of outages. The benefits are quantified to a rough order of magnitude that provides directional guidance to NPPs that are interested in developing a similar business case. This business case focuses on modernization of the operator control room and does not consider a complete overhaul and modernization of a plants instrument and control systems. While operators may be considering such an investment at their plants, the sizable capital investment required is not likely supported by a cost/benefit analysis alone. More likely, it is driven by obsolescence and reliability issues, and requires consideration of mechanical condition of plant systems, capital depreciation, financing, relicensing and overall viability of the plant asset over a 20-year horizon in a competitive market. Prior studies [REF] have indicated that such a modernization of plant I&C systems, alone or as part of a larger modernization effort, can yield very significant reductions in O&M costs. However, the depth of research and analysis required to develop a meaningful business case for a plant modernization effort is well beyond the scope of this study. While CRM as considered in this study can be easily integrated as part of grander plant

  12. Study of two control rods of a district heating nuclear plant

    International Nuclear Information System (INIS)

    Martinez, J.M.

    1979-01-01

    This paper broaches the study of the control rods to ensure a convenient working during load following of the nuclear reactor THERMOS. The mathematical model is descriptive of the whole of the nuclear plant (point model for the core and the heat balances). Two power control are studied. The first, like PWR, is a program for the mean temperature of primary water. The second takes into account the structure of the plant and is described by a schedule of powers [fr

  13. Automated rule-base control for nuclear power plants

    International Nuclear Information System (INIS)

    Colley, R.W.

    1983-09-01

    An effort is underway to optimize the roles of man and machine in the control of liquid-metal-cooled fast breeder reactors. The work reported here describes: (1) a methodology for the decomposition of a process into a hierarchical structure; (2) an explicit methodology, Sequencing Established States, to limit the state space search for process control; and (3) the Procedure Prompting System which demonstrates the use of the above methodologies for automatically generating instructions to provide guidance to an operator for both normal and off-normal plant conditions

  14. Safety and security analysis for distributed control system in nuclear power plants

    International Nuclear Information System (INIS)

    Lu Zhigang; Liu Baoxu

    2011-01-01

    The Digital Distributed Control System (DCS) is the core that manages all monitoring and operation tasks in a Nuclear Power Plant (NPP). So, Digital Distributed Control System in Nuclear Power Plant has strict requirements for control and automation device safety and security due to many factors. In this article, factors of safety are analyzed firstly, while placing top priority on reliability, quality of supply and stability have also been carefully considered. In particular, advanced digital and electronic technologies are adopted to maintain sufficient reliability and supervisory capabilities in nuclear power plants. Then, security of networking and information technology have been remarked, several design methodologies considering the security characteristics are suggested. Methods and technologies of this article are being used in testing and evaluation for a real implement of a nuclear power plant in China. (author)

  15. Nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

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

  16. Methodology for allocating nuclear power plant control functions to human or automatic control

    International Nuclear Information System (INIS)

    Pulliam, R.; Price, H.E.; Bongarra, J.; Sawyer, C.R.; Kisner, R.A.

    1983-08-01

    This report describes a general method for allocating control functions to man or machine during nuclear power plant (NPP) design, or for evaluating their allocation in an existing design. The research examined some important characeristics of the systems design process, and the results make it clear that allocation of control functions is an intractable problem, one which increases complexity of systems. The method is reported in terms of specific steps which should be taken during early stages of a new system design, and which will lead to an optimal allocation at the functional design level of detail

  17. Progress of nuclear safety for symbiosis and sustainability advanced digital instrumentation, control and information systems for nuclear power plants

    CERN Document Server

    Yoshikawa, Hidekazu

    2014-01-01

    This book introduces advanced methods of computational and information systems allowing readers to better understand the state-of-the-art design and implementation technology needed to maintain and enhance the safe operation of nuclear power plants. The subjects dealt with in the book are (i) Full digital instrumentation and control systems and human?machine interface technologies (ii) Risk? monitoring methods for large and? complex? plants (iii) Condition monitors for plant components (iv) Virtual and augmented reality for nuclear power plants and (v) Software reliability verification and val

  18. Iron concentration controller in feedwater in nuclear plant

    International Nuclear Information System (INIS)

    Aizawa, Motohiro; Isaka, Yoshitaka

    1990-01-01

    The purpose of the present invention is to prevent chlorine ions from flowing into a reactor when sea water leakage accident should occur in a condenser upon control of Fe concentration in feedwater. That is, a sensor is disposed for detecting the leakage of the sea water at the exit of the condenser. The controller receives a detection signal as the input and delivers a control signal as the output. A control system receives the control signal and actuates valves in bypass systems. In view of the above, the electroconductivity or chlorine ion concentration of the condensate, which varies upon occurrence of sea water leakages in the condenser, is detected by the sensor, and then the controller closes a valve dispposed in the bypass systems in a processing device for filtering and desalting the condensates. Accordingly, the chlorine ions mixed into the condensates are removed by a desalting device without flowing into the reactor. In view of the above, an effect capable of keeping integrity of the plant is obtainable. (I.S.)

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

    Directory of Open Access Journals (Sweden)

    Gusev S. S.

    2017-04-01

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

  20. Experience in designing the automatic nuclear power plant control system

    International Nuclear Information System (INIS)

    Sedov, V.K.; Busygin, B.F.; Eliseeva, O.V.; Mikhajlov, V.A.

    1981-01-01

    The integrated automatic control system (ACS) is designed at the Novovoronezh NPP (NVNPP). It comprises automatic technological control of all the five power un+ts and the plant in the whole (ACST) and automatic organizational-economic production control system (ACSP). The NVNPP ACS is designed as a two-level system. The two M-4030 and M-4030-1 computers are the technical base of the upper layer while a set of block NPP (computer-M-60 and M-700 for unit 5; M-60 and SM-2 for units 1-4) of the lower level. Block diagram of the NVNPP ACS, flowsheet of NVNPP ACS technical means and external communications of the control centre are described. The NVNPP ACS is supposed to be put into operation by stages. It is noted that design and introduction of the typical NPP ACS at the NVNPP permits to maximally reduce in the future the period of developing automatic control systems at nly introduced units and NPPs with the WWER reactors [ru

  1. Analysis on nuclear power plant control room system design and improvement based on human factor engineering

    International Nuclear Information System (INIS)

    Gao Feng; Liu Yanzi; Sun Yongbin

    2014-01-01

    The design of nuclear power plant control room system is a process of improvement with the implementation of human factor engineering theory and guidance. The method of implementation human factor engineering principles into the nuclear power plant control room system design and improvement was discussed in this paper. It is recommended that comprehensive address should be done from control room system function, human machine interface, digital procedure, control room layout and environment design based on the human factor engineering theory and experience. The main issues which should be paid more attention during the control room system design and improvement also were addressed in this paper, and then advices and notices for the design and improvement of the nuclear power plant control room system were afforded. (authors)

  2. Simulation of control performance under house load transients for nuclear power plant

    International Nuclear Information System (INIS)

    Liao Zhongyue; Wang Yuanlong; Tang Yuyuan; Liu Jiong

    1999-01-01

    The CATIA2 code is used to simulate the extreme normal transients--house load transients of Qinshan Phase II 600 MW nuclear power plant. The simulating results show that all of the reactor main parameters are operating in the allowable ranges, the reactor system is stable, and the control characteristics of the nuclear power plant is satisfactory. They are also good in agreement with Framatome's results

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

    International Nuclear Information System (INIS)

    Spetko, V.

    1976-01-01

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

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

    International Nuclear Information System (INIS)

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

    1979-07-01

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

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

    International Nuclear Information System (INIS)

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

    1979-01-01

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

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

    International Nuclear Information System (INIS)

    Zha Qing

    2014-01-01

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

  7. A framework for selecting suitable control technologies for nuclear power plant systems

    International Nuclear Information System (INIS)

    Kisner, R.A.

    1992-01-01

    New concepts continue to emerge for controlling systems, subsystems, and components and for monitoring parameters, characteristics, and vital signs in nuclear power plants. The steady stream of new control theories and the evolving state of control software exacerbates the difficulty of selecting the most appropriate control technology for nuclear power plant systems. As plant control room operators increase their reliance on computerized systems, the integration of monitoring, diagnostic, and control functions into a uniform and understandable environment becomes imperative. A systematic framework for comparing and evaluating the overall usefulness of control techniques is needed. This paper describes nine factors that may be used to evaluate alternative control concepts. These factors relate to a control system's potential effectiveness within the context of the overall environment, including both human and machine components. Although not an in-depth study, this paper serves to outline an evaluation framework based on several measures of utility. 32 refs

  8. Verification and validation of software related to nuclear power plant instrumentation and control

    International Nuclear Information System (INIS)

    1999-01-01

    This report is produced in response to a recommendation of the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation. The report has objectives of providing practical guidance on the methods available for verification of the software and validation of computer based systems, and on how and when these methods can be effectively applied. It is meant for those who are in any way involved with the development, implementation, maintenance and use of software and computer based instrumentation and control systems in nuclear power plants. The report is intended to be used by designers, software producers, reviewers, verification and validation teams, assessors, plant operators and licensers of computer based systems

  9. Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants

    International Nuclear Information System (INIS)

    1999-01-01

    The problems of creation and operation of nuclear materials (NM) control and accounting systems and their components at radiochemical plants were discussed in seminar during November 2-6 of 1998. There were 63 Russian and 25 foreign participants in seminar. The seminar programme includes following sessions and articles: the aspects of State NM control and accountancy; NM control and accounting in radiochemical plants and at separate stages of reprocessing of spent nuclear fuel and irradiated fuel elements of commercial reactors; NM control and accountancy in storage facilities of radiochemical plants; NM control and accounting computerization, material balance assessment, preparation of reports; qualitative and quantitative measurements in NM control and accounting at radiochemical plants destructive analysis techniques [ru

  10. NCS--a software for visual modeling and simulation of PWR nuclear power plant control system

    International Nuclear Information System (INIS)

    Cui Zhenhua

    1998-12-01

    The modeling and simulation of nuclear power plant control system has been investigated. Some mathematical models for rapid and accurate simulation are derived, including core models, pressurizer model, steam generator model, etc. Several numerical methods such as Runge-Kutta Method and Treanor Method are adopted to solve the above system models. In order to model the control system conveniently, a block diagram-oriented visual modeling platform is designed. And the Discrete Similarity Method is used to calculate the control system models. A corresponding simulating software, NCS, is developed for researching on the control systems of commercial nuclear power plant. And some satisfactory results are obtained. The research works will be of referential and applying value to design and analysis of nuclear power plant control system

  11. OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring

    2012-10-01

    This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

  12. Concept and design of a fully computerized control room for future nuclear power plant

    International Nuclear Information System (INIS)

    Hinz, W.; Kollmannsberger, J.

    1991-01-01

    The development of digital process control equipment and of safety engineering equipment together with the CRT - based information visualization systems is advanced to a state allowing process control of nuclear power plant to be done by these equipments. The systems have been tested in the control room of the fossil-fuel Staudinger reactor station, unit 5, and the computer-assisted PRISCA process information system has been tested in the Konvoi-type nuclear reactor series. These tests serve as a basis for further process control system development by Siemens KWU, to be used in their future nuclear power plants. The advantages of digital process control and CRT-based information display are intended to be used for further optimization of the man-machine interface in nuclear power plant. One important aspect is to give the control room personnel complete insight into the operational processes of the entire plant, and to establish for detail recognition for process monitoring a very close mental link between operators and the system processes. In addition, the control room operator has to be given appropriate means and tools for process monitoring and control, fulfilling the requirements of guaranteeing the plant's availability and safety. These requirements put very high demands on the process monitoring and control equipment. (orig.) [de

  13. Sensor controlled robotic welding for nuclear power plant operations

    International Nuclear Information System (INIS)

    Chin, B.A.

    1989-01-01

    The objective of the proposed research is to apply real time monitoring, artificial intelligence and on-line correction to dynamically control the depth of weld penetration and weld integrity during the welding process. Welding is a major technique used in the fabrication, construction and maintenance of power generating and energy conversion systems. In the welding process, fluctuations in process variables lead to weld defects such as lack of penetration, cracks, porosity and undesirable metallurgical structures. This research will apply advanced infrared sensing techniques which have been successfully used in seam tracking to the equally complex problem of weld defect and weld puddle penetration control. Thermal temperature distributions of plates being welded will be dynamically measured during welding using infrared techniques. These temperature distributions will be used to interpret changes in the size and shape of the molten metal pool and the presence of conditions that may lead to defects in the solidified weld. The ultimate result of this research will be the development of machines which are capable of sensing and altering process variables to eliminate defective welds and increase the productivity of the welding process. Successful completion of this proposed research will lead to potential major improvements in the fabrication, construction and maintenance of advanced nuclear reactors and promote increased safety and reliability while decreasing construction costs. 47 refs., 50 figs

  14. Nuclear power plant control room task analysis. Pilot study for pressurized water reactors

    International Nuclear Information System (INIS)

    Barks, D.B.; Kozinsky, E.J.; Eckel, S.

    1982-05-01

    The purposes of this nuclear plant task analysis pilot study: to demonstrate the use of task analysis techniques on selected abnormal or emergency operation events in a nuclear power plant; to evaluate the use of simulator data obtained from an automated Performance Measurement System to supplement and validate data obtained by traditional task analysis methods; and to demonstrate sample applications of task analysis data to address questions pertinent to nuclear power plant operational safety: control room layout, staffing and training requirements, operating procedures, interpersonal communications, and job performance aids. Five data sources were investigated to provide information for a task analysis. These sources were (1) written operating procedures (event-based); (2) interviews with subject matter experts (the control room operators); (3) videotapes of the control room operators (senior reactor operators and reactor operators) while responding to each event in a simulator; (4) walk-/talk-throughs conducted by control room operators for each event; and (5) simulator data from the PMS

  15. Quality assurance as a system of management control in nuclear power plants

    International Nuclear Information System (INIS)

    Raisic, N.

    1986-04-01

    Quality assurance is considered as a management control system which the owner of a nuclear power plant has to establish for a nuclear power project for ensuring that a plant is built as designed and that defects are corrected. The building up of such a system should start early enough in project activities and before the plant design and construction, in order to ensure correct performance of all activities related to selection of the site for the nuclear power plant, bid specification and evaluation and procurement of services. The QA is a regulatory requirement, but the prudent plant management would create such a system as part of their total project management systems irrespective of formulation of requirement. In fact regulatory requirement should be considered as the criteria to be used by the regulatory organization for evaluation of licensee's QA system and not as an objective to be reached. In this paper the needs for QA system are justified as part of the development of industrial infrastructure for the nuclear power project. Elements of the system are described such as documented QA programme and organizational structures with defined responsibility and functions of individual organizational units, and with control of information flow across the interfaces. The goals and objectives or the project organizations related to achievement and verification of quality are defined as well as system functions in attaining these objectives. This includes the feedback of information to the management on monitoring of performance in project activities, identifying deficiencies and initiating corrective actions. Domestic participation in the nuclear power plant construction will depend on the ability of local construction and manufacturing organizations to achieve high quality standards of products and services that can affect safety and performance of the nuclear power plant. Introduction of QA systems in project organizations, development of QA programme and

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

    International Nuclear Information System (INIS)

    Plas, Y. van der

    1990-01-01

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

  17. An underwater robot controls water tanks in nuclear power plants

    International Nuclear Information System (INIS)

    Lardiere, C.

    2015-01-01

    The enterprises Newton Research Labs and IHI Southwest Technologies have developed a robot equipped with sensors to inspect the inside walls (partially) and bottom of water tanks without being obliged to empty them. The robot called 'Inspector' is made up of 4 main components: a chassis with 4 independent steering wheels, a camera video system able to provide a 360 degree view, various non-destructive testing devices such as underwater laser scanners, automated ultra-sound or Foucault current probes and an operation system for both driving the robot and controlling the testing. The Inspector robot has been used to inspect the inside bottom of an operating condensate tank at the Palo Verde nuclear station. The robot was able to check all the welds joining the bottom plates and the welds between the walls and the bottom. The robot is also able to come back to the exact place where a defect was detected during a previous inspection. (A.C.)

  18. The human factors of CRT displays for nuclear power plant control

    International Nuclear Information System (INIS)

    Danchak, M.M.

    1984-01-01

    This chapter attempts to show how the Cathode Ray Tube (CRT) can be used to effectively present information to the operator rather than just data. The capabilities of the human as a sensing and information processing subsystem are discussed with CRT displays in mind. The display system is described in terms of its hardware and functioning. The interface between the two is examined by providing substantive guidelines for the effective design of CRT displays for nuclear power plant control. Alphanumeric displays, graphic displays, and representational displays are treated. The design of CRT displays for nuclear power plant control requires an extensive knowledge of cognitive psychology, computer display systems and the process being controlled

  19. Concept and structure of instrumentation and control of the Atucha II nuclear power plant

    International Nuclear Information System (INIS)

    Garzon, D.; Roca, J.L.

    1987-01-01

    The general structure of instrumentation and control of Atucha II nuclear power plant as well as the technologies used, are described: concepts of functional decentralization and physical centralization; concept of functional group and functional complex; description of the technologies used (physical support) in the project of plant instrumentation and control; description of the different automation levels on the basis of concepts of control interface, automatism, regulation, group and subgroup controls; principles of signal conditioning; concept of announcement of alarms and state: supervisory computer, description of HAS (Hard wired Alarm System) and CAS (Computer Alarm System); application of the above mentioned structure to the project of another type of plants. (Author)

  20. Administrative controls and quality assurance for the operational phase of nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    This standard provides requirements and recommendations for an adminstrative controls and quality assurance program to help ensure that activities associated with nuclear power plant operation are carried out without undue risk to the health and safety of the public. This standard applies to all activities affecting those functions important to the safety of nuclear power plant structures, systems, and components. Activities included are: design changes, purchasing, fabricating, handling, shipping, storing, cleaning and decontaminating, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, modifying and decomissioning. This standard is not specifically intended for application to test, mobile or experimental reactors, nor reactors not subject to U.S. Nuclear Regulatory Commission licensing

  1. A performance improvement program applied to the Perry Nuclear Power Plant instrumentation and control section

    International Nuclear Information System (INIS)

    Anderson, G.R.

    1987-01-01

    The management at Cleveland Electric Illuminating Company sought to avoid problems typically encountered in the start-up of new nuclear generating units. In response to early indications that such problems may have been developing at their Perry Nuclear Power Plant, several performance improvement initiatives were undertaken. One of these initiatives was a performance improvement evaluation (PIE) for the instrumentation and control (IandC) section at Perry. The IandC PIE, which used a method designed to be adaptable to other disciplines as well, had important results that are applicable to other nuclear power plants

  2. Utility of low-order linear nuclear-power-plant models in plant diagnostics and control

    International Nuclear Information System (INIS)

    Tylee, J.L.

    1981-01-01

    A low-order, linear model of a pressurized water reactor (PWR) plant is described and evaluated. The model consists of 23 linear, first-order difference equations and simulates all subsystems of both the primary and secondary sides of the plant. Comparisons between the calculated model response and available test data show the model to be an adequate representation of the actual plant dynamics. Suggested use for the model in an on-line digital plant diagnostics and control system are presented

  3. A full scope nuclear power plant simulator for multiple reactor types with virtual control panels

    International Nuclear Information System (INIS)

    Yonezawa, Hisanori; Ueda, Hiroki; Kato, Takahisa

    2017-01-01

    This paper summarizes a full scope nuclear power plant simulator for multiple reactor types with virtual control panels which Toshiba developed and delivered. After the Fukushima DAIICHI nuclear power plants accident, it is required that all the people who are engaged in the design, manufacturing, operation, maintenance, management and regulation for the nuclear power plant should learn the wide and deep knowledge about the nuclear power plant design including the severe accident. For this purpose, the training with a full scope simulator is one of the most suitable ways. However the existing full scope simulators which are consist of the control panels replica of the referenced plants are costly and they are hard to remodel to fit to the real plant of the latest condition. That's why Toshiba developed and delivered the new concept simulator system which covers multiple referenced plants even though they have different design like BWR and PWR. The control panels of the simulator are made by combining 69 large Liquid Crystal Display (LCD) panels with touch screen instead of a control panel replica of referenced plant. The screen size of the each panel is 42 inches and 3 displays are arranged in tandem for one unit and 23 units are connected together. Each panel displays switches, indicators, recorders and lamps with the Computer Graphics (CG) and trainees operate them with touch operations. The simulator includes a BWR and a PWR simulator model, which enable trainees to learn the wide and deep knowledge about the nuclear power plant of BWR and PWR reactor types. (author)

  4. Control rooms and man-machine interface in nuclear power plants

    International Nuclear Information System (INIS)

    1990-08-01

    The importance of man-machine interface for ensuring safe and reliable operation of nuclear power plants has always been recognized. Since the early 1970's, the concepts of operator support and human factors have been increasingly used to better define the role of control rooms. In the late 1970's, the lessons learned from experience considerably accelerated the development of recommendations and regulatory requirements governing the resources and data available to operators in nuclear power plant control rooms, and specified the expertise required to assist them in case of need. This document summarizes the steps which have been taken and are being planned around the world to improve the man-machine interface for safe and economic power generation. It intends to present to the reader useful examples on some selected control room design and man-machine interface practices for operation and surveillance of nuclear power plants. 53 refs, 94 figs, 27 tabs

  5. Instrumentation and control systems for CANDU-PHW nuclear power plants

    International Nuclear Information System (INIS)

    Lepp, R.M.; Watkins, L.M.

    1982-02-01

    The instrumentation and control of CANDU nuclear power plants takes advantage of modern electronics technology in the extensive computerization of important control and man-machine functions. A description of these functions as well as those of the four Special Safety Systems is provided

  6. Recent developments in the field of nuclear power plant control and instrumentation in Hungary

    International Nuclear Information System (INIS)

    Pellionisz, P.

    1992-01-01

    A considerable percentage (32.8% in 1989) of electric energy in Hungary is produced by nuclear power plant Paks. The paper presents an overview of activities on control and instrumentation in the following areas: Control and instrumentation upgrading; training simulators; diagnostic systems. (author). 1 tab

  7. Study on reactor power change and ambiguous control of third Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Wang Gongzhan

    2006-01-01

    The phenomenon of the average power reduction during long term full power operating in Third Qinshan nuclear power plant is analyzed . According to the basic conclusions of reactor power fluctuating derived by probability statistic and calculation the corresponding ambiguous control project is proposed. The operating performance could be achieved by the present controlling project is predicted additionally. (authors)

  8. Practice of radiation dose control for tech-modification items in Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zhang Yong; Chen Zhongyu; Xu Hongming; Fan Liguang; Jiang Jianqi; Bu Weidong

    2006-01-01

    In order to improve the safety and reliability of nuclear power plant operation, many tech-modifications related to system or equipment have been completed since operation in Qinshan NPP. this paper introduces radiation dose control for mainly tech-modifications items related to radiation, including radiation protection optimization measures and experience in aspects of item planning, program writing, process control, etc. (authors)

  9. KWU Nuclear Plant Analyzer

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  10. Consideration of Command and Control Performance during Accident Management Process at the Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed, Nisrene M. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Kim, Sok Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The accident at the Fukushima Daiichi nuclear power plants shifted the nuclear safety paradigm from risk management to on-site management capability during a severe accident. The kernel of on-site management capability during an accident at a nuclear power plant is situation awareness and agility of command and control. However, little consideration has been given to accident management. After the events of September 11, 2001 and the catastrophic Fukushima nuclear disaster, agility of command and control has emerged as a significant element for effective and efficient accident management, with many studies emphasizing accident management strategies, particularly man-machine interface, which is considered a key role in ensuring nuclear power plant safety during severe accident conditions. This paper proposes a conceptual model for evaluating command and control performance during the accident management process at a nuclear power plant. Communication and information processing while responding to an accident is one of the key issues needed to mitigate the accident. This model will give guidelines for accurate and fast communication response during accident conditions.

  11. The nuclear materials control and accountability internal audit program at the Oak Ridge Y-12 plant

    International Nuclear Information System (INIS)

    Lewis, T.J.

    1987-01-01

    The internal audit program of the Nuclear Material Control and Accountability (NMCandA) Department at the Oak Ridge Y-12 Plant, through inventory-verification audits, inventory-observation audits, procedures audits, and records audits, evaluates the adequacy of material accounting and control systems and procedures throughout the Plant; appraises and verifies the accuracy and reliability of accountability records and reports; assures the consistent application of generally accepted accounting principles in accounting for nuclear materials; and assures compliance with the Department of Energy (DOE) and NMCandA procedures and requirements. The internal audit program has significantly strengthened the control and accountability of nuclear materials through improving the system of internal control over nuclear materials, increasing the awareness of materials control and accountability concerns within the Plant's material balance areas (MBAs), strengthening the existence of audit trails within the overall accounting system for nuclear materials, improving the accuracy and timeliness of data submitted to the nuclear materials accountability system, auditing the NMCandA accounting system to ensure its accuracy and reliability, and ensuring that all components of that system (general ledgers, subsidiary ledgers, inventory listings, etc.) are in agreement among themselves

  12. Optimal sampling period of the digital control system for the nuclear power plant steam generator water level control

    International Nuclear Information System (INIS)

    Hur, Woo Sung; Seong, Poong Hyun

    1995-01-01

    A great effort has been made to improve the nuclear plant control system by use of digital technologies and a long term schedule for the control system upgrade has been prepared with an aim to implementation in the next generation nuclear plants. In case of digital control system, it is important to decide the sampling period for analysis and design of the system, because the performance and the stability of a digital control system depend on the value of the sampling period of the digital control system. There is, however, currently no systematic method used universally for determining the sampling period of the digital control system. Generally, a traditional way to select the sampling frequency is to use 20 to 30 times the bandwidth of the analog control system which has the same system configuration and parameters as the digital one. In this paper, a new method to select the sampling period is suggested which takes into account of the performance as well as the stability of the digital control system. By use of the Irving's model steam generator, the optimal sampling period of an assumptive digital control system for steam generator level control is estimated and is actually verified in the digital control simulation system for Kori-2 nuclear power plant steam generator level control. Consequently, we conclude the optimal sampling period of the digital control system for Kori-2 nuclear power plant steam generator level control is 1 second for all power ranges. 7 figs., 3 tabs., 8 refs. (Author)

  13. Fuzzy logic control for improved pressurizer systems in nuclear power plants

    International Nuclear Information System (INIS)

    Brown, Chris; Gabbar, Hossam A.

    2014-01-01

    Highlights: • Improved performance of the pressurizer system in a CANDU nuclear power plant (NPP). • Inventory control for the pressurizer system in NPP. • Compare fuzzy logic with PID in pressurizer system in NPP. • Develop a fuzzy controller to regulate the pressurizer inventory control. • Compare control performance with current proportional controller used at NPP. - Abstract: The pressurizer system in a CANDU nuclear power plant is responsible for maintaining the pressure of the primary heat transport system to ensure the plant is operated within its safe operating envelope. The inventory control for the pressurizer system use a combination of level sensors, feed valves and bleed valves to ensure that there is adequate room in the pressurizer to accommodate any swell or shrinkage in the PHT system. The Darlington Nuclear Generating Station (DNGS) in Ontario, Canada currently uses a proportional controller for the bleed and feed valves to regulate the pressurizer inventory control which can result in large coolant level overshoot along with excessive settling times. The purpose of this paper is to develop a fuzzy controller to regulate the pressurizer inventory control and compare its performance to the current proportional controller used at DNGS. The simulation of the pressurizer inventory control system shows the fuzzy controller performs better than the proportional controller in terms of settling time and overshoot

  14. Work Analysis of the nuclear power plant control room operators (II): The classes of situation

    International Nuclear Information System (INIS)

    Alengry, P.

    1989-03-01

    This report presents a work analysis of nuclear power plant control room operators focused on the classes of situation they can meet during their job. Each class of situation is first described in terms of the process variables states. We then describe the goals of the operators and the variables they process in each class of situation. We report some of the most representative difficulties encountered by the operators in each class of situation. Finally, we conclude on different topics: the nature of the mental representations, the temporal dimension, the monitoring activity, and the role of the context in the work of controlling a nuclear power plant [fr

  15. Fundamental attributes of a practical configuration management program for nuclear plant design control

    International Nuclear Information System (INIS)

    Klein, S.M.

    1988-06-01

    This summarizes the results of an evaluation of findings identifies during a number of Safety-System Functional Inspections and Safety System Outage Modification Inspections which are related to configuration management for nuclear plant design control. A computerized database of these findings was generated from a review of the design inspection reports. Based on the results of the evaluation, attributes of a configuration management program were developed which are responsive to minimizing these types of inspection findings. Incorporation of these key attributes is considered good practice in the development of a configuration management program for design control at operating nuclear plants

  16. Man-machine considerations in nuclear power plant control room design

    International Nuclear Information System (INIS)

    Tennant, D.V.

    1987-01-01

    Although human factors is a subject that has been around for a number of years, this area of design has only recently become known to the power industry. As power plants have grown in size and complexity, the instrumentation required to control and monitor plant processes has increased tremendously. This has been especially true in nuclear power facilities. Although operators are better trained and qualified, very little consideration has been devoted to man-machine interface and the limitations of human operators. This paper explores the historic aspects and design philosophy associated with nuclear plant control rooms. Current problems and solutions are explored along with the components of a control room review. Finally, a survey of future advances in control room design are offered. This paper is concerned with instrumentation, controls, and displays

  17. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey Clark [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-04-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple “pathways,” or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  18. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    International Nuclear Information System (INIS)

    Kovesdi, Casey Robert; Joe, Jeffrey Clark

    2016-01-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple ''pathways,'' or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  19. Adaptive Neural Network Algorithm for Power Control in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Husam Fayiz, Al Masri

    2017-01-01

    The aim of this paper is to design, test and evaluate a prototype of an adaptive neural network algorithm for the power controlling system of a nuclear power plant. The task of power control in nuclear reactors is one of the fundamental tasks in this field. Therefore, researches are constantly conducted to ameliorate the power reactor control process. Currently, in the Department of Automation in the National Research Nuclear University (NRNU) MEPhI, numerous studies are utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems and genetic algorithms) to enhance the performance, safety, efficiency and reliability of nuclear power plants. In particular, a study of an adaptive artificial intelligent power regulator in the control systems of nuclear power reactors is being undertaken to enhance performance and to minimize the output error of the Automatic Power Controller (APC) on the grounds of a multifunctional computer analyzer (simulator) of the Water-Water Energetic Reactor known as Vodo-Vodyanoi Energetichesky Reaktor (VVER) in Russian. In this paper, a block diagram of an adaptive reactor power controller was built on the basis of an intelligent control algorithm. When implementing intelligent neural network principles, it is possible to improve the quality and dynamic of any control system in accordance with the principles of adaptive control. It is common knowledge that an adaptive control system permits adjusting the controller’s parameters according to the transitions in the characteristics of the control object or external disturbances. In this project, it is demonstrated that the propitious options for an automatic power controller in nuclear power plants is a control system constructed on intelligent neural network algorithms. (paper)

  20. Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

    International Nuclear Information System (INIS)

    Hou, Xue Yan; Li, Shu; Li, Qing

    2011-01-01

    Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier

  1. Near-term improvements for nuclear power plant control room annunciator systems

    International Nuclear Information System (INIS)

    Rankin, W.L.; Duvernoy, E.G.; Ames, K.R.; Morgenstern, M.H.; Eckenrode, R.J.

    1983-04-01

    This report sets forth a basic design philosophy with its associated functional criteria and design principles for present-day, hard-wired annunciator systems in the control rooms of nuclear power plants. It also presents a variety of annunciator design features that are either necessary for or useful to the implementation of the design philosophy. The information contained in this report is synthesized from an extensive literature review, from inspection and analysis of control room annunciator systems in the nuclear industry and in related industries, and from discussions with a variety of individuals who are knowledgeable about annunciator systems, nuclear plant control rooms, or both. This information should help licensees and license applicants in improving their hard-wired, control room annunciator systems as outlined by NUREG-0700

  2. Optimizing the human engineering design of control panels in nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Behrendt, V.; Krehbiehl, T.; Hartfiel, H.D.; Mannhaupt, H.R.

    1986-12-01

    The study contains two parts. In the first part an analytical procedure is developed to logically and reproducibly subdivide the control room personnel tasks resulting in a list of the elements (operations) and the structure (operations scheme) of a task. The second part lists together all knowledge of and influences on human engineering which are known at this time and which should be taken into account in designing control rooms. The content of this catalogue can best be used and presented by using a personal computer. Two fundamental different ways are possible to use the catalogue. Designing new control rooms or new parts of control rooms the results of the task analysis which should be done first, should guide the search in the catalogue to find the right human engineering factors. For assessing existing control room panels the performance shaping factors which are establishing the table of content, permit a quick access to the catalogue. Both the specific procedure of the task analysis and the different ways of access to the catalogue of human engineering knowledge for designing nuclear power plant control rooms have been proven by experienced system engineers and safety experts. The results are presented. They have been considered in this version of the study. (orig.) [de

  3. Simulation research on multivariable fuzzy model predictive control of nuclear power plant

    International Nuclear Information System (INIS)

    Su Jie

    2012-01-01

    To improve the dynamic control capabilities of the nuclear power plant, the algorithm of the multivariable nonlinear predictive control based on the fuzzy model was applied in the main parameters control of the nuclear power plant, including control structure and the design of controller in the base of expounding the math model of the turbine and the once-through steam generator. The simulation results show that the respond of the change of the gas turbine speed and the steam pressure under the algorithm of multivariable fuzzy model predictive control is faster than that under the PID control algorithm, and the output value of the gas turbine speed and the steam pressure under the PID control algorithm is 3%-5% more than that under the algorithm of multi-variable fuzzy model predictive control. So it shows that the algorithm of multi-variable fuzzy model predictive control can control the output of the main parameters of the nuclear power plant well and get better control effect. (author)

  4. Nuclear power plant control and instrumentation in Switzerland

    International Nuclear Information System (INIS)

    Voumard, A.

    1992-01-01

    In Switzerland five NPPs are in operation and none is planned or is under construction. The three oldest NPPs are backfitted with an additional safety system. In the field of I and C, efforts are essentially directed to maintaining high performance and to improve the safety of the plants in operation. Three of these plants are about 20 years old and a significant part of their I and C equipment has to be replaced. This is an ongoing process which is carried out stage by stage mostly during the annual shutdown. Measures to avoid or mitigate severe accidents, including core melting, have been taken or are planned. (author). 1 tab

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

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  6. Methodology for risk-based configuration control of nuclear power plant operation

    International Nuclear Information System (INIS)

    Valle, Antonio Torres; Oliva, Jose de Jesus Rivero

    2012-01-01

    The hazardous configurations control in Nuclear Power Plants is an application of a previous Probabilistic Safety Analysis (PSA). A more complete option would be the risk monitoring for the online detection of these configurations but expert personnel would be required to deal with the complexities of PSA and risk monitor. The paper presents a simpler but effective approach: a method of configuration control, based on dependencies matrixes. The algorithm is included in a computer code called SECURE A-Z. The configuration control is carried out in a qualitative way, without previous PSA results and not using a Risk Monitor. The simplicity of the method warrants its application to facilities where these tools have not been developed, allowing the detection of hazardous configurations during operation and increasing plant safety. This configuration control system was implemented in the Embalse Nuclear Power Plant in Argentina. The paper shows the application of the algorithm to the analysis of a simplified safety system. (author)

  7. Report on the status of instrumentation and control in Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Blomberg, P.E.

    1990-01-01

    During 1988 the twelve nuclear power units in Sweden generated 69 TWh, which was 45% of the total electric power produced in Sweden. The production capacity of the nuclear power plants increased successively by upgrading the units to higher nominal power levels. The paper presents an overview of activities on control and instrumentation in the following: maintenance, renewal of the I and C systems, training. The operational data of Swedish reactor units are presented. (author). 1 tab

  8. Reactor power control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Nakajima, Kazuo.

    1980-01-01

    Purpose: To enable power control by automatic control rod operation based on the calculated amounts of operation for the control rods determined depending on a power set value from reactor operators or on power variation amounts from other devices. Constitution: When an operator designates an automatic selection by way of a control rod operation panel, automatic signals are applied to a manual-automatic switching circuit and the mode judging circuit of a rod pattern control device. Then, mode signals such as for single operation, load setting, load following and the like produced by the operator are judged in a circuit, wherein a control rod pattern operation circuit calculates the designation for the control rods and the operation amounts for the control rods depending on the designated modes and automatic control is conducted for the control rods by a rod position control circuit, a rod drive control device and the like connected at a rod position monitor device. The reactor power is thus controlled automatically to reduce the operator's labours. The automatic power control can also be conducted in the same manner by the amount of power variations applied to the device from the external device. (Yoshino, Y.)

  9. YAEC's view of the cause and control of escalating nuclear plant O and M costs

    International Nuclear Information System (INIS)

    Haseltine, J.D.; Lessard, L.P.

    1990-01-01

    This paper provides insights on this issue in terms of both the genesis and effective long-term control of O and M costs. Yankee Atomic Electric Company's (YAEC's) insights stem not only from an analysis of certain industry data, but also from its unique position within the nuclear industry in terms of its age, plant size, and organization. First, at 30 yr of age, the YAEC plant has endured the full swing of the regulatory/institutional pendulum and the associated impact on O and M costs. Second, with a size of only 185 MW(electric), YAEC's imperative since start-up has been the strict control of O and M costs while still achieving operational excellence. Finally, YAEC is an organization strictly focused on nuclear power operations and has not been distracted by fossil plant operations or other utility requirements like distribution, retail sales, etc., that may have plagued other plant operators

  10. Implementing digital instrumentation and control systems in the modernization of nuclear power plants

    International Nuclear Information System (INIS)

    2009-01-01

    The IAEA encourages greater use of good engineering and management practices by Member States. In particular, it supports activities such as nuclear power plant (NPP) performance improvement, plant life management, training, power uprating, operational license renewal and the modernization of instrumentation and control (I and C) systems of NPPs in Member States. The subject of implementing digital I and C systems in nuclear power plants was suggested by the Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) in 2003. It was then approved by the IAEA and included in the programmes for 2006-2008. As the current worldwide fleet of nuclear power plants continues ageing, the need for improvements to maintain or enhance plant safety and reliability is increasing. Upgrading NPP I and C systems is one of the possible approaches to achieving this improvement, and in many cases upgrades are a necessary activity for obsolescence management. I and C upgrades at operating plants require the use of digital I and C equipment. While modernizing I and C systems is a significant undertaking, it is an effective means to enhance plant safety and system functionality, manage obsolescence, and mitigate the increasing failure liability of ageing analog systems. Many of the planning and implementation tasks of a digital I and C upgrade project described here are also relevant to new plant design and construction since all equipment in new plants will be digital. This publication explains a process for planning and conducting an I and C modernization project. Numerous issues and areas requiring special consideration are identified, and recommendations on how to integrate the licensing authority into the process are made. To complement this report, a second publication is planned which will illustrate many of the aspects described here through experience based descriptions of I and C projects and lessons learned from those activities. It is upon these

  11. Optimization of the main control room habitability system in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Guanghui; Zhao Xinyan

    2013-01-01

    This article describes the optimization of main control room habitability system in nuclear power plant. It also describes the design shortage in terms of habitability in the main control room. Through modification and optimization, habitable conditions are met for personnel staying in the emergency area of the main control room for a period of time, with an aim to take accident intervention measures smoothly and reduce the accident loss and radioactive contamination as low as possible. (authors)

  12. Macrophytes control on a stretch of the Ebro River flowing through the Asco Nuclear Power Plant

    International Nuclear Information System (INIS)

    Munte Clua, L.; Fernandez Alentorn, E.; Beltran Grau, A.

    2010-01-01

    The objective of this paper is to evaluate the time evolution of the different macrophytes populations in the stretch of the Ebro River between the town of Flix and the Asco Nuclear Power Plant, and the effects observed by the programmed flood for their control.

  13. Uncertainty identification for robust control using a nuclear power plant model

    International Nuclear Information System (INIS)

    Power, M.; Edwards, R.M.

    1995-01-01

    An on-line technique which identifies the uncertainty between a lower order and a higher order nuclear power plant model is presented. The uncertainty identifier produces a hard upper bound in H ∞ on the additive uncertainty. This additive uncertainty description can be used for the design of H infinity or μ-synthesis controllers

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  15. Parameter identification of a BWR nuclear power plant model for use in optimal control

    International Nuclear Information System (INIS)

    Volf, K.

    1976-02-01

    The problem being considered is the modeling of a nuclear power plant for the development of an optimal control system of the plant. Current system identification concepts, combining input/output information with a-priori structural information are employed. Two of the known parameter identification methods i.e., a least squares method and a maximum likelihood technique, are studied as ways of parameter identification from measurement data. A low order state variable stochastic model of a BWR nuclear power plant is presented as an application of this approach. The model consists of a deterministic and a noise part. The deterministic part is formed by simplified modeling of the major plant dynamic phenomena. The moise part models the effects of input random disturbances to the deterministic part and additive measurement noise. Most of the model parameters are assumed to be initially unknown. They are identified using measurement data records. A detailed high order digital computer simulation is used to simulate plant dynamic behaviour since it is not conceivable for experimentation of this kind to be performed on the real nuclear power plant. The identification task consists in adapting the performance of the simple model to the data acquired from this plant simulation ensuring the applicability of the techniques to measurement data acquired directly from the plant. (orig.) [de

  16. 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)

  17. Operating control systems in advanced types of nuclear power plants

    International Nuclear Information System (INIS)

    Jeannot, A.; Quittet, Y.; Bonnemort, P.

    The report presented first gives a general description of operating control of the PHENIX reactor, covering the level of automaticity and the methods of data perception. The authors then describe the control of the core, the supervision of cooling and the detection of cladding rupture. A summary description is given of the evolution of the SUPER-PHENIX reactor from its PHENIX predecessor. As regards high temperature reactors, the report discusses control rods, the regulation of the flow of coolant gas, the system of emergency stoppage and the general systems for safety and output limitation, with special attention being paid to particular aspects of some of the control systems

  18. Strategy for improving instrumentation and control in operating nuclear power plants

    International Nuclear Information System (INIS)

    Abad Bassols, L.; Nino Perote, R.

    1996-01-01

    There are three basic reasons why nuclear power plants need to systematically upgrade their instrumentation and control equipment: Obsolete instrumentation and lack spares Little capacity of flexibility for extension Possibility of attaining better systems integration and improving systems-operations interface This article shows how to approach these issues using the following strategies: Use of distributed control systems and PLCs for control, signalling, command, communications, etc, in both nuclear and conventional applications Upgrading of process instrumentation equipment, sensors, transmitters, etc Upgrading of alarm-signalling systems In each group of equipment items consideration should be given to: Aspects regarding manufacturers-suppliers Effects on design, adaptation and documentation of operating plants Effects on the training and handling skills of operation and maintenance staff Strategy for incorporating the new system into the Plant with minimum impact on operation (Author)

  19. Fuzzy model predictive control algorithm applied in nuclear power plant

    International Nuclear Information System (INIS)

    Zuheir, Ahmad

    2006-01-01

    The aim of this paper is to design a predictive controller based on a fuzzy model. The Takagi-Sugeno fuzzy model with an Adaptive B-splines neuro-fuzzy implementation is used and incorporated as a predictor in a predictive controller. An optimization approach with a simplified gradient technique is used to calculate predictions of the future control actions. In this approach, adaptation of the fuzzy model using dynamic process information is carried out to build the predictive controller. The easy description of the fuzzy model and the easy computation of the gradient sector during the optimization procedure are the main advantages of the computation algorithm. The algorithm is applied to the control of a U-tube steam generation unit (UTSG) used for electricity generation. (author)

  20. Methods for nuclear material control used in the basic production of a typical radiochemical plant

    International Nuclear Information System (INIS)

    Kositsyn, V.F.; Mukhortov, N.F.; Korovin, Yu.I.; Rudenko, V.S.; Petrov, A.M.

    1999-01-01

    Techniques for destructive and non-destructive assay of the component and isotopic composition of nuclear materials are described, namely gravimetric, titrimetric, coulometric, mass spectrometry, as well as those based on registration of neutron and γ radiations. Their metrologic characteristics are described. The techniques described are suggested to be used for nuclear material (NM) control and accounting purposes at the model radiochemical plant for processing irradiated fuel subassemblies from power reactors. The measurement control program is also described. This program is intended for the measurement quality assurance in the framework of NM control and accountancy system [ru

  1. 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)

  2. Optimizing the roles of man and computer in nuclear power plant control

    International Nuclear Information System (INIS)

    Colley, R.W.; Seeman, S.E.

    1983-10-01

    We are presently participating in a program to optimize the functional man-machine interface for Liquid Metal-Cooled Fast Breeder Reactors. The overall objective of this program is to enhance operational safety; that is, to accommodate plant incidents through optimal integration of man and machine in performing the functions required to safely control a plant during both normal and off-normal conditions. Purpose of this talk is to describe an approach to determine the optimal roles of man and computer in the control of nuclear power plants. Purpose of this session was to get together people that are working in the areas of understanding of how operators control plants, and working on developing new aids for these operators. We were asked to explain how our modeling and approach we're taking will lead us to an optimization of the roles of the man and the computer in the control of nuclear power plants. Our emphasis was to be on the functions required for plant control, and how the attributes of the human operator and the attributes of the computer can be optimally used to enhance operational safety in performing these functions

  3. Dose control and ALARA at nuclear power plants

    International Nuclear Information System (INIS)

    Xia Yihua; Li Xutong

    1999-01-01

    With the development of NPPs in China, paying attention to dose control and ALARA at NPPs is very important. The author briefly introduces two primary tasks for exposure control at NPPs, primary consideration of ALARA and the common technical methods. It points out that adoption of some quantitative indicators is useful, but it is important to bear it in mind that these ' values of dose avoided' are situation specific

  4. Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems

    International Nuclear Information System (INIS)

    Wood, Richard Thomas; Belles, Randy; Cetiner, Mustafa Sacit; Holcomb, David Eugene; Korsah, Kofi; Loebl, Andy; Mays, Gary T.; Muhlheim, Michael David; Mullens, James Allen; Poore, Willis P. III; Qualls, A.L.; Wilson, Thomas L.; Waterman, Michael E.

    2010-01-01

    This report presents the technical basis for establishing acceptable mitigating strategies that resolve diversity and defense-in-depth (D3) assessment findings and conform to U.S. Nuclear Regulatory Commission (NRC) requirements. The research approach employed to establish appropriate diversity strategies involves investigation of available documentation on D3 methods and experience from nuclear power and nonnuclear industries, capture of expert knowledge and lessons learned, determination of best practices, and assessment of the nature of common-cause failures (CCFs) and compensating diversity attributes. The research described in this report does not provide guidance on how to determine the need for diversity in a safety system to mitigate the consequences of potential CCFs. Rather, the scope of this report provides guidance to the staff and nuclear industry after a licensee or applicant has performed a D3 assessment per NUREG/CR-6303 and determined that diversity in a safety system is needed for mitigating the consequences of potential CCFs identified in the evaluation of the safety system design features. Succinctly, the purpose of the research described in this report was to answer the question, 'If diversity is required in a safety system to mitigate the consequences of potential CCFs, how much diversity is enough?' The principal results of this research effort have identified and developed diversity strategies, which consist of combinations of diversity attributes and their associated criteria. Technology, which corresponds to design diversity, is chosen as the principal system characteristic by which diversity criteria are grouped to form strategies. The rationale for this classification framework involves consideration of the profound impact that technology-focused design diversity provides. Consequently, the diversity usage classification scheme involves three families of strategies: (1) different technologies, (2) different approaches within the same

  5. Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems

    Energy Technology Data Exchange (ETDEWEB)

    Wood, Richard Thomas [ORNL; Belles, Randy [ORNL; Cetiner, Mustafa Sacit [ORNL; Holcomb, David Eugene [ORNL; Korsah, Kofi [ORNL; Loebl, Andy [ORNL; Mays, Gary T [ORNL; Muhlheim, Michael David [ORNL; Mullens, James Allen [ORNL; Poore III, Willis P [ORNL; Qualls, A L [ORNL; Wilson, Thomas L [ORNL; Waterman, Michael E. [U.S. Nuclear Regulatory Commission

    2010-02-01

    This report presents the technical basis for establishing acceptable mitigating strategies that resolve diversity and defense-in-depth (D3) assessment findings and conform to U.S. Nuclear Regulatory Commission (NRC) requirements. The research approach employed to establish appropriate diversity strategies involves investigation of available documentation on D3 methods and experience from nuclear power and nonnuclear industries, capture of expert knowledge and lessons learned, determination of best practices, and assessment of the nature of common-cause failures (CCFs) and compensating diversity attributes. The research described in this report does not provide guidance on how to determine the need for diversity in a safety system to mitigate the consequences of potential CCFs. Rather, the scope of this report provides guidance to the staff and nuclear industry after a licensee or applicant has performed a D3 assessment per NUREG/CR-6303 and determined that diversity in a safety system is needed for mitigating the consequences of potential CCFs identified in the evaluation of the safety system design features. Succinctly, the purpose of the research described in this report was to answer the question, 'If diversity is required in a safety system to mitigate the consequences of potential CCFs, how much diversity is enough?' The principal results of this research effort have identified and developed diversity strategies, which consist of combinations of diversity attributes and their associated criteria. Technology, which corresponds to design diversity, is chosen as the principal system characteristic by which diversity criteria are grouped to form strategies. The rationale for this classification framework involves consideration of the profound impact that technology-focused design diversity provides. Consequently, the diversity usage classification scheme involves three families of strategies: (1) different technologies, (2) different approaches within

  6. Development of nuclear power plant online monitoring system using statistical quality control

    International Nuclear Information System (INIS)

    An, Sang Ha

    2006-02-01

    Statistical Quality Control techniques have been applied to many aspects of industrial engineering. An application to nuclear power plant maintenance and control is also presented that can greatly improve plant safety. As a demonstration of such an approach, a specific system is analyzed: the reactor coolant pumps (RCP) and the fouling resistance of heat exchanger. This research uses Shewart X-bar, R charts, Cumulative Sum charts (CUSUM), and Sequential Probability Ratio Test (SPRT) to analyze the process for the state of statistical control. And we made Control Chart Analyzer (CCA) to support these analyses that can make a decision of error in process. The analysis shows that statistical process control methods can be applied as an early warning system capable of identifying significant equipment problems well in advance of traditional control room alarm indicators. Such a system would provide operators with enough time to respond to possible emergency situations and thus improve plant safety and reliability

  7. Nuclear material control and accountancy in a radiochemical plant

    International Nuclear Information System (INIS)

    Crawford, J. M.

    1999-01-01

    The measurement systems in use at Savannah River Site, SRS, to determine material balance around dissolution of fuel, separation and purification of actinides to a nitrate product are described. To ensure that volume accuracy's are as expected, SRS has implemented a volumetric measurement control program to control errors and to detect anomalies. The program consists of periodic instrument calibrations, comparison of in-tank density measurements. An analytical quality control program is in place at SRS to provide assurance that analysis are reliable and to estimate and monitor method performance. Checks include the analysis of standard prior to the use of each method each shift the method is used. At SRS cumulative inventory difference is compared to the combined errors for the balance. The results from current evaluations for uranium and plutonium balances are presented [ru

  8. Impact of digital information and control system platform selection on nuclear power generating plant operating costs

    International Nuclear Information System (INIS)

    Bogard, T.; Radomski, S.; Sterdis, B.; Marta, H.; Bond, V.; Richardson, J.; Ramon, G.; Edvinsson, H.

    1998-01-01

    Information is presented on the benefits of a well-planned information and control systems (I and CS) replacement approach for aging nuclear power generating plants' I and CS. Replacement of an aging I and CS is accompanied by increases in plant profitability. Implementing a structured I and CS replacement with current technology allows improved plant electrical production in parallel with reduced I and CS operations and maintenance cost. Qualitative, quantitative, and enterprise management methods for cost benefit justification are shown to justify a comprehensive approach to I and CS replacement. In addition to the advantages of standard I and CS technologies, examples of new I and CS technologies are shown to add substantial cost benefit justification for I and CS replacements. Focus is upon I and CS replacements at nuclear power plants, however the information is applicable to other types of power generating facilities. (author)

  9. Instrumentation and control systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. It supplements Safety Standards Series No. NS-R-1: Safety of Nuclear Power Plants: Design (the Requirements for Design), which establishes the design requirements for ensuring the safety of nuclear power plants. This Safety Guide describes how the requirements should be met for instrumentation and control (I and C) systems important to safety. This publication is a revision and combination of two previous Safety Guides: Safety Series Nos 50-SG-D3 and 50-SG-D8, which are superseded by this new Safety Guide. The revision takes account of developments in I and C systems important to safety since the earlier Safety Guides were published in 1980 and 1984, respectively. The objective of this Safety Guide is to provide guidance on the design of I and C systems important to safety in nuclear power plants, including all I and C components, from the sensors allocated to the mechanical systems to the actuated equipment, operator interfaces and auxiliary equipment. This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety. It expands on paragraphs of Ref in the area of I and C systems important to safety. This publication is intended for use primarily by designers of nuclear power plants and also by owners and/or operators and regulators of nuclear power plants. This Safety Guide provides general guidance on I and C systems important to safety which is broadly applicable to many nuclear power plants. More detailed requirements and limitations for safe operation specific to a particular plant type should be established as part of the design process. The present guidance is focused on the design principles for systems important to safety that warrant particular attention, and should be applied to both the design of new I and C systems and the modernization of existing systems. Guidance is provided on how design

  10. Digitization of instrumentation and control in nuclear power plants

    International Nuclear Information System (INIS)

    Hofmann, A.; Buschhorn, W.; Pache, K.; Kimmel, W.; Hoeing, M.

    1997-01-01

    Unit 1 of the Chooz NPP was connected to the grid in August 1996. Unit 2 will soon be connected. In the western part of the center of France, not far from the town Poitiers, there is an identical construction site where likewise two NPP units are being erected. The French firm Sema Group is the supplier of the control and monitoring system (KIC) and as the prime contractor also is responsible for coordination of work and cooperation with the firm Hartmann and Braun. Hartmann and Braun developed the Contronic E automation system and are one of the major instrumentation and control suppliers for these units. (orig./DG) [de

  11. Nuclear power plant control and instrumentation in Italy

    International Nuclear Information System (INIS)

    Lantieri, A.

    1992-01-01

    The National Energy Plan (PEN) approved by the Government of Italy in August 1988 provides a programme of research and industrial development or reactors with inherent and passive safety features. For the Control Systems and Instrumentation there is the aim to define rules and design criteria, by evaluating the impact of inherent safety goals on the C and I design. The effort on man-machine interface is considered essential to increase safety and efficiency of advanced reactors. The paper briefly describes the activity in control systems and in the instrumentation area. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-09-01

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  14. Study on control method of the actuators accepting commands from different classifications in nuclear power plant

    International Nuclear Information System (INIS)

    Tang Lixue; Zhang Nan; Fan Jin; Li Liang

    2015-01-01

    The distributed control system has become the main control system for the nuclear power plant, consisting of 1E and non-1E parts. Because the safety actuators accept commands from different safety classifications, this is a difficulty of controlling those actuators in nuclear power plant. This article discusses about the control method for safety actuators accepting commands from different classifications. Firstly, one control method adopted in new nuclear power projects is introduced. Then based on this, an optimized method is raised. The new method mainly concludes two points than the adopted method: 1. The concept 'local control mode' is introduced into the signal priority logic modules, and the priority logic module turns into local mode for the non-1E control system once it accepts safety signal; 2. The 'remote control mode' is added into the module of the safety actuator in the non-1E control system, and this can make the non-1E control system abandon controlling the safety actuator when the relevant priority logic module accept the safety signal. Based on verifying the correctness of modified scheme, comparisons between the fore-and-aft schemes are provided to summary the merits of the optimized method. It is concluded that optimized scheme is better in the aspects of reliability, safety and economy. (authors)

  15. Cognitive models and computer aids for nuclear plant control room operators

    International Nuclear Information System (INIS)

    Sheridan, T.B.

    1982-01-01

    This paper reviews what is usually meant by a cognitive model of a control room operator in a nuclear power plant. It emphasizes the idea of internal (that is, mental) representation of external events and the use of such representation for the cognitive steps of attending, recognizing or learning, assessing and deciding. As computers play an increasingly important role in nuclear power plants, especially as cognitive aids to human supervisors of highly automated control systems, it is important that the software and computer interface characteristics be compatible with the operator's internal model. Specific examples discussed in this paper are in the monitoring and prediction of the plant state and in the detection and diagnosis of failures. Current trends in SPDS (safety parameter display system) and failure detection/location systems will be discussed in this regard

  16. Quality control of concrete structures in nuclear power plant, (3)

    International Nuclear Information System (INIS)

    Takahashi, Hisao; Kawaguchi, Tohru; Oike, Takeshi; Morimoto, Shoichi; Takeshita, Shigetoshi.

    1979-01-01

    In general, concrete placed in the winter season has a tendency to have lower strength at the age of 4 weeks due to low curing temperature after placement. Therefore, under the Japanese code, the target mix Proportions in the winter season are modified adding an extra correction factor based on air temperature. Meanwhile, the quality control system for mass concrete to be placed in the winter system is indistinct at this stage. It is the aim of this report to present the results of investigations to clarify the following two subjects: (1) whether the correction factor due to temperature is needed or not for mass concrete in the winter season; (2) what kind of curing should be applied to control cylinders for estimating strength of mass concrete. (author)

  17. Fault tolerant control for steam generators in nuclear power plant

    International Nuclear Information System (INIS)

    Deng Zhihong; Shi Xiaocheng; Xia Guoqing; Fu Mingyu

    2010-01-01

    Based on the nonlinear system with stochastic noise, a bank of extended Kalman filters is used to estimate the state of sensors. It can real-time detect and isolate the single sensor fault, and reconstruct the sensor output to keep steam generator water level stable. The simulation results show that the methodology of employing a bank of extended Kalman filters for steam generator fault tolerant control design is feasible. (authors)

  18. Licensing and regulatory control of nuclear power plants in Canada

    International Nuclear Information System (INIS)

    Atchison, R.J.

    1975-01-01

    The paper discusses the safety philosophy adopted in Canada, the safety criteria and regulatory requirements necessary for the application of this philosophy to reactor design and operation, and finally the means by which compliance with Board requirements is effected. It is emphasized that the effectiveness of regulatory control depends not only on the underlying philosophy but also on the detailed way in which it is applied. (orig./HP) [de

  19. Operational experience of human-friendly control and instrumentation systems for BWR nuclear power plants

    International Nuclear Information System (INIS)

    Makino, M.; Watanabe, T.; Suto, O.; Asahi, R.

    1987-01-01

    In recent BWR nuclear power plants in Japan, an advanced centralized monitoring and control system PODIA (Plant Operation by Displayed Information and Automation), which incorporates many operator aid functions, has been in operation since 1985. Main functions of the PODIA system as a computerized operator aid system are as follows. CRT displays for plant monitoring. Automatic controls and operation guides for plant operation. Stand-by status monitoring for engineered safety features during normal operation. Surveillance test procedure guides for engineered safety features. Integrated alarm display. The effectiveness of these functions have been proved through test and commercial operation. It has been obtained that operators have preferred PODIA much more than conventional monitoring and control systems

  20. Use of ABB ADVANT Power for large scale instrumentation and controls replacements in nuclear power plants

    International Nuclear Information System (INIS)

    Pucak, J.L.; Brown, E.M.

    1999-01-01

    One of the major issues facing plants planning for life extension is the viability and feasibility of modernization of a plant's existing I and C systems including the safety systems and the control room. This paper discusses the ABB approach to the implementation of large scale Instrumentation and Controls (I and C) modernization. ABB applies a segmented architecture approach using the ADVANT Power control system to meet the numerous constraints of a major I and C upgrade program. The segmented architecture and how it supports implementation of a complete I and C upgrade either in one outage or in a series of outages is presented. ADVANT Power contains standardized industrial control equipment that is designed to support 1E applications as well as turbine and non-1E process control. This equipment forms the basis for the architecture proposed for future new nuclear plant sales as well as large scale retrofits. (author)

  1. Gradual instrumentation and control upgrades in U.S. nuclear power plants

    International Nuclear Information System (INIS)

    Welk, S.

    1997-01-01

    Since the late 1980s, US nuclear power plants have been struggling with the technical and licensing realities associated with installing digital protection and control systems into existing facilities. The industry, regulators and equipment vendors are finally reaching agreements regarding acceptable practices and requirements. The present paper explains the philosophy for gradual instrumentation and control replacements being pursued and the technical issues being addressed. It also describes some of the future challenges facing the industry. (author)

  2. Study on comprehensive evaluation model for nuclear power plant control room layout

    International Nuclear Information System (INIS)

    Zhu Yiming; Liu Yuan; Fan Huixian

    2010-01-01

    A comprehensive evaluation model for layout of the main control room of nuclear power plants was proposed. Firstly the design scope and principle for the layout of the main control room were defined based on the standards, and then the index system for the comprehensive evaluation was established. Finally, comprehensive evaluation was carried out for the layout design by applying the fuzzy comprehensive evaluation method in the index system. (authors)

  3. Safety review for human factors engineering and control rooms of nuclear power plants

    International Nuclear Information System (INIS)

    Yang Mengzhuo

    1998-01-01

    Safety review for human factors engineering and control rooms of nuclear power plants (NPP) is in a forward position of science and technology, which began at American TMI severe accident and had been implemented in China. The importance and the significance of the safety review are expounded, the requirements of its scope and profundity are explained in detail. In addition, the situation of the technical document system for nuclear safety regulation on human factors engineering and control rooms of NPP in China is introduced briefly, on which the safety review is based

  4. Optimization criteria for control and instrumentation systems in nuclear power plants

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    1978-01-01

    The system of dose limitation recently recommended by the International Commission on Radiation Protection includes, as a base for deciding what is reasonably achievable in dose reduction, the optimization of radioprotection systems. This paper, after compiling relevant points in the new system, discusses the application of optimization to control and instrumentation of radioprotection systems in nuclear power plants. Furthermore, an extension of the optimization criterion to nuclear safety systems is also presented and its application to control and instrumentation is discussed; systems including majority logics are particularly scrutinized. Finally, eventual regulatory implications are described. (author)

  5. Probabilistic safety assessment for instrumentation and control systems in nuclear power plants: an overview

    International Nuclear Information System (INIS)

    Lu, Lixuan; Jiang, Jin

    2004-01-01

    Deregulation in the electricity market has resulted in a number of challenges in the nuclear power industry. Nuclear power plants must find innovative ways to remain competitive by reducing operating costs without jeopardizing safety. Instrumentation and Control (I and C) systems not only play important roles in plant operation, but also in reducing the cost of power generation while maintaining and/or enhancing safety. Therefore, it is extremely important that I and C systems are managed efficiently and economically. With the increasing use of digital technologies, new methods are needed to solve problems associated with various aspects of digital I and C systems. Probabilistic Safety Assessment (PSA) has proved to be an effective method for safety analysis and risk-based decisions, even though challenges are still present. This paper provides an overview of PSA applications in three areas of digital I and C systems in nuclear power plants. These areas are Graded Quality Assurance, Surveillance Testing, and Instrumentation and Control System Design. In addition, PSA application in the regulation of nuclear power plants that adopt digital I and C systems is also investigated. (author)

  6. Considerations on safety against seismic excitations in the project of reactor auxiliary building and control building in nuclear power plants

    International Nuclear Information System (INIS)

    Santos, S.H.C.; Castro Monteiro, I. de

    1986-01-01

    The seismic requests to be considered in the project of main buildings of a nuclear power plant are discussed. The models for global seismic analysis of nuclear power plant structures, as well as models for global strength distribution are presented. The models for analysing reactor auxiliary building and control building, which together with the reactor building and turbine building form the main energy generation complex in a nuclear power plant, are described. (M.C.K.) [pt

  7. Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

    2013-03-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

  8. Total quality control: the deming management philosophy applied to nuclear power plants

    International Nuclear Information System (INIS)

    Heising, C.D.; Wetherell, D.L.; Melhem, S.A.; Sato, M.

    1987-01-01

    In recent years, a call has come for the development of inherently safe nuclear reactor systems that cannot have large-scale accidents. In the search for the perfect inherently safe reactor system, some are calling for the institution of computerized automated control of reactors eliminating most human operators from the control room. A different approach to the problem of the control of inherently safe reactors is that both future and present nuclear power plants need to institute total quality control (TQC) to plant operations and management. The Deming management philosophy of TQC has been implemented in a wide range of industries - particularly in Japan and the US. Specific attention is given, however, to TQC implementation in the electric power industry as applied to nuclear plants. The Kansai Electric Power Company and Florida Power and Light Company have recently implemented TQC. Statistical quality control methods have been applied to monitor and control reactor variables (for example, to the steam generator water level important to start-up operations of pressurized water reactors)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

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

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  11. Wireless system controlling of electromagnetic wave distribution in nuclear power plant use

    International Nuclear Information System (INIS)

    Kuroda, Hidehiko; Kume, Naoto; Oshima, Tomomi; Takakura, Kei; Oda, Naotaka; Hasegawa, Takeshi; Odanaka, Shigeru

    2017-01-01

    Recently, wireless technologies have rapidly spread by cellular phones, smartphones and tablet devices. Wireless systems in the nuclear power plant are expected to bring various advantages such as shortening of the inspection time, online monitoring, remote control and cable reduction, etc. However, wireless systems have hardly applied to the nuclear power plant, from the point of security and electromagnetic interference (EMI). We propose a new wireless system controlling automatically electromagnetic wave distribution. In our wireless system, the transmitter / receiver modules automatically measure the wave strength and adjust the power and directivity of the wave, resulting in wireless communication only in target zones, i.e. non-influence to safety-related instruments and non-leakage of information. We will present the algorithm of the electromagnetic wave controlling and experimental results about the proposed system. (author)

  12. Evaluation of digital fault-tolerant architectures for nuclear power plant control systems

    International Nuclear Information System (INIS)

    Battle, R.E.

    1990-01-01

    This paper reports on four fault-tolerant architectures that were evaluated for their potential reliability in service as control systems of nuclear power plants. The reliability analyses showed that human- and software-related common cause failures and single points of failure in the output modules are dominant contributors to system unreliability. The four architectures are triple-modular-redundant, both synchronous and asynchronous, and also dual synchronous and asynchronous. The evaluation includes a review of design features, an analysis of the importance of coverage, and reliability analyses of fault-tolerant systems. Reliability analyses based on data from several industries that have fault-tolerant controllers were used to estimate the mean-time-between-failures of fault-tolerant controllers and to predict those failure modes that may be important in nuclear power plants

  13. Virtual control desk for operators training: a case study for a nuclear power plant simulator

    International Nuclear Information System (INIS)

    Aghina, Mauricio Alves da Cunha e

    2009-03-01

    Nuclear Power Plant (NPP) is a facility for electrical energy generation. Because of its high degree of complexity and very rigid norms of security it is extremely necessary that operators are very well trained for the NPP operation. A mistaken operation by a human operator may cause a shutdown of the NPP, incurring in a huge economical damage for the owner and for the population in the case of a electric net black out. To reduce the possibility of a mistaken operation, the NPP usually have a full scope simulator of the plant's control room, which is the physical copy of the original control room. The control of this simulator is a computer program that can generate the equal functioning of the normal one or some scenarios of accidents to train the operators in many abnormal conditions of the plant. A physical copy of the control room has a high cost for its construction, not only of its facilities but also for its physical components. The proposal of this work is to present a project of a virtual simulator with the modeling in 3D stereo of a control room of a given nuclear plant with the same operation functions of the original simulator. This virtual simulator will have a lower cost and serves for pretraining of operators with the intention of making them familiar to the original control room. (author)

  14. Cooperative control scheme for an HVDC system connected to an isolated BWR nuclear power plant

    International Nuclear Information System (INIS)

    Sakurai, T.; Goto, K.; Kawai, T.; Matori, I.; Nakao, T.; Watanabe, A.

    1983-01-01

    This paper describes a cooperative control system to achieve stable operation of an isolated BWR nuclear plant linked to an HVDC system. In the proposed control system, under normal conditions the power plant is controlled according to the generating power reference and the generator frequency deviation is adjusted by converter power control. Such frequency control is also effective in the case of AC-DC system faults. In addition to the frequency control, an overload control is provided with the HVDC system, where the DC transmission power in the sound poles is increased due to a fault detection signal from the faulty pole. Effects of the above mentioned control systems were studied using digital dynamic programs. The sets of simulation results confirmed that in the case of a DC single pole fault, the plant is able to continue operation without any use of the turbine speed control units even for a restarting failure in the faulty pole. In case of a DC two pole fault, the plant is able to continue operation, being assisted by turbine speed control units when restarting in the faulty poles succeeds. In case of an AC three-line to ground fault near the AC terminal of the converter at the sending or receiving end, the system is able to continue stable operation, being supplemented by the turbine control unit when the faulty section of the AC system is isolated by a main or back-up relaying system

  15. Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

    Energy Technology Data Exchange (ETDEWEB)

    Hou, Xue Yan; Li, Shu; Li, Qing [China Nuclear Power Operation Technology Co., Wuhan (China)

    2011-08-15

    Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier.

  16. Radiation exposure control of nuclear power plant personnel in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Mehl, J.

    1980-01-01

    The analysis of exposure records of all persons engaged in radiation work at nuclear power plants of the Federal Republic of Germany has shown that annual collective doses increase rapidly with time. The annual gross electrical energy generated from nuclear power also increases rapidly with time, corresponding to about 11% of the total gross electrical energy produced in 1977/78. Therefore, it is obvious that there is an increase of both the risk and the benefit from nuclear power production. Whether in the course of time the situation develops more towards the risk or the benefit side is learned from the history of the annual ratio of the collective dose per gross electrical energy generated. This ratio shows a significant decrease since 1972. The decrease is due to the experience gained from operation of the first-generation plants, which led to several administrative measures aimed at an improved control of the collective doses of power plant personnel in the Federal Republic of Germany. The administrative measures include, among others, the introduction of the following requirements: (a) Everyone who applies for a nuclear power plant construction licence has to provide evidence that, in the design of the plant, full use is made of the experience gained from plants in operation with respect to reduction of collective doses of the power plant personnel. (b) Everyone who engages his employees on radiation work within operations for which an operation licence is required, but which is held by others, requires a special 'contractor licence'. (c) Every person engaged in radiation work on the basis of a contractor licence must carry a special exposure record book which is registered by the competent national authority. (author)

  17. Probabilistic safety assessment- a tool for configuration control of nuclear power plants

    International Nuclear Information System (INIS)

    Vijaya, A.K.; Guptan, Rajee; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    A comprehensive configuration control programme implies a sophisticated set of risk related measures to manage and control concurrent unavailabilities of components, the possibility of functional alternative components, the outage times of the unavailable components and the frequency of critical configurations. These measures are implemented through operational and maintenance activities such as maintenance and test scheduling and scheduling of operational realignments. An appropriate risk based configuration control programme would enable plant personnel to maintain the risk level of the nuclear power plant within an acceptable range during all the operational regimes. Use of plant specific PSA to support configuration control makes it risk based. The PSA can help to identify the measures needed according to the situation to reduce risk to acceptable level. The main benefit of establishing a risk based configuration control programme is the reduction of risk peaks and the control of cumulative or average risk. It helps to ensure that as far as possible, the plant does not enter the critical, high risk situations and other risk significant configurations are avoided A plant specific PSA along with a 'Risk Monitor' can be used as an efficient tool for Configuration Control. (author)

  18. Use of control room simulators for training of nuclear power plant personnel

    International Nuclear Information System (INIS)

    2004-09-01

    Safety analysis and operational experience consistently indicate that human error is the greatest contributor to the risk of a severe accident in a nuclear power plant. Subsequent to the Three Mile Island accident, major changes were made internationally in reducing the potential for human error through improved procedures, information presentation, and training of operators. The use of full scope simulators in the training of operators is an essential element of these efforts to reduce human error. The operators today spend a large fraction of their time training and retraining on the simulator. As indicated in the IAEA Safety Guide on Recruitment, Qualification and Training of Personnel for Nuclear Power Plants, NS-G-2.8, 2002, representative simulator facilities should be used for training of control room operators and shift supervisors. Simulator training should incorporate normal, abnormal and accident conditions. The ability of the simulator to closely represent the actual conditions and environment that would be experienced in a real situation is critical to the value of the training received. The objective of this report is to provide nuclear power plant (NPP) managers, training centre managers and personnel involved with control room simulator training with practical information they can use to improve the performance of their personnel. While the emphasis in this publication is on simulator training of control room personnel using full scope simulators, information is also provided on how organizations have effectively used control room simulators for training of other NPP personnel, including simulators other than full-scope simulators

  19. The control of operational risk in nuclear power plant operations - Some cross-cultural perspectives

    International Nuclear Information System (INIS)

    Suchard, A.; Rochlin, G.

    1992-01-01

    The operation of nuclear power plants requires the management of a complex technology under exacting performance and safety criteria. Organizations operating nuclear power plants are faced with the challenge of simultaneously meeting technical, organizational, and social demands, striving toward perfection in a situation where learning by trial and error can be too costly. In this process, they interact with regulatory bodies who seek to help minimize operational risk by imposing and upholding safety standards. The character of this interaction differs in various countries, as does the larger cultural setting. The study generally pursued the question of how organizations operating complex and demanding technologies adapt to such requirements and circumstances, and how they can succeed in delivering nearly error-free performance. One aspect of this study includes the comparison of organizational and cultural environments for nuclear power plant operations in the US, France, Germany, Sweden, and Switzerland. The research involved in-depth, continuous observations on location and interviews with plant personnel, especially control operators, at one plant in each country

  20. Method for fault diagnosis of digital control systems in nuclear power plant

    International Nuclear Information System (INIS)

    Suzuki, Satoshi; Nagaoka, Yukio; Ohga, Yukiharu; Ito, Tetsuo

    1990-01-01

    This paper presents a method for localizing faulty components of control systems by replaceable parts such as print boards and cables, in a large scale plant like a nuclear power plant. Most of today's control systems form a distributed configuration including many digital controllers interconnected by data communication networks. Usually, to localize the faulty components in nuclear plant control systems, suspected faulty components are narrowed down by executing manual tests to examine whether the objects are normal or abnormal based on design documents and personnel know-how, besides the uses of self-diagnosis functions built into the control systems. In the present method, procedures of various tests including the know-how and checking of self-diagnosis functions are provided as knowledge of tests. The tests to be executed is determined by considering failure probabilities of objects, and easiness and effectiveness of testing. Then, the suspects are narrowed down sequentially based on the test result. In checking feasibility of this diagnosis method for a simulated control system, intended faults are satisfactorily localized. This method is confirmed to be practicable for diagnosis of large scale digital control systems. (author)

  1. GUIDANCE FOR NUCLEAR POWER PLANT CONTROL ROOM AND HUMAN-SYSTEM INTERFACE MODERNIZATION

    International Nuclear Information System (INIS)

    Naser, J.; Morris, G.

    2004-01-01

    Several nuclear power plants in the United States are starting instrumentation and control (I and C) modernization programs using digital equipment to address obsolescence issues and the need to improve plant performance while maintaining high levels of safety. As an integral part of the I and C modernization program at a nuclear power plant, the control room and other human-system interfaces (HSIs) are also being modernized. To support safe and effective operation, it is critical to plan, design, implement, train for, operate, and maintain the control room and HSI changes to take advantage of human cognitive processing abilities. A project, jointly funded by the Electric Power Research Institute (EPRI) and the United States Department of Energy (DOE) under the Nuclear Energy Plant Optimization (NEPO) Program, is developing guidance for specifying and designing control rooms, remote shut-down panels, HSIs etc. The guidance is intended for application by utilities and suppliers of control room and HSI modernization. The guidance will facilitate specification, design, implementation, operations, maintenance, training, and licensing activities. This guidance will be used to reduce the likelihood of human errors and licensing risk, to gain maximum benefit of implemented technology, and to increase performance. The guidance is of five types. The first is planning guidance to help a utility develop its plant-specific control room operating concepts, its plant-specific endpoint vision for the control room, its migration path to achieve that endpoint vision, and its regulatory, licensing, and human factors program plans. The second is process guidance for general HSI design and integration, human factors engineering analyses, verification and validation, in-service monitoring processes, etc. The third is detailed human factors engineering guidance for control room and HSI technical areas. The fourth is guidance for licensing. The fifth is guidance for special topics

  2. Digitized operator evaluation system for main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Chen Yu; Yan Shengyuan; Chen Wenlong

    2014-01-01

    In order to evaluate the human-machine system matching relation of main control room in nuclear power plant accurately and efficiently, the expression and parameters of operator human body model were analyzed, and the evaluation required function of digital operator was determined. Based on the secondary development technology, the digital operator evaluation body model was developed. It could choose generation, gender, operation posture, single/eyes horizon, and left/right hand up to the domain according to the needs of specific evaluation, it was used to evaluate whether display information can be visible and equipment can be touch, and it also has key evaluation functions such as workspace and character visibility at the same time. The examples show that this method can complete the evaluation work of human-machine matching relation for main control room of nuclear power plant accurately, efficiently and quickly, and achieve the most optimal human-machine coordination relationship. (authors)

  3. Advanced control and instrumentation systems in nuclear power plants. Design, verification and validation

    International Nuclear Information System (INIS)

    Haapanen, P.

    1995-01-01

    The Technical Committee Meeting on design, verification and validation of advanced control and instrumentation systems in nuclear power plants was held in Espoo, Finland on 20 - 23 June 1994. The meeting was organized by the International Atomic Energy Agency's (IAEA) International Working Group's (IWG) on Nuclear Power Plant Control and Instrumentation (NPPCI) and on Advanced Technologies for Water Cooled Reactors (ATWR). VTT Automation together with Imatran Voima Oy and Teollisuuden Voima Oy responded about the practical arrangements of the meeting. In total 96 participants from 21 countries and the Agency took part in the meeting and 34 full papers and 8 posters were presented. Following topics were covered in the papers: (1) experience with advanced and digital systems, (2) safety and reliability analysis, (3) advanced digital systems under development and implementation, (4) verification and validation methods and practices, (5) future development trends. (orig.)

  4. Study on quality control measures of static casting main pipe in PWR nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Zhenbiao; Li Guanying; Liu Zhicheng

    2013-01-01

    This study analyzes the main reasons which impact the quality of primary pipe static casting elbows in PWR-M310 nuclear power plant. The quality control measures are developed from the election and inspection of material, improving sand production and casting process, improving lean management of personnel. The static casting defects of primary pipe elbows for Fuqing Unit 1 and 2 were down to less than 50% of the former project. The quality of static casting for the primary pipe elbows was significantly improved. Moreover, the implementation saves human resources and financing to repair casting defects, and also helps to win the delivery schedule. The quality control measures are good reference for improving primary pipe casting process. This study provides valuable experience for further study of improving the quality of static casting for the primary pipe of PWR nuclear power plant. (authors)

  5. 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

  6. 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.

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

    International Nuclear Information System (INIS)

    Buisson, J.

    1985-06-01

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

  8. Savannah River Plant's Accountability Inventory Management System (AIMS) (Nuclear materials inventory control)

    International Nuclear Information System (INIS)

    Croom, R.G.

    1976-06-01

    The Accountability Inventory Management System (AIMS) is a new computer inventory control system for nuclear materials at the Savannah River Plant, Aiken, South Carolina. The system has two major components, inventory files and system parameter files. AIMS, part of the overall safeguards program, maintains an up-to-date record of nuclear material by location, produces reports required by ERDA in addition to onplant reports, and is capable of a wide range of response to changing input/output requirements through use of user-prepared parameter cards, as opposed to basic system reprogramming

  9. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    1997-01-01

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

  10. Recent activities in the field of nuclear power plant control and instrumentation in Czechoslovakia

    International Nuclear Information System (INIS)

    Rubek, J.

    1992-01-01

    The report presents a review of Czechoslovak nuclear power plants that are in operation and in the course of construction. The present state of the instrumentation of the newly built NPP's is described, and a special attention is given to work on the control of spatial power distribution in the reactor core of WWER 1000, the first unit to be installed in NPP Temelin. A project of a secondary circuit diagnostic system of this unit is described. (author). 6 refs, 1 tab

  11. Optimization for set-points and robust model predictive control for steam generator in nuclear power plants

    International Nuclear Information System (INIS)

    Osgouee, Ahmad

    2010-01-01

    Full Text: Nuclear power plants will be needed for future energy demands, which are expected to grow at different rates around the world. Lower operating cost is one of the major benefits of nuclear power plants over fossil power plants. Also, the plant availability is a key factor to economic index of a nuclear power plant. The opportunities for building new nuclear power plants around the world will depend on the need for clean energy with zero, or minimal emissions to support healthy communities, supply reliable energy with stable prices, and issues related to global warming and climate change. Compared to other types of power plants, nuclear power plants are preferred for their numerous advantages, including low operating costs, emission free operation with no smog, no acid rain, and no effect on global warming. Economic feasibility of a nuclear power plant requires for smooth and uninterrupted plant operation during electrical power demand variations. The steam generator (SG) in a nuclear power plant plays an important role in cooling of the reactor, balancing energy between reactor and turbine and producing steam for the turbine-generators. SG acts as an additional safety barrier between the nuclear reactor and the outside world also. As a result, control of the water inventory in the SG is very important to ensure continuous cooling of the nuclear reactor core, plant protection and at the same time, to prevent the SG tubes and turbine blades failure. A review of past nuclear power plant operation experiences indicates that unplanned reactor trips due to steam generator level (SGL) control have been significant contributors to plant unavailability. During low power operation, the level control is complicated by the thermal reverse effects known as 'shrink and swell'. Manual operator intervention to the SGL control system at low reactor power and to the unit upset conditions has been identified as an operator response in most nuclear power plants. In spite of

  12. Implementation of nuclear power plant simulation in start-up commissioning of reactor control system

    International Nuclear Information System (INIS)

    Yang Zongwei; Huang Tieming; Feng Guangyu; Luan Zhenhua; Lin Meng; Zhu Lizhi

    2009-01-01

    Based on the nuclear power thermal-hydraulic model, Labview graphical programming language and virtual instrument data acquisition technology, this paper describes a dedicate test platform to solve the problem that the reactor control system (RRC) can not be evaluated and analyzed far before the actual startup of the unit. By connecting the test platform to the nuclear Digital Control System (DCS), the step-by-step closed-looped test and global function test of RRC system were performed, the dynamic validation and logical function demonstration for RRC were realized, and a lot of configuration mistakes of RRC and nonconformity were solved. The test for unit 3 of Ling'ao phase II has proved that the implementation of nuclear power plant simulation in the start-up commissioning of RRC can greatly reduce the risk of normal power operation and great transient tests, with which the term of startup for overall unit test can be greatly shortened. (authors)

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  14. LEITTEC '96. Digitization of instrumentation and control in nuclear power plants

    International Nuclear Information System (INIS)

    Bauer, K.G.

    1997-01-01

    The nuclear power plants in operation in Germany have been commissioned in the years from 1968 until 1988. Their control and safety systems likewise correspond to the electronic technology available then, as e.g. discrete semi-conductor technology. The high reliability of those systems contributed a major share to the excellent operating results achieved by German nuclear power plants. However, aging of existing systems as well as spare part availability and integration of older and more recent hardware generations now are posing specific problems. Intensive work has been devoted to the retrofitting of existing systems and integration of computer-assisted control systems as well as conversion to programmable systems in order to achieve a basis permitting economically justifiable operation, acceptable also from the angle of hardware and software inspection requirements, so that the German Atomforum thought that these activities and the underlying problems would make a suitable topic for a conference. There were about 150 experts attending the one-day meeting for intensive discussion and exchange of information. The proceedings volume contains 11 of the conference papers and provides an overview of the current status and expected developments in the field of digitization of instrumentation and control in nuclear power plants.(orig./CB) [de

  15. Instrumentation and control engineering at ENACE (Argentine Nuclear Enterprise of Electric Power Plants S.A.)

    International Nuclear Information System (INIS)

    Roca, J.L.; Garzon, D.

    1987-01-01

    This paper describes the techniques used in the project of instrumentation and control for the Atucha II nuclear power plant, from the original flow diagram of the system whose instrumentation and control is requested to the functional binary diagrams and control loops, through measurement sheets and other documentation. An account of the organization and handling of this mass of information is given, using an electronic processing system of data file for the project. A brief description of the task implied in the completing and updating of these files defines the scheme in which all the documentation development associated with a given process is included. (Author)

  16. Measuring Human Performance in Simulated Nuclear Power Plant Control Rooms Using Eye Tracking

    Energy Technology Data Exchange (ETDEWEB)

    Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Brandon Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bower, Gordon Ross [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary Alexander [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hill, Rachael Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States); LeBlanc, Katya Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-11-01

    Control room modernization will be an important part of life extension for the existing light water reactor fleet. As part of modernization efforts, personnel will need to gain a full understanding of how control room technologies affect performance of human operators. Recent advances in technology enables the use of eye tracking technology to continuously measure an operator’s eye movement, which correlates with a variety of human performance constructs such as situation awareness and workload. This report describes eye tracking metrics in the context of how they will be used in nuclear power plant control room simulator studies.

  17. Measuring Human Performance in Simulated Nuclear Power Plant Control Rooms Using Eye Tracking

    International Nuclear Information System (INIS)

    Kovesdi, Casey Robert; Rice, Brandon Charles; Bower, Gordon Ross; Spielman, Zachary Alexander; Hill, Rachael Ann; LeBlanc, Katya Lee

    2015-01-01

    Control room modernization will be an important part of life extension for the existing light water reactor fleet. As part of modernization efforts, personnel will need to gain a full understanding of how control room technologies affect performance of human operators. Recent advances in technology enables the use of eye tracking technology to continuously measure an operator's eye movement, which correlates with a variety of human performance constructs such as situation awareness and workload. This report describes eye tracking metrics in the context of how they will be used in nuclear power plant control room simulator studies.

  18. Controlling engineering project changes for multi-unit, multi-site standardized nuclear power plants

    International Nuclear Information System (INIS)

    Randall, E.; Boddeker, G.; McGugin, H.; Strother, E.; Waggoner, G.

    1978-01-01

    Multibillioin dollar multiple nuclear power plant projects have numerous potential sources of engineering changes. The majority of these are internally generated changes, client generated changes, and changes from construction, procurement, other engineering organizations, and regulatory organizations. For multiunit, multisite projects, the use of a standardized design is cost effective. Engineering changes can then be controlled for a single standardized design, and the unit or site unique changes can be treated as deviations. Once an effective change procedure is established for change control of the standardized design, the same procedures can be used for control of unit or site unique changes

  19. Human factors survey of advanced instrumentation and controls technologies in nuclear plants

    International Nuclear Information System (INIS)

    Carter, R.J.

    1992-01-01

    A survey of advanced instrumentation and controls (I ampersand C) technologies and associated human factors issues in the US and Canadian nuclear industries was carried out by a team from Oak Ridge national laboratory to provide background for the development of regulatory policy, criteria, and guides for review of advanced I ampersand C systems as well as human engineering guidelines for evaluating these systems. The survey found those components of the US nuclear industry surveyed to be quite interested in advanced I ampersand C, but very cautious in implementing such systems in nuclear facilities and power plants. The trend in the facilities surveyed is to experiment cautiously when there is an intuitive advantage or short-term payoff. In the control room, the usual practice is direct substitution of digital and microprocessor-based instruments or systems that are functionally identical to the analog instruments or systems being replaced. The most advanced I ampersand C systems were found in the Canadian CANDU plants, where the newest plant has digital system in almost 100% of its control systems and in over 70% of its plant protection system. The hypothesis that properly 'introducing digital systems increases safety' is supported by the Canadian experience. The performance of these digital systems was achieved using an appropriate quality assurance program for the software development. The ability of digital systems to detect impending failures and initiate a fail-safe action, is a significant safety issue that should be of special interest to every US utility as well as to the US Nuclear Regulatory Commission. (orig.)

  20. Training simulator for nuclear power plant reactor control model and method

    International Nuclear Information System (INIS)

    Czerbuejewski, F.R.

    1975-01-01

    A description is given of a method and system for the real-time dynamic simulation of a nuclear power plant for training purposes, wherein a control console has a plurality of manual and automatic remote control devices for operating simulated control rods and has indicating devices for monitoring the physical operation of a simulated reactor. Digital computer means are connected to the control console to calculate data values for operating the monitoring devices in accordance with the control devices. The simulation of the reactor control rod mechanism is disclosed whereby the digital computer means operates the rod position monitoring devices in a real-time that is a fraction of the computer time steps and simulates the quick response of a control rod remote control lever together with the delayed response upon a change of direction

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

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  2. Aging of control and service air compressors and dryers used in nuclear power plants

    International Nuclear Information System (INIS)

    Moyers, J.C.

    1990-07-01

    This report was produced under the Detection of Defects and Degradation Monitoring of Nuclear Plant Safety Equipment element of the Nuclear Plant Aging Research Program. This element includes the identification of practical and cost-effective methods for detecting, monitoring, and assessing the severity of time-dependent degradation (aging) of control and service air compressors and dryers in nuclear power plants. These methods are to provide capabilities for establishing degradation trends prior to failure and developing guidance for effective maintenance. The topics of this Phase 1 assessment report are failure modes and causes resulting from aging, manufacturer--recommended maintenance and surveillance practices, and measurable parameters (including functional indicators) for use in assessing operational readiness, establishing degradation trends, and detecting incipient failure. the results presented are based on information derived from operating experience records, manufacturer-supplied information, and input from plant operators. For each failure mode, failure causes are listed by subcomponent, and parameters potentially useful for detecting degradation that could lead to failure are identified. 13 refs., 9 figs., 16 tabs

  3. Administrative and research needs associated with the control of occupational exposures in commercial nuclear power plants

    International Nuclear Information System (INIS)

    Moeller, D.W.

    1980-01-01

    This review of occupational exposures in commercial nuclear power plants in the United States of America has revealed that, although many problem areas are being adequately addressed, there is a need for additional work. Areas relative to exposure evaluation that need attention include better data collection and analysis as to when and where exposures occur, improved information on exposures from internally deposited radionuclides, improved techniques for monitoring occupational neutron exposures, and an upgrading in quality control procedures in the manufacture, calibration, use and maintenance of monitoring instruments. Areas relative to exposure control that need attention include the development of additional design and manufacturing approaches for preventing the production and build-up of key radionuclides within reactor cooling systems, the development and testing of techniques for removing those radionuclides that do accumulate in such systems, the application of risk/benefit assessments to procedures for the maintenance, repair, modification, replacement and disposal of major nuclear power plant components, such as steam generators, and the development of design features to facilitate the decommissioning of nuclear power plants. Professional radiation workers also have to be aware of the impact that the proposed major reductions in occupational dose limits would have on their operations. This impact is compounded by the fact that the number of people receiving graduate education in radiation protection in the USA is decreasing. (author)

  4. Methods for the computerized control of nuclear power plants for improved safety, quality, and productivity

    International Nuclear Information System (INIS)

    Heising, C.D.

    1988-12-01

    The purpose of this research project was to translate the Total Quality Control (TQC) management system to the operation of nuclear power plants. This work began on September 30, 1986 and continued through December 30, 1988 at an original funding level of $251,000. Four graduate research assistants were employed during the two year project period, with all four completing master's level degree theses or projects. In addition, several papers were presented at technical conferences regarding this work. Currently, one paper has been accepted for publication in the journal of Operations Research, and two more papers are currently being written for submission in the near future. The project also received favorable publicity at the university and elsewhere. The major findings of this work was that, indeed, the Japanese management system of Total Quality Control (TQC) may be applied to nuclear power plant operation to achieve enhanced safety and increased efficiency. Two utilities are already heavily engaged in implementing TQC at their nuclear power plants: the Kansai Electric Company of Osaka, Japan and the Florida Power and Light Company of Miami, Florida. We have documented in detail the progress of these utilities in their attempts to implement TQC, as well as highlighting ''success stories'' of TQC implementation in other industries

  5. The impact of twenty years of noise research on nuclear power plant design, instrumentation and control

    International Nuclear Information System (INIS)

    Kemeny, L.G.

    1975-01-01

    Early investigations demonstrated that time constants and the dynamic characteristics of low energy nuclear systems could be elegantly determined by correlation of spectral analysis of fluctuating signals from ion chambers and proportional counters. Analyses of the time series information and the multi-filtering operations in the frequency domain were time consuming and tedious projects due to the lack of suitable data processing equipment. During the last decade, the significant advances were the recognition of the advantages of the two-channel cross-correlation technique and the realisation that the dynamic behaviour of nuclear power plant at power could be monitored and studied in depth by the cross-correlation of mechanical, thermal and hydrodynamic signals with neutronic information. The former concept led to the development of theoretical models for spatial and energy-dependent noise fields within a nuclear system. The latter opened a floodgate of potential advances in nuclear power plant design optimization, control and safety instrumentation, and control and safety diagnostic systems. (U.K.)

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

    Science.gov (United States)

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

    2017-12-01

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

  7. Evaluation of digital fault-tolerant architectures for nuclear power plant control systems

    International Nuclear Information System (INIS)

    Battle, R.E.

    1990-01-01

    Four fault tolerant architectures were evaluated for their potential reliability in service as control systems of nuclear power plants. The reliability analyses showed that human- and software-related common cause failures and single points of failure in the output modules are dominant contributors to system unreliability. The four architectures are triple-modular-redundant (TMR), both synchronous and asynchronous, and also dual synchronous and asynchronous. The evaluation includes a review of design features, an analysis of the importance of coverage, and reliability analyses of fault tolerant systems. An advantage of fault-tolerant controllers over those not fault tolerant, is that fault-tolerant controllers continue to function after the occurrence of most single hardware faults. However, most fault-tolerant controllers have single hardware components that will cause system failure, almost all controllers have single points of failure in software, and all are subject to common cause failures. Reliability analyses based on data from several industries that have fault-tolerant controllers were used to estimate the mean-time-between-failures of fault-tolerant controllers and to predict those failures modes that may be important in nuclear power plants. 7 refs., 4 tabs

  8. Analysis results for the stereotypes regarding colors applied to the nuclear power plant control room

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Seok; Lee, Yong Hee; Lee, Hyun Chul [KAERI, Taejon (Korea, Republic of); Lee, Dhong Ha [Suwon Univ., Suwon (Korea, Republic of)

    2003-01-01

    The general public not engaged in the nuclear power plant industry have no idea of the color usage in the nuclear control room. So we converted the specific color usage situation into similar but general situations. In questionnaire, we gave subjects the general situation where color coding is applied and alternative colors which were applied to the HF010 guidelines. And we asked the subjects to choose the colors proper to the situation and to rank the colors according to the degree of suitability. Two hundred fifty college students participated in the experiment. The results suggest that we can use any color coding system in the conventional control room and the CRT in the control deck because most people have no special previous color-meaning association but red-emergency relation.

  9. Analysis results for the stereotypes regarding colors applied to the nuclear power plant control room

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Oh, In Seok; Lee, Yong Hee; Lee, Hyun Chul; Lee, Dhong Ha

    2003-01-01

    The general public not engaged in the nuclear power plant industry have no idea of the color usage in the nuclear control room. So we converted the specific color usage situation into similar but general situations. In questionnaire, we gave subjects the general situation where color coding is applied and alternative colors which were applied to the HF010 guidelines. And we asked the subjects to choose the colors proper to the situation and to rank the colors according to the degree of suitability. Two hundred fifty college students participated in the experiment. The results suggest that we can use any color coding system in the conventional control room and the CRT in the control deck because most people have no special previous color-meaning association but red-emergency relation

  10. Strategies to control zebra mussel fouling at Kewaunee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Schwartz, D.; Kasper, J.R.; Pisani, W.

    1992-01-01

    The zebra mussel, Dreissena polymorpha, is currently infesting the Great Lakes. First discovered in Lake St. Clair, it is now widespread in Lakes Erie and Ontario. The initial efforts relating to zebra mussel control at Wisconsin Public Service Corporation's (WPSC) Kewaunee Nuclear Power Plant (KNPP) precipitated from the Nuclear Regulatory Commission's (NRC) Generic Letter 89-13 regarding fouling of service water (SW) systems at nuclear power plants. In the summer of 1990, Stone and Webster Engineering Corporation (Stone and Webster) was contracted to perform an evaluation of known problems within the SW system. The purposes of the study were to evaluate the actual and potential magnitude of these problems, to evaluate corrective actions to resolve the problems, and to prepare recommendations which would adequately address the issues. Two of the recommendations of this study were to continue a zebra mussel monitoring program which WPSC had already implemented and to evaluate various biocide injection programs should one be required for zebra mussel control. The concern of utilities operating power stations which use waters infested with zebra mussels as their source of cooling and/or makeup water is that mussels (both adults and veligers) will enter plant water systems and foul piping and heat exchangers. This type of fouling can restrict flow through piping, process equipment, and heat exchangers. This type of fouling can restrict flow through piping, process equipment, and heat exchangers, thereby increasing head losses and reducing heat transfer capabilities. The greatest concern in that fouling of this type is within safety-related piping and equipment that are components of service water systems at nuclear power plants

  11. Control room modernization at Finnish nuclear power plants - Two projects compared

    International Nuclear Information System (INIS)

    Laarni, J.; Norros, L.

    2006-01-01

    The modernization of automation systems and human-machine interfaces is a current issue at both of the two nuclear power plants (i.e., Fortum's Loviisa plant and TVO's Olkiluoto plant) in Finland. Since the plants have been launched in the 1970's or 1980's, technology is in part old-fashioned and needs to be renewed. At Olkiluoto upgrades of the turbine operator systems have already been conducted; at Loviisa the first phase of the modernization project has just started. Basically, there is a question of the complete digitalization of the information streams at the two plants, and transition from a conventional hard-wired or hybrid control room to a screen-based one. The new human-machine interfaces will comprise new technology, such as PC workstations, soft control, touch screens and large-screen overall displays. The modernization of human-system interfaces is carried out in a stepwise manner at both plants. At both plants the main driver has not been the need to renew the user interfaces of the control room, but the need to upgrade the automation systems. In part because of this, there is a lack of a systematic top-down approach in which different aspects of human factors (HF) engineering are considered in relationship to higher level goals. Our aim here is to give an overview description of the control room modernization projects at the two plants and provide a preliminary evaluation of their progress to date. The projects are also compared, for example, in terms of duration, scope and phasing, and who is responsible for the realization of the project. In addition, we also compare experiences from the Finnish projects to experiences from similar projects abroad. The main part of the data used in this study is based on designers' and project members' interviews. (authors)

  12. Nuclear plants - military hostages

    International Nuclear Information System (INIS)

    Ramberg, B.

    1986-01-01

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

  13. Applying Human Factors Evaluation and Design Guidance to a Nuclear Power Plant Digital Control System

    Energy Technology Data Exchange (ETDEWEB)

    Thomas Ulrich; Ronald Boring; William Phoenix; Emily Dehority; Tim Whiting; Jonathan Morrell; Rhett Backstrom

    2012-08-01

    The United States (U.S.) nuclear industry, like similar process control industries, has moved toward upgrading its control rooms. The upgraded control rooms typically feature digital control system (DCS) displays embedded in the panels. These displays gather information from the system and represent that information on a single display surface. In this manner, the DCS combines many previously separate analog indicators and controls into a single digital display, whereby the operators can toggle between multiple windows to monitor and control different aspects of the plant. The design of the DCS depends on the function of the system it monitors, but revolves around presenting the information most germane to an operator at any point in time. DCSs require a carefully designed human system interface. This report centers on redesigning existing DCS displays for an example chemical volume control system (CVCS) at a U.S. nuclear power plant. The crucial nature of the CVCS, which controls coolant levels and boration in the primary system, requires a thorough human factors evaluation of its supporting DCS. The initial digital controls being developed for the DCSs tend to directly mimic the former analog controls. There are, however, unique operator interactions with a digital vs. analog interface, and the differences have not always been carefully factored in the translation of an analog interface to a replacement DCS. To ensure safety, efficiency, and usability of the emerging DCSs, a human factors usability evaluation was conducted on a CVCS DCS currently being used and refined at an existing U.S. nuclear power plant. Subject matter experts from process control engineering, software development, and human factors evaluated the DCS displays to document potential usability issues and propose design recommendations. The evaluation yielded 167 potential usability issues with the DCS. These issues should not be considered operator performance problems but rather opportunities

  14. Nuclear power plant monitoring and control system software: verification and validation

    International Nuclear Information System (INIS)

    Kaneda, M.; Niki, K.; Shibata, K.

    1986-01-01

    The design philosophy, configuration, and production of process computer system software used for the monitoring and control of nuclear power plants are presented in detail. To achieve a very complex software system that not only has excellent performance, high reliability, and full fail safe protection, but also is easy to produce, verify, and validate, and has flexibility for future modifications, we developed the following software production system to support safe operation of nuclear power stations. The fundamental design philosophy of our monitoring and control system software is the complete separation of program logic from the data base. The logic section is highly standardized and applicable to a wide range of power generation plant computer application systems. The plant-unique properties and characteristics are all described in the data base. This separation of logic and data base has a dramatic effect on the reliability and productivity of the software system. One of the main features of the data base system is the use of easy-to-learn, easy-to-use, problem-oriented language that enables non-programmers to build up the data base using simple fill-in-the-blank type tables. The generation of these tables is fully automated, and the full set of online table editing utility software, which runs on the target plant process computer, has proven very effective in incorporation of changes and modifications at the site. (author)

  15. Changes in control room at Swedish nuclear power plants; Kontrollrumsfoeraendringar vid svenska kaernkraftverk

    Energy Technology Data Exchange (ETDEWEB)

    Kecklund, Lena [MTO Psykologi, Huddinge (Sweden)

    2005-09-15

    The Swedish nuclear power plants were commissioned during a period between 1972 and 1985 and the instrumentation and control equipment are basically from that period. For several years there have been plans made for changes in all the nuclear power plants and to a certain extent the changes in control equipment and monitoring rooms have also been implemented. The object of this project was to make a comprehensive review of the changes in control room design implemented in the Swedish nuclear power plants and to describe how the MTO- (Man-Technology-Organisation) and (Man-Machine-Interface) -issues have been integrated in the process. The survey is intended to give an overall picture of the changes in control room design and man-machine-interface made in the Swedish control rooms, in order to get a deeper knowledge of the change management process and its results as well as of the management of MTO-issues in these projects. The units included in this survey are: Oskarhamn reactor 2 and 3; Ringhals reactor 2, 3 and 4; Forsmark reactor 1, 2 and 3. The Oskarshamn 1 unit has not been included in this report as it has recently undergone an extensive modernisation program as well as a detailed inspection by the SKI (Swedish Nuclear Power Inspectorate). At Ringhals 2 the modernisation work is carried out at present and the unit is also subjected to extensive inspection activities carried out by SKI and is therefore not part of this survey. This report also includes a short description of relevant standards and requirements. Then follows a presentation of the results of the plant survey, presented as case studies for three companies OKG, Ringhals and FKA. Control room changes are summarized as well as the results on specific MTO issues which has been surveyed. In all the power companies there is a joint way of working with projects concerning plant modifications. This process is described for each company separately. In the concluding of the report the strengths and

  16. Development of a test bed for operator aid and advanced control concepts in nuclear power plants

    International Nuclear Information System (INIS)

    Turinsky, P.J.; Doster, J.M.; Kim, K.D.; Al-Chalabi, R.M.; Khedro, T.; Sues, R.H.; Yacout, A.M.

    1990-01-01

    A great amount of research and development is currently under way in the utilization of artificial intelligence (AI), expert system, and control theory advances in nuclear power plants as a basis for operator aids and automatic control systems. This activity requires access to the measured dynamic responses of the plant to malfunction, operator- or automatic-control-initiated actions. This can be achieved by either simulating plant behavior or by using an actual plant. The advantage of utilizing an actual plant versus a simulator is that the true behavior is assured of both the power generation system and instrumentation. Clearly, the disadvantages of using an actual plant are availability due to licensing, economic, and risk constraints and inability to address accident conditions. In this work the authors have decided to employ a functional one-ninth scale model of a pressurized water reactor (PWR). The scaled PWR (SPWR) facility is a two-loop representation of a Westinghouse PWR utilizing freon as the working fluid and electric heater rods for the core. The heater rods are driven by a neutron kinetics model accounting for measured thermal core conditions. A control valve in the main steam line takes the place of the turbine generator. A range of normal operating and accident situations can be addressed. The SPWR comes close to offering all the advantages of both a simulator and an actual physical plant in regard to research and development on AI, expert system, and control theory applications. The SPWR is being employed in the development of an expert-system-based operator aid system. The current status of this project is described

  17. Pulsed nuclear power plant

    International Nuclear Information System (INIS)

    David, C.V.

    1986-01-01

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

  18. Performance-based evaluation of graphic displays for nuclear-power-plant control rooms

    International Nuclear Information System (INIS)

    Petersen, R.J.; Banks, W.W.; Gertman, D.I.

    1982-01-01

    This paper reports several methodologies for evaluating the perceptual and perceptual/decision making aspects of displays used in the control rooms of nuclear power plants. This NRC funded study focuses upon the Safety Parameter Display System (SPDS) and relates the utility of the display to objective performance and preference measures obtained in experimental conditions. The first condition is a traditional laboratory setting where classical experimental methodologies can be employed. The second condition is an interactive control room simulation where the operator's performance is assessed while he/she operates the simulator. The third condition is a rating scale designed to assess operator preferences and opinions regarding a variety of display formats. The goal of this study is the development of a cost-efficient display evaluation methodology which correlates highly with the operator's ability to control a plant

  19. Building of a CAD system for instrumentation and control system of nuclear power plant

    International Nuclear Information System (INIS)

    Ma Zhicai; Hu Chunping; Zhang Dongsheng

    2012-01-01

    Base on the analysis of deign documents and process, a database for instrumentation and control system design can be developed with a popular desktop relational database management system (RDBMS). With the RDBMS, an instrumentation and control system CAD system can be built unitizing database link feature of popular CAD software, with the function of management of design data, output of list and forms. and design of drawings. A CAD system of this kind has been used in the design practice of nuclear power plant. With this system, it is shown that, the consistency of information has been controlled and the load on the engineer has been significantly reduced. The methodology used here can also be used in the CAD system for CAP1000 and CAP1400 plant. (authors) series

  20. Development of a remote monitoring and control system for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Seung Jun; Kim, Jong Hyun; Seong, Poong Hyun

    2002-01-01

    Nuclear Power Plants (NPPs) will be highly connected network enabled system and need to be monitored and controlled round the clock for high safety and availability. Using the network and web enabled tools, NPPs can be monitored remotely by operators at anytime from any place connected to the network via a general web browser. However, there are security and performance issues associated with such tools, as will be further discussed further. We developed a web-based Remote Monitoring and Control System (RMCS) that uses prevalent web technology. This work, as a preliminary study, performed the conceptual design of the web-based RMCS and developed the prototype

  1. Dimensional control of buttwelding pipe fitting for nuclear power plant Class 1 piping systems

    International Nuclear Information System (INIS)

    Rodabaugh, E.C.; Moore, S.E.; Robinson, J.N.

    1976-11-01

    Dimensional controls of wrought steel buttwelding fittings are examined from the standpoint of design adequacy. A fairly large number of fittings were purchased from different manufacturers. The dimensions of each fitting were measured and correlated along with additional information obtained from the manufacturers in an effort to establish ''standard'' shapes. This information and a critical examination of the present ANSI standards is used to develop a ''Supplementary Standard.'' The Supplementary Standard is intended to provide improved dimensional control and more complete design information for fittings used in Class 1 nuclear power plant piping systems

  2. Limitation for performance of jobs in power unit control room of nuclear power plant

    International Nuclear Information System (INIS)

    Janas, D.

    1988-01-01

    The procedure is described for an analysis of the somatic and mental health condition of operating personnel in the unit control room of a nuclear power plant. It was divided into three stages, viz.: (1) determination of adverse and favorable effects of work; (2) the recording of social, psychological, physiological and biochemical changes in the personnel; (3) determination of possibilities of controlling the limit for performance of a job. The analysis showed that the problem is complex and should permanently remain in the centre of attention. (J.B.). 3 refs

  3. National report on nuclear power plant control and instrumentation in Czechoslovakia

    International Nuclear Information System (INIS)

    Stirsky, P.; Karpeta, C.

    1986-01-01

    Research, development and design efforts in the field of nuclear power plant I and C systems in Czechoslovakia have been recently aimed at solving the following problems: setting the parameters of the WWER 440 units control and protection systems and testing them in the power phase of commissioning; design and simulation of the WWER 440 units control system performance under the conditions of steam bleeding for a centralized heat supply system; development of a simulation model of the unit WWER 1000 dynamics for the purpose of I and C systems investigation and design; design of innovated I and C systems for WWER 440 and WWER 1000 units

  4. Dynamic flowgraph modeling of process and control systems of a nuclear-based hydrogen production plant

    Energy Technology Data Exchange (ETDEWEB)

    Al-Dabbagh, Ahmad W. [Faculty of Engineering and Applied Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario (Canada); Lu, Lixuan [Faculty of Energy Systems and Nuclear Science, Faculty of Engineering and Applied Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario (Canada)

    2010-09-15

    Modeling and analysis of system reliability facilitate the identification of areas of potential improvement. The Dynamic Flowgraph Methodology (DFM) is an emerging discrete modeling framework that allows for capturing time dependent behaviour, switching logic and multi-state representation of system components. The objective of this research is to demonstrate the process of dynamic flowgraph modeling of a nuclear-based hydrogen production plant with the copper-chlorine (Cu-Cl) cycle. Modeling of the thermochemical process of the Cu-Cl cycle in conjunction with a networked control system proposed for monitoring and control of the process is provided. This forms the basis for future component selection. (author)

  5. Tricon hardware controller implementation of CANDU nuclear power plant shutdown system

    International Nuclear Information System (INIS)

    Zahedi, P.

    2007-01-01

    This paper introduces the implementation of logic functions associated with the shutdown systems of CANDU nuclear power plants. The experimental aspects of this work include development of control program embedded in shutdown systems of CANDU based NPPs. A physical test environment is designed to simulate the measurements of in-core flux detector (ICFD) and ion chamber (I/C) signals. The programmable logic used in this experimentation provides Triple Modular Redundant (TMR) architecture as well as a voting mechanism used upon execution of control program on each independent channel. (author)

  6. A foundation for allocating control functions to humans and machines in future CANDU nuclear power plants

    International Nuclear Information System (INIS)

    Lupton, L.R.; Lipsett, J.J.; Davey, E.C.; Olmstead, R.A.

    1990-06-01

    Since the control room for the Atomic Energy of Canada Limited CANDU 6 plant was designed in the 1970s, requirements for control rooms have changed dramatically as a result of new licensing requirements, evolution of major new standards for control centre design and technological advances. The role of the human operator has become prominent in the design and operation of industrial and, in particular, nuclear plants. Major industrial accidents in the last decade have highlighted the need for paying significantly more attention to the requirements of the human as an integral part of the plant control system. A Functional Design Methodology has been defined that addresses the issues related to maximizing the strengths of the human and the machine in the next generation of CANDU plants. This method is based, in part, on the recently issued international standard IEC 964. The application of this method will lead to the definition of the requirements for detailed design of the control room, including man-machine interfaces, preliminary operating procedures, staffing and training. Further, it provides a basis for the verification and validation of the allocation of functions to the operator and the machine

  7. Recent movements and some topics on nuclear power plant control and instrumentation in Japan from 1984 to 1986

    International Nuclear Information System (INIS)

    Wakayama, N.

    1986-01-01

    Extensive works have been carried out in Japan in the field of nuclear power plants control and instrumentation, and many fruitful results have been obtained. This paper aims to introduce such progress and topics obtained since 1984 in this field

  8. Natural interfaces for interacting with a virtual control desk of a nuclear power plant simulator

    International Nuclear Information System (INIS)

    Aghina, Mauricio Alves da Cunha e

    2012-01-01

    Due to very strict standards of safe operation of a nuclear power plant operators must be well trained so they can operate it within the necessary safety procedures. This is done through training simulators, which enable the user operation, as close as possible to the real control desk, and can be inserted accident situations, so they train, how to return the plant to a normal operating condition. Normally is used two types of simulator. Preferred is the full scope simulator, what is a computational dynamics program of the plant used in conjunction with a physical replica of the control desk, but this type of simulator involves a high construction cost. The second type is what uses synoptic windows of various regions of the original control desk, its construction cost is smaller, but it have a little fidelity to the original appearance of the table. Currently, with the use of virtual reality, control desks can be modeled in 3D, making the simulator interface is very similar to the appearance of the real control desk with a low cost construction. This work shows the use of natural interfaces for operator interaction with the virtual control desk, in order that it does not use any mechanical device for displaying and acting with it. For procedures that were used, such as: computer vision to recognize the position of the operator's and observation of their hands to the work of the desk controls and voice recognition. (author)

  9. Computerization of nuclear material accounting and control at storage facilities of RT-1 plant, PA Mayak

    International Nuclear Information System (INIS)

    Krakhmal'nik, V.I.; Menshchikov, Yu.L.; Mozhaev, D.A.

    1999-01-01

    Computerized system for nuclear material (NM) accounting and control at RT-1 plant is being created on the basis of advanced engineering and programming tools, which give a possibility to ensure prompt access to the information required, to unify the accounting and report documentation, make statistical processing of the data, and trace the NM transfers in the chain of its storage at facilities of RT-1 plant. Currently, the accounting is performed in parallel, both by the old methods and with computerized system. The following functions are performed by the system at the current stage: input of data on the end product's (plutonium dioxide) quantitative and qualitative composition; data input on the localization of containers with finished products at storage facilities of the plant and the product's temporary characteristics; selective verification of the data on containers and batches, according to the criteria prespecified by the user; data protection against unauthorized access; data archiving; report documents formation and providing [ru

  10. Aging Management Guideline for commercial nuclear power plants: Motor control centers

    International Nuclear Information System (INIS)

    Toman, G.; Gazdzinski, R.; O'Hearn, E.

    1994-02-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

  11. Experience feedback of operational events of the control rod assembly and its drive mechanism in nuclear power plants

    International Nuclear Information System (INIS)

    Zhou Hong; Xiao Zhi; Tao Shusheng; Zheng Lixin; Chen Zhaolin

    2013-01-01

    Seventeen operational events of the control rod assembly and its drive mechanism are collected from 1992 to 2012 important nuclear operational events and feedback in referred nuclear power plants. After investigated and classified, several important issues, such as the impact of control rod swell and fuel assembly distortion, control rod drive mechanism leakage, and the control system reliability of control rod, are emphatically analyzed. Some suggestions of experience feedback are proposed. (authors)

  12. Modernizing and Maintaining Instrumentation and Control Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Naser, Joseph; Torok, Raymond; Shankar, Ramesh

    2003-01-01

    Deregulation of the electric utilities has made a major impact on nuclear power plants. To be competitive, more emphasis is being put on cost-effective production of electricity with a more critical look at whether a system should be modernized due to obsolescence, reliability, or productivity concerns. Instrumentation and control (I and C) systems play an important role in reducing the cost of producing electricity while maintaining or enhancing safety. Systems that are well designed, reliable, enhance productivity, and are cost-effective to operate and maintain can reduce the overall costs. Modern technology with its ability to better provide and use real-time information offers an effective platform for modernizing systems. At the same time, new technology brings new challenges and issues, especially for safety systems in nuclear power plants. To increase competitiveness, it is important to take advantage of the opportunities offered by modern technology and to address the new challenges and issues in a cost-effective manner. The Electric Power Research Institute (EPRI) and its member utilities have been working together with other members of the nuclear industry since 1990 to address I and C modernization and maintenance issues. The EPRI I and C Program has developed a life-cycle management approach for I and C systems that involves the optimization of maintenance, monitoring, and capital resources to sustain safety and performance throughout the plant life. Strategic planning methodologies and implementation guidelines addressing digital I and C issues in nuclear power plants have been developed. Work is ongoing in diverse areas to support the design, implementation, and operation of new digital systems. Technology transfer is an integral part of this I and C program

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

    International Nuclear Information System (INIS)

    Liu Dong; Wang Hongyin; Zhang Yong

    2013-01-01

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

  14. Beloyarsk Nuclear Power Plant

    International Nuclear Information System (INIS)

    1997-01-01

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

  15. Improvements and standardization of communication means for control room personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Preuss, W.; Eggerdinger, C.; Sieber, R.

    1982-01-01

    This report describes the findings of an investigation into selected communication means for control room personnel in nuclear power stations. The study can be seen as a contribution to the systematic analysis of major problem areas which were identified in the general study 'Human factors in the nuclear power plant'. The subjects under investigation were the 'Shift book', 'Simulation book', and 'Technical and organisational changes and their records'. It was intended to analyse both the communication, processes and the associated written documentation in order to determine areas for potential improvement and possibilities for standardization. Information was obtained by interviewing shift members and their supervisors, by general observation, and by compilation and evaluation of the extensive dokumentation. Assessment criteria were developed on a scientific basis and in the course of the investigation, in particular from ergonomic findings, as well as from standards and regulations and comparison between the plants. General practical suggestions were developed for the improvement of the communication forms and the formal design of the documents and their contents. The transfer of the recommendations to practical use in the plants presupposes the consideration of plant-specific frames of reference. The report includes a compilation and listing of suggestions for improvement in topical subdivisions. (orig.) [de

  16. Nuclear power plant control room crew task analysis database: SEEK system. Users manual

    International Nuclear Information System (INIS)

    Burgy, D.; Schroeder, L.

    1984-05-01

    The Crew Task Analysis SEEK Users Manual was prepared for the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission. It is designed for use with the existing computerized Control Room Crew Task Analysis Database. The SEEK system consists of a PR1ME computer with its associated peripherals and software augmented by General Physics Corporation SEEK database management software. The SEEK software programs provide the Crew Task Database user with rapid access to any number of records desired. The software uses English-like sentences to allow the user to construct logical sorts and outputs of the task data. Given the multiple-associative nature of the database, users can directly access the data at the plant, operating sequence, task or element level - or any combination of these levels. A complete description of the crew task data contained in the database is presented in NUREG/CR-3371, Task Analysis of Nuclear Power Plant Control Room Crews (Volumes 1 and 2)

  17. Results of automatic system implementation for the friction control rods execution in Cofrentes nuclear power plant

    International Nuclear Information System (INIS)

    Curiel, M.; Palomo, M. J.; Urrea, M.; Arnaldos, A.

    2010-10-01

    The purpose of this presentation is to show the obtained results in Cofrentes nuclear power plant (Spain) of control rods Pcc/24 friction test procedure. In order to perform this, a control rod friction test system has been developed. Principally, this system consists on software and data acquisition hardware that obtains and analyzes the control rod pressure variation on which the test is being made. The Pcc/24 procedure objective is to detect an excessive friction in the control rod movement that could cause a control rod drive movement slower than usual. This test is necessary every time that an anomalous alteration is produced in the reactor core that could affect to a fuel rod, and it is executed before the time measure of control rods rapid scram test of the affected rods. This test has to be carried out to all the reactor control rods and takes valuable time during plant refuelling. So, by means of an automatic system to perform the test, we obtain an important time saving during refuelling. On the other hand, the on-line monitoring of the control rod insertion and changes in differential pressure, permits a control rod operation fast and safe validation. Moreover, an automatic individual report of every rod is generated by the system and a final global result report of the entire test developed in refuelling is generated. The mentioned reports can be attached directly to the procedure documents obtaining an office data processing important saving time. (Author)

  18. Results of automatic system implementation for the friction control rods execution in Cofrentes nuclear power plant

    International Nuclear Information System (INIS)

    Palomo, M.; Urrea, M.; Arnaldos, A.

    2011-01-01

    The purpose of this presentation is to show the obtained results in Cofrentes Nuclear Power Plant (Spain) of Control Rods PCC/24 Friction Test Procedure. In order to perform this, a Control Rod Friction Test System has been developed. Principally, this system consists on software and data acquisition hardware that obtains and analyzes the control rod pressure variation on which the test is being made. The PCC/24 Procedure objective is to detect an excessive friction in the control rod movement that could cause a CRD (Control Rod Drive) movement slower than usual. This test is necessary every time that an anomalous alteration is produced in the reactor core that could affect to a fuel rod, and it is executed before the time measure of control rods rapid scram test of the affected rods. This test has to be carried out to all the reactor control rods and takes valuable time during plant refuelling. So, by means of an automatic system to perform the test, we obtain an important time saving during refuelling. On the other hand, the on-line monitoring of the control rod insertion and changes in differential pressure, permits a control rod operation fast and safe validation. Moreover, an automatic individual report of every rod is generated by the system and a final global result report of the entire test developed in refuelling is generated. The mentioned reports can be attached directly to the procedure documents obtaining an office data processing important saving time.(author)

  19. Results of automatic system implementation for the friction control rods execution in Cofrentes nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, M., E-mail: mpalomo@iqn.upv.es [Universidad Politecnica de Valencia (UPV) (Spain); Urrea, M., E-mail: matias.urrea@iberdrola.es [Iberdrola Generacion S.A. Valencia (Spain). C.N. Cofrentes; Curiel, M., E-mail: m.curiel@lainsa.com [Logistica y Acondicionamientos Industriales (LAINSA), Valencia (Spain); Arnaldos, A., E-mail: a.arnaldos@titaniast.com [TITANIA Servicios Teconologicos, Valencia (Spain)

    2011-07-01

    The purpose of this presentation is to show the obtained results in Cofrentes Nuclear Power Plant (Spain) of Control Rods PCC/24 Friction Test Procedure. In order to perform this, a Control Rod Friction Test System has been developed. Principally, this system consists on software and data acquisition hardware that obtains and analyzes the control rod pressure variation on which the test is being made. The PCC/24 Procedure objective is to detect an excessive friction in the control rod movement that could cause a CRD (Control Rod Drive) movement slower than usual. This test is necessary every time that an anomalous alteration is produced in the reactor core that could affect to a fuel rod, and it is executed before the time measure of control rods rapid scram test of the affected rods. This test has to be carried out to all the reactor control rods and takes valuable time during plant refuelling. So, by means of an automatic system to perform the test, we obtain an important time saving during refuelling. On the other hand, the on-line monitoring of the control rod insertion and changes in differential pressure, permits a control rod operation fast and safe validation. Moreover, an automatic individual report of every rod is generated by the system and a final global result report of the entire test developed in refuelling is generated. The mentioned reports can be attached directly to the procedure documents obtaining an office data processing important saving time.(author)

  20. Results of automatic system implementation for the friction control rods execution in Cofrentes nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Curiel, M. [Logistica y Acondicionamientos Industriales SAU, Sorolla Center, local 10, Av. de las Cortes Valencianas, 46015 Valencia (Spain); Palomo, M. J. [ISIRYM, Universidad Politecnica de Valencia, Camino de Vera s/n, Valencia (Spain); Urrea, M. [Iberdrola Generacion S. A., Central Nuclear Cofrentes, Carretera Almansa Requena s/n, 04662 Cofrentes, Valencia (Spain); Arnaldos, A., E-mail: m.curiel@lainsa.co [TITANIA Servicios Tecnologicos SL, Sorolla Center, local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain)

    2010-10-15

    The purpose of this presentation is to show the obtained results in Cofrentes nuclear power plant (Spain) of control rods Pcc/24 friction test procedure. In order to perform this, a control rod friction test system has been developed. Principally, this system consists on software and data acquisition hardware that obtains and analyzes the control rod pressure variation on which the test is being made. The Pcc/24 procedure objective is to detect an excessive friction in the control rod movement that could cause a control rod drive movement slower than usual. This test is necessary every time that an anomalous alteration is produced in the reactor core that could affect to a fuel rod, and it is executed before the time measure of control rods rapid scram test of the affected rods. This test has to be carried out to all the reactor control rods and takes valuable time during plant refuelling. So, by means of an automatic system to perform the test, we obtain an important time saving during refuelling. On the other hand, the on-line monitoring of the control rod insertion and changes in differential pressure, permits a control rod operation fast and safe validation. Moreover, an automatic individual report of every rod is generated by the system and a final global result report of the entire test developed in refuelling is generated. The mentioned reports can be attached directly to the procedure documents obtaining an office data processing important saving time. (Author)

  1. Potential safety enhancements to nuclear plant control: proof testing at EBR-II

    International Nuclear Information System (INIS)

    Lindsay, R.W.; Chisholm, G.H.

    1984-01-01

    Future changes in nuclear plant control and protective systems will reflect an evolutionary improvement through increased use of computers coupled with a better integration of man and machine. Before improvements can be accepted into the licensed commercial plant environment, significant testing must be accomplished to answer safety questions and to prove the worth of new ideas. The Experimental Breeder Reactor-II (EBR-II) is being used as a test-bed for both in-house development and testing for others in a DOE sponsored Man-Machine Integration program. The ultimate result of the development and testing would be a control system for which safety credit could be taken in the licensing process

  2. Water Chemistry Control Technology to Improve the Performance of Nuclear Power Plants for Extended Fuel Cycles

    International Nuclear Information System (INIS)

    Maeng, W. Y.; Na, J. W.; Lee, E. H.

    2010-07-01

    Ο To Develop the technology to manage the problems of AOA and radiation, corrosion as long term PWR operation. Ο To Establish the advanced water chemical operating systems. - Development of the proper water chemistry guidelines for long term PWR operation. AOA(Axial Offest Anomaly) has been reported in many PWR plants in the world, including Korea, especially in the plants of higher burn-up and longer cycle operation or power up-rate. A test loop has been designed and made by KAERI, in order to investigate and mitigate AOA problems in Korea. This project included the study of hydrodynamic simulation and the modeling about AOA. The analysis of radioactive crud was performed to investigate of NPPs primary water chemical effect on AOA and to reduce the radioactive dose rate. The high temperature measurement system was developed to on-line monitor of water chemistry in nuclear power plants. The effects of various environmental factors such as temperature, pressure, and flow rate on YSZ-based pH electrode were evaluated for ensuring the accuracy of high-temperature pH measurement. The inhibition technology for fouling and SCC of SG tube was evaluated to establish the water chemistry technology of corrosion control of nuclear system. The high temperature and high pressure crevice chemistry analysis test loop was manufactured to develop the water chemistry technology of crevice chemistry control

  3. Steam Generator control in Nuclear Power Plants by water mass inventory

    Energy Technology Data Exchange (ETDEWEB)

    Dong Wei [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States); Doster, J. Michael [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States)], E-mail: doster@eos.ncsu.edu; Mayo, Charles W. [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States)

    2008-04-15

    Control of water mass inventory in Nuclear Steam Generators is important to insure sufficient cooling of the nuclear reactor. Since downcomer water level is measurable, and a reasonable indication of water mass inventory near steady-state, conventional feedwater control system designs attempt to maintain downcomer water level within a relatively narrow operational band. However, downcomer water level can temporarily react in a reverse manner to water mass inventory changes, commonly known as shrink and swell effects. These complications are accentuated during start-up or low power conditions. As a result, automatic or manual control of water level is difficult and can lead to high reactor trip rates. This paper introduces a new feedwater control strategy for Nuclear Steam Generators. The new method directly controls water mass inventory instead of downcomer water level, eliminating complications from shrink and swell all together. However, water mass inventory is not measurable, requiring an online estimator to provide a mass inventory signal based on measurable plant parameters. Since the thermal-hydraulic response of a Steam Generator is highly nonlinear, a linear state-observer is not feasible. In addition, difficulties in obtaining flow regime and density information within the Steam Generator make an estimator based on analytical methods impractical at this time. This work employs a water mass estimator based on feedforward neural networks. By properly choosing and training the neural network, mass signals can be obtained which are suitable for stable, closed-loop water mass inventory control. Theoretical analysis and simulation results show that water mass control can significantly improve the operation and safety of Nuclear Steam Generators.

  4. Steam Generator control in Nuclear Power Plants by water mass inventory

    International Nuclear Information System (INIS)

    Dong Wei; Doster, J. Michael; Mayo, Charles W.

    2008-01-01

    Control of water mass inventory in Nuclear Steam Generators is important to insure sufficient cooling of the nuclear reactor. Since downcomer water level is measurable, and a reasonable indication of water mass inventory near steady-state, conventional feedwater control system designs attempt to maintain downcomer water level within a relatively narrow operational band. However, downcomer water level can temporarily react in a reverse manner to water mass inventory changes, commonly known as shrink and swell effects. These complications are accentuated during start-up or low power conditions. As a result, automatic or manual control of water level is difficult and can lead to high reactor trip rates. This paper introduces a new feedwater control strategy for Nuclear Steam Generators. The new method directly controls water mass inventory instead of downcomer water level, eliminating complications from shrink and swell all together. However, water mass inventory is not measurable, requiring an online estimator to provide a mass inventory signal based on measurable plant parameters. Since the thermal-hydraulic response of a Steam Generator is highly nonlinear, a linear state-observer is not feasible. In addition, difficulties in obtaining flow regime and density information within the Steam Generator make an estimator based on analytical methods impractical at this time. This work employs a water mass estimator based on feedforward neural networks. By properly choosing and training the neural network, mass signals can be obtained which are suitable for stable, closed-loop water mass inventory control. Theoretical analysis and simulation results show that water mass control can significantly improve the operation and safety of Nuclear Steam Generators

  5. Technical and regulatory challenges for digital instrumentation and control and control room systems in nuclear plants

    International Nuclear Information System (INIS)

    Torok, R.; Naser, J.; Harris, T.; Keithline, K.

    2006-01-01

    There are several unsettled technical and licensing issues in the areas of instrumentation and control (I and C), human factors, and updated control room designs that need coordinated, proactive industry attention. Some of these issues are already causing protracted regulatory reviews for existing plants, and left untreated, may cause substantial delays and increased costs for new plant combined construction and operating license approvals. Both industry and the NRC will have roles in resolving the key issues and addressing them in future design efforts and regulatory reviews. Where action is needed, the industry will want to minimize costs and risks by defining industry consensus solutions with corresponding technical bases. NEI has formed a working group to coordinate industry efforts and communications with NRC staff. The working group will also help determine priorities and coordinate both new and existing plant resources. EPRI will provide technical input and guidance for the working group. In order to be able to conduct reviews in a timely fashion, the NRC will likely need to enhance and expand staff resources as existing plants are upgraded and new plant reviews become more active. The industry initiative began with a workshop sponsored by EPRI and NEI on March 28-29, 2006, which led to the creation of the NEI working group. The working group has now identified and prioritized important generic issues, established resolution paths and schedules, and identified the roles of various stakeholders including utility companies, EPRI, NEI, vendors and the NRC. Through the course of this initiative I and C issues for both existing and new plants are being addressed. This paper describes the key I and C related technical and regulatory issues and their implications for new and operating plants, and provides a status report on the efforts to resolve them. (authors)

  6. Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Gregory Weatherby

    2012-05-01

    The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980’s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work tasks, may have a failure rate of 1.0E-3 or higher (Gertman, 1996). With between 10,000 and 45,000 subtasks being performed during an outage (Gomes, 1996), the opportunity for human error of some consequence is a realistic concern. Although a number of factors exist that can make these errors recoverable, reducing and effectively coordinating the sheer number of tasks to be performed, particularly those that are error prone, has the potential to enhance outage efficiency and safety. Additionally, outage management requires precise coordination of work groups that do not always share similar objectives. Outage

  7. Control and accountancy of nuclear materials in a uranium enrichment plant

    International Nuclear Information System (INIS)

    Hurt, N.H.

    1985-01-01

    A nuclear material control and accountancy system has been developed by Goodyear Atomic Corporation to meet safeguards and security requirements. It comprises three major elements: physical security, nuclear material control, and nuclear material accounting. This safeguards system is called Dynamic Material Control and Accountancy System (DYMCAS). The system approaches real-time computer control on a transaction-by-transaction basis

  8. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-02-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative—intended to catalog final products—rather than formative—intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  9. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-01-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative–intended to catalog final products–rather than formative–intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  10. Human factors review of nuclear power plant control room design. Final report

    International Nuclear Information System (INIS)

    Seminara, J.L.; Gonzalez, W.R.; Parsons, S.O.

    1976-11-01

    The human factors aspects of five representative nuclear power plant control rooms were evaluated using such methods as a checklist guided observation system, structured interviews with operators and trainers, direct observations of operator behavior, task analyses and procedure evaluation, and historical error analyses. The human factors aspects of design practices are illustrated, and many improvements in current practices are suggested. The study recommends that a detailed set of applicable human factors standards be developed to stimulate a uniform and systematic concern for human factors in design considerations

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

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

    International Nuclear Information System (INIS)

    Kobori, Takuji; Kanayama, Hiroo; Kamagata, Shuichi

    1989-01-01

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

  13. Nuclear power plants

    International Nuclear Information System (INIS)

    Margulova, T.Ch.

    1976-01-01

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

  14. Review of Methods Related to Assessing Human Performance in Nuclear Power Plant Control Room Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Katya L Le Blanc; Ronald L Boring; David I Gertman

    2001-11-01

    With the increased use of digital systems in Nuclear Power Plant (NPP) control rooms comes a need to thoroughly understand the human performance issues associated with digital systems. A common way to evaluate human performance is to test operators and crews in NPP control room simulators. However, it is often challenging to characterize human performance in meaningful ways when measuring performance in NPP control room simulations. A review of the literature in NPP simulator studies reveals a variety of ways to measure human performance in NPP control room simulations including direct observation, automated computer logging, recordings from physiological equipment, self-report techniques, protocol analysis and structured debriefs, and application of model-based evaluation. These methods and the particular measures used are summarized and evaluated.

  15. Nuclear power plant V-1

    International Nuclear Information System (INIS)

    1998-01-01

    The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

  16. Effects of soft control in the nuclear power plants emergency operation condition

    International Nuclear Information System (INIS)

    Al Harbi, Mohamed Ali Salem; Kim, Ar Ryum; Jang, Inseok; Seong, Poong Hyun; Shirouzu, Shigenori; Katayama, Sotetsu; Kang, Hyun Gook

    2013-01-01

    Highlights: ► We investigated the effect of touch screen, known as ESCM, which is a soft control, on emergency operation of nuclear plants. ► Experiments clearly show the occurrence of more human errors in ESCM task groups. ► Physiological measures (ECG, EEG, nose temperature) were analyzed. ► Higher stress levels were consistently observed in ESCM task groups. - Abstract: In addition to the evolution from buttons and switches to the computer-based consoles, the operator may interact with the plant via soft controls. Soft controls are input interfaces connected with control and display systems that are mediated by software, rather than by direct physical connections. However use of soft control may cause unknown difficulties of operation and provide new opportunities of human errors. This study is to investigate the effect of the new interface to human errors in the emergency operation. Based on the emergency operation procedure, the human error modes were identified by using systematic human error reduction and prediction approach. Experiments with 21 graduate students in main control room mockup in the nuclear engineering departments of universities in UAE and Korea were conducted to observe the operators’ behavior resulted from the use of new input interface (Emergency safety feature-component control system Soft Control Module, ESCM). Physiological parameters such as electroencephalogram, electrocardiogram and skin temperature were measured to assess the stress level of the subjects. The experimental results showed more human errors during ESCM tasks than non-ESCM tasks. The analysis of the physiological measurements also demonstrated that subjects were in high stress level during the ESCM tasks in comparison with non-ESCM tasks. It is notable that this study was performed with graduate students without consideration of their expertise levels. Different behaviors of the novice and the expert groups were also discussed

  17. Multi-region fuzzy logic controller with local PID controllers for U-tube steam generator in nuclear power plant

    Directory of Open Access Journals (Sweden)

    Puchalski Bartosz

    2015-12-01

    Full Text Available In the paper, analysis of multi-region fuzzy logic controller with local PID controllers for steam generator of pressurized water reactor (PWR working in wide range of thermal power changes is presented. The U-tube steam generator has a nonlinear dynamics depending on thermal power transferred from coolant of the primary loop of the PWR plant. Control of water level in the steam generator conducted by a traditional PID controller which is designed for nominal power level of the nuclear reactor operates insufficiently well in wide range of operational conditions, especially at the low thermal power level. Thus the steam generator is often controlled manually by operators. Incorrect water level in the steam generator may lead to accidental shutdown of the nuclear reactor and consequently financial losses. In the paper a comparison of proposed multi region fuzzy logic controller and traditional PID controllers designed only for nominal condition is presented. The gains of the local PID controllers have been derived by solving appropriate optimization tasks with the cost function in a form of integrated squared error (ISE criterion. In both cases, a model of steam generator which is readily available in literature was used for control algorithms synthesis purposes. The proposed multi-region fuzzy logic controller and traditional PID controller were subjected to broad-based simulation tests in rapid prototyping software - Matlab/Simulink. These tests proved the advantage of multi-region fuzzy logic controller with local PID controllers over its traditional counterpart.

  18. Real-time corrosion control system for cathodic protection of buried pipes for nuclear power plant

    International Nuclear Information System (INIS)

    Kim, Ki Tae; Kim, Hae Woong; Kim, Young Sik; Chang, Hyun Young; Lim, Bu Taek; Park, Heung Bae

    2015-01-01

    Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.)

  19. Real-time corrosion control system for cathodic protection of buried pipes for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ki Tae; Kim, Hae Woong; Kim, Young Sik [School of Materials Science and Engineering, Andong National University, Andong (Korea, Republic of); Chang, Hyun Young; Lim, Bu Taek; Park, Heung Bae [Power Engineering Research Institute, KEPCO Engineering and Construction Company, Seongnam (Korea, Republic of)

    2015-02-15

    Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.)

  20. Regulation on governmental quality control during erection and reconstruction of nuclear power plants in the GDR dated 20 July 1988

    International Nuclear Information System (INIS)

    1988-01-01

    The Regulation enters into force on 1 October 1988 and provides for governmental quality control of products, plants and services intended for the erection and reconstruction of nuclear power plant systems. It covers the following provisions: quality control; licensing of enterprises; approval of the use of products manufactured in the GDR; acceptance of products manufactured in the GDR; clearance of plants and services; clearance of imported products; labelling; consulting of experts; penalties, and interim provisions

  1. Neural network for adapting nuclear power plant control for wide-range operation

    International Nuclear Information System (INIS)

    Ku, C.C.; Lee, K.Y.; Edwards, R.M.

    1991-01-01

    A new concept of using neural networks has been evaluated for optimal control of a nuclear reactor. The neural network uses the architecture of a standard backpropagation network; however, a new dynamic learning algorithm has been developed to capture the underlying system dynamics. The learning algorithm is based on parameter estimation for dynamic systems. The approach is demonstrated on an optimal reactor temperature controller by adjusting the feedback gains for wide-range operation. Application of optimal control to a reactor has been considered for improving temperature response using a robust fifth-order reactor power controller. Conventional gain scheduling can be employed to extend the range of good performance to accommodate large changes in power where nonlinear characteristics significantly modify the dynamics of the power plant. Gain scheduling is developed based on expected parameter variations, and it may be advantageous to further adapt feedback gains on-line to better match actual plant performance. A neural network approach is used here to adapt the gains to better accommodate plant uncertainties and thereby achieve improved robustness characteristics

  2. Control device for the recycling flow rate in a nuclear power plant

    International Nuclear Information System (INIS)

    Tanigawa, Naoshi; Shida, Toichi.

    1983-01-01

    Purpose: To prevent the cavitation in a recycling pump even under the conditions where a recycling pump run-back is inhibited, thereby secure the safety of equipments. Constitution: An AND circuit is disposed to a recycling flow rate control system in a BWR type nuclear power plant that issues an output on the condition that a run-back signal is present together with a contact signal of a scoop pipe locking relay or a contact signal of a scoop pipe locking relay. Then, if a demand for the run-back operation of a nuclear reactor recycling pump is issued, the reactor recycling pump is forcedly tripped. Since the pump can always be tripped upon requirement of run-back even if there are some or other inhibitive factors, generation of the cavitation in recycling system equipments can be prevented thereby prevent the damages in the equipments. (Moriyama, K.)

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

    International Nuclear Information System (INIS)

    Santandrea, E.

    1990-01-01

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

  4. Flood control construction of Shidao Bay nuclear power plant and safety analysis for hypothetical accident of HTR-PM

    International Nuclear Information System (INIS)

    Chen Yongrong; Zhang Keke; Zhu Li

    2014-01-01

    A series of events triggered by tsunami eventually led to the Fukushima nuclear accident. For drawing lessons from the nuclear accident and applying to Shidao Bay nuclear power plant flood control construction, we compare with the state laws and regulations, and prove the design of Shidao Bay nuclear power plant flood construction. Through introducing the history of domestic tsunamis and the national researches before and after the Fukushima nuclear accident, we expound the tsunami hazards of Shidao Bay nuclear power plant. In addition, in order to verify the safety of HTR-PM, we anticipate the contingent accidents after ''superposition event of earthquake and extreme flood'', and analyse the abilities and measures of HTR-PM to deal with these beyond design basis accidents (BDBA). (author)

  5. Integrated Nuclear Recycle Plant

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  6. Predictors of operator performance at a simulated nuclear power plant control task

    International Nuclear Information System (INIS)

    Spettell, C.M.

    1986-01-01

    Male undergraduates participated in two experiments as operators of a simple dynamic nuclear power plant simulated on a personal computer. Their task involved monitoring the temperature and power output of the plant and controlling the flow of coolants and the position of the control rods to ensure that the plant operated at the desired temperature and output levels. Quality of performance was defined as the operator's ability to minimize the deviations in temperature and output from optimal values during the trials. Operator inputs and the status of all plant variables were recorded on-line every two seconds. Based on a review of human factors engineering and psychological literature, a number of personality, background, and process variables were measured and correlated with operator performance. Results of both experiments indicated that the strongest predictors of operator performance were the rate, magnitude, and accuracy of operator inputs. Input rate and magnitude were negatively related to overall performance; input accuracy was positively related to performance. These process variables and overall performance were relatively stable across trials of varying difficulty

  7. A HUMAN FACTORS META MODEL FOR U.S. NUCLEAR POWER PLANT CONTROL ROOM MODERNIZATION

    Energy Technology Data Exchange (ETDEWEB)

    Joe, Jeffrey C.

    2017-03-01

    Over the last several years, the United States (U.S.) Department of Energy (DOE) has sponsored human factors research and development (R&D) and human factors engineering (HFE) activities through its Light Water Reactor Sustainability (LWRS) program to modernize the main control rooms (MCR) of commercial nuclear power plants (NPP). Idaho National Laboratory (INL), in partnership with numerous commercial nuclear utilities, has conducted some of this R&D to enable the life extension of NPPs (i.e., provide the technical basis for the long-term reliability, productivity, safety, and security of U.S. NPPs). From these activities performed to date, a human factors meta model for U.S. NPP control room modernization can now be formulated. This paper discusses this emergent HFE meta model for NPP control room modernization, with the goal of providing an integrated high level roadmap and guidance on how to perform human factors R&D and HFE for those in the U.S. nuclear industry that are engaging in the process of upgrading their MCRs.

  8. Preparing and Conducting Review Missions of Instrumentation and Control Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2011-06-01

    The mission for Independent Engineering Review of Instrumentation and Control (I and C) Systems (IERICS) in Nuclear Power Plants (NPPs) has been established with the aim of conducting peer reviews of I and C design documents, implementation processes, prototype I and C systems, and actual systems already deployed in operating NPPs. Organizations in IAEA Member States, such as nuclear utilities, regulators, and technical support organizations can benefit from I and C technical reviews through requesting IERICS missions that provide a detailed technical assessment on I and C systems, as well as recommendations for improvement. The IERICS mission is conducted by a team of international subject matter experts from various complementing technical areas. The review is based on appropriate IAEA documents, such as Safety Guides and Nuclear Energy Series, and the mission's findings are summarized in a mission report, including a list of recommendations, suggestions, and identified good practices. The review is not intended to be a regulatory inspection or an audit against international codes and standards. Rather, it is a peer review aimed at improving design and implementation procedures through an exchange of technical experiences and practices at the working level. The IERICS mission is applicable at any stages of the life cycle of I and C systems in NPPs and it is initiated based on a formal request through official IAEA channels from an organization of a Member State. The formation of the IERICS mission is based on the recommendation of the IAEA Technical Working Group on Nuclear Power Plant Instrumentation and Control (TWG-NPPIC). The recommendation came from the recognition that the IAEA can play an important role in the independent assessment and review of NPP I and C systems in terms of their compliance with IAEA safety guides and technical documents.

  9. How does a change in the control room design affect diagnostic strategies in nuclear power plants?

    International Nuclear Information System (INIS)

    Kim, Dong Young; Kim, Jonghyun

    2014-01-01

    Recently, main control rooms have been considerably changed by modern computer techniques. Some of the features that distinguish digital control rooms from conventional, analog rooms in nuclear power plants include advanced alarm systems, graphic information display systems, computerized procedure systems, and soft control. These features can bring changes in operator tasks, changing the characteristics of tasks or creating new tasks for operators. It is especially expected that these features may bring out changes in the operator's diagnostic tasks and strategies in a digital control room as compared with an analog control room. This study investigates the differences in the operator's diagnostic tasks and strategies in analog and digital control rooms. This study also attempts to evaluate how new systems in a digital control room affect diagnostic strategies. Three different approaches, which are complementary, are used to identify diagnostic strategies in the digital control room and in the analog control room: (1) observation in the simulator, (2) interview with operators, and (3) a literature review. The results show that the digital control room introduces new diagnosis strategies compared with the analog control room while also changing the characteristics of the strategies, mostly by gaining more support from the computerized system. (author)

  10. Investigation on the advanced control room design for next generation nuclear power plants

    International Nuclear Information System (INIS)

    Choi, Seong Soo

    1998-02-01

    An advanced human-machine interface (HMI) has been developed to enhance the safety and availability of a nuclear power plant (NPP) by improving operational reliability. The key elements of the proposed HMI are the large display panels which present synopsis of plant status and the compact, computer-based work stations for monitoring, control and protection functions. The work station consists of four consoles such as a dynamic alarm console (DAC), a system information console (SIC), a computerized operating-procedure console (COC), and a safety system information console (SSIC). The DAC provides clean alarm pictures, in which information overlapping is excluded and alarm impacts are discriminated, for quick situation awareness. The SIC supports a normal operation by offering all necessary system information and control functions over non-safety systems. In addition, it is closely linked to the other consoles in order to automatically display related system information according to situations of the DAC and the COC. The COC aids operators with proper operating procedures during normal plant startup and shutdown or after a plant trip, and it also reduces their physical/mental burden through soft automation. The SSIC continuously displays safety system status and enables operators to control safety systems. With regard to automation, the automating strategies of emergency operation are developed for achieving safe shutdown in pressurized water reactors. These strategies can make emergency operation optimal, and as well they considerably lengthen the operator response time. Decision-making and control are investigated in order to develop the automating strategies. In decision-making, diagnostic trees are established to automate the diagnostic tasks for selecting appropriate emergency operations, and the decision-making procedure is developed to automate some decisions which must be made on a plant- and event-specific basis. In control, cooldown is planned by

  11. Probabilistic safety assessment for digital instrumentation and control systems in nuclear power plants - a review

    International Nuclear Information System (INIS)

    Lu, L.; Jiang, J.

    2003-01-01

    Deregulation in electricity market has created a great deal of challenges for nuclear power industries [1]. To stay competitive, Nuclear Power Plants (NPPs) will have to find ways to reduce their operational costs and to improve the plant safety. Instrumentation and Control (I and C) systems play an important role in this regard. Thus, new methodologies need to be developed to manage the operation of I and C systems more economically without jeopardizing the overall plant safety. Probabilistic Safety Assessment (PSA) technique is one of the promising methods to deal with such an issue, because PSA analyzes various system operational issues from a probabilistic sense, rather than a worst-case approach. However, there are several limitations when PSA is applied to I and C systems directly. A possible solution to this problem can be found by incorporating PSA with several other approaches. To better understand the issues involved, an attempt has been made in this paper to carry out a literature survey on this and related subject, particularly the effort will be made on: 1) the development of digital I and C systems in NPP, 2) PSA and its potential benefits and limitations, and 3) applications of PSA in various aspects of I and C systems including the resource allocation, the determination of surveillance testing strategies and the design of I and C systems. Finally, some solutions to overcome the aforementioned obstacles when applying PSA in I and C systems are also examined critically. (author)

  12. Utilization of water soluble plastics for radiological control within nuclear power plants

    International Nuclear Information System (INIS)

    Smith, R.J.; Deltete, C.P.; Homyk, W.A.; Kasprzak, L.; Robinson, P.J.

    1989-01-01

    The utilization of plastic products for radioactive contamination control within nuclear power facilities currently results in relatively large volumes of waste requiring disposal as low-level radioactive waste. The utilization of a polymer resin product that possesses comparable physical attributes to currently utilized plastic materials, but which is water soluble, has significant potential to reduce the volume of plastic waste requiring disposal as radwaste. Such a volume reduction will reduce overall plant )ampersand M costs, reduce the overall waste volume allocation utilization, and improve the regulatory perception of any plant realizing a volume reduction through plastic source minimization. This potential reduction in waste volume (and associated availability of the Low-level Waste Policy Amendments Act disposal allocation for other purposes), combined with potential economic benefits summarized above, has led to the undertaking of a detailed evaluation, presented in this paper

  13. Cost-effective instrumentation and control upgrades for commercial nuclear power plants surety principles developed at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Rochau, G.E.; Dalton, L.J.

    1998-01-01

    Many nuclear power plants use instrument and control systems based on analog electronics. The state of the art in process control and instrumentation has advanced to use digital electronics and incorporate advanced technology. This technology includes: distributed microprocessors, fiber optics, intelligent systems (neutral networks), and advanced displays. The technology is used to optimize processes and enhance the man-machine interface while maintaining control and safety of the processes. Nuclear power plant operators have been hesitant to install this technology because of the cost and uncertainty in the regulatory process. This technology can be directly applied in an operating nuclear power plant provided a surety principle-based 'administrator' hardware system is included in parallel with the upgrade. Sandia National Laboratories has developed a rigorous approach to High Consequence System Surety (HCSS). This approach addresses the key issues of safety, security, and control while satisfying requirements for reliability and quality. We believe that HCSS principles can be applied to nuclear power plants in a manner that allows the off-the-shelf use of process control instrumentation while maintaining a high level of safety and enhancing the plant performance. We propose that an HCSS Administrator be constructed as a standardized approach to address regulatory issues. Such an administrator would allow a plant control system to be constructed with commercially available, state-to-the-art equipment and be customized to the needs of the individual plant operator. (author)

  14. Cost-effective instrumentation and control upgrades for commercial nuclear power plants using surety principles developed at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Rochau, G.E.; Dalton, L.J.

    1997-01-01

    Many nuclear power plants use instrument and control systems based on analog electronics. The state of the art in process control and instrumentation has advanced to use digital electronics and incorporate advanced technology. This technology includes distributed microprocessors, fiber optics, intelligent systems (neural networks), and advanced displays. The technology is used to optimize processes and enhance the man-machine interface while maintaining control and safety of the processes. Nuclear power plant operators have been hesitant to install this technology because of the cost and uncertainty in the regulatory process. This technology can be directly applied in an operating nuclear power plant provided a surety principle-based open-quotes administratorclose quotes hardware system is included in parallel with the upgrade Sandia National Laboratories has developed a rigorous approach to High Consequence System Surety (HCSS). This approach addresses the key issues of safety, security, and control while satisfying requirements for reliability and quality. HCSS principles can be applied to nuclear power plants in a manner that allows the off-the-shelf use of process control instrumentation while maintaining a high level of safety and enhancing the plant performance. We propose that an HCSS administrator be constructed as a standardized approach to address regulatory issues. Such an administrator would allow a plant control system to be constructed with commercially available, state-of-the-art equipment and be customized to the needs of the individual plant operator

  15. Single parameter controls for nuclear criticality safety at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    Baker, J.S.; Peek, W.M.

    1995-01-01

    At the Oak Ridge Y-12 Plant, there are numerous situations in which nuclear criticality safety must be assured and subcriticality demonstrated by some method other than the straightforward use of the double contingency principle. Some cases are cited, and the criticality safety evaluation of contaminated combustible waste collectors is considered in detail. The criticality safety evaluation for combustible collectors is based on applying one very good control to the one controllable parameter. Safety can only be defended when the contingency of excess density is limited to a credible value based on process knowledge. No reasonable single failure is found that will result in a criticality accident. The historically accepted viewpoint is that this meets double contingency, even though there are not two independent controls on the single parameter of interest

  16. Experiences with monitoring and control of microbiological growth in the standby service water system of a BWR nuclear power plant

    International Nuclear Information System (INIS)

    Zisson, P.S.; Whitaker, J.M.; Neilson, H.L.; Mayne, L.L.

    1995-01-01

    In 1989, the Unites States Nuclear Regulatory Commission formally recognized the potential for nuclear accidents resulting from microbiological causes. Such causes range from loss of heat transfer due to microbiological fouling, to loss of system integrity caused by microbiologically influenced corrosion (MIC). As a result of these potential problems, monitoring, mitigation, and control procedures must be developed by all regulated plants. In developing a control and mitigation strategy for the standby service water system of a boiling water reactor (BWR) nuclear power plant, numerous monitoring techniques were employed to evaluate effectiveness. This paper describes the monitoring techniques that were evaluated, and those that ultimately proved to be effective

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

    International Nuclear Information System (INIS)

    Jung, Byung-Ryul; Lee, Un-Chul

    1997-01-01

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

  18. Future-oriented computerized information system for power plant process control in a pilot project at Philippsburg nuclear power plant

    International Nuclear Information System (INIS)

    Woehrle, G.; Kraft, M.

    1988-01-01

    The motivation for the pilot project at Philippsburg nuclear power plant resulted from the Three Mile Island accident in 1979. The primary task embraces an efficient computer-aided reduction of information when a fault occurs based on a process engineering analysis of the information accrued. Accompanying this are a consolidation and evaluation of the information available in the control room. In this pilot project the new tasks of status monitoring, information reduction and operationalcontrol have been realized for the first time using a computer-aided process information system. In addition to the existing control computer, an information computer with approximately 1200 analogue and about 10000 binary signals has been installed. The installation of the system was completed in 1984 and in the meantime initial operational experience has become available. (orig.) [de

  19. Information technology impact on nuclear power plant documentation. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2002-04-01

    As the majority of the nuclear power plants (NPPs) in the world were designed and constructed about twenty to forty years ago, these older power plants may have shortcomings in documentation on construction, commissioning, operations, maintenance, or decommissioning. Therefore, facility documentation does not always reflect actual plant status after years of plant operation, modification, and maintenance. To deal with these shortcomings, computer and information technologies that provide sophisticated and modern design tools as well as information processing and storage facilities can offer dramatic innovation from paper-centric documentation towards data-centric documentation. This report addresses all aspects of documentation associated with various life-cycle phases of NPPs and the information technology (IT) that are relevant to the documentation process. It also provides a guide for planning, designing, and executing an IT documentation project. Examples are given to demonstrate successful implementations at plants. Finally, it discusses the issues related to the application of the IT in NPPs and the trends for applications of the IT at NPPs as well as the technology itself. It is recognized that this can also improve configuration management. reliability of data, quality of personnel work, and ultimately plant performance reliability and safety. The aspects of using the IT for NPP documentation are closely related to configuration management at NPPs. The report consists of nine sections, a reference section, and five additional appendices. The development of this report which was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is the result of a series of consultants meetings held by the IAEA in Vienna (October 1999, November 2000). It was prepared with the participation and contributions of experts from Canada, Germany, Norway, Sweden, and the United States of America. In addition, a

  20. Information technology impact on nuclear power plant documentation. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-04-01

    As the majority of the nuclear power plants (NPPs) in the world were designed and constructed about twenty to forty years ago, these older power plants may have shortcomings in documentation on construction, commissioning, operations, maintenance, or decommissioning. Therefore, facility documentation does not always reflect actual plant status after years of plant operation, modification, and maintenance. To deal with these shortcomings, computer and information technologies that provide sophisticated and modern design tools as well as information processing and storage facilities can offer dramatic innovation from paper-centric documentation towards data-centric documentation. This report addresses all aspects of documentation associated with various life-cycle phases of NPPs and the information technology (IT) that are relevant to the documentation process. It also provides a guide for planning, designing, and executing an IT documentation project. Examples are given to demonstrate successful implementations at plants. Finally, it discusses the issues related to the application of the IT in NPPs and the trends for applications of the IT at NPPs as well as the technology itself. It is recognized that this can also improve configuration management. reliability of data, quality of personnel work, and ultimately plant performance reliability and safety. The aspects of using the IT for NPP documentation are closely related to configuration management at NPPs. The report consists of nine sections, a reference section, and five additional appendices. The development of this report which was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is the result of a series of consultants meetings held by the IAEA in Vienna (October 1999, November 2000). It was prepared with the participation and contributions of experts from Canada, Germany, Norway, Sweden, and the United States of America. In addition, a

  1. Potential human factors deficiencies in the design of local control stations and operator interfaces in nuclear power plants

    International Nuclear Information System (INIS)

    Hartley, C.S.; Levy, I.S.; Fecht, B.A.

    1984-04-01

    The Pacific Northwest Laboratory has completed a project to identify human factors deficiencies in safety-significant control stations outside the control room of a nuclear power plant and to determine whether NUREG-0700, Guidelines for Control Room Design Reviews, would be sufficient for reviewing those local control stations (LCSs). The project accomplished this task by first, reviewing existing data pertaining to human factors deficiencies in LCSs involved in significant safety actions; second, surveying LCSs environments and design features at several operating nuclear power plants; and third, assessing the results of that survey relative to the contents of NUREG-0700

  2. Licensing and regulatory control of nuclear power plants in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Obenhaus, W.

    1977-01-01

    The lecture is divided into three parts: 1) the legal conception and requirements of the German Atomic Energy Law (with special view on construction and operation of nuclear power plants), 2) the role of the Federation ('Bund') and the 'Laender' in the field of atomic energy and the Radiation Protection Ordinance (especially for licensing and supervision of nuclear power plants), 3) the function, participants, types and sequence of the strongly formalised licensing procedure for nuclear power plants, technical assessment in the frame of this procedure, content of a licence, possibility for altering the licence at a later date, role of administrative courts, continual supervision. (orig./HP) [de

  3. Bivalve fouling of nuclear power plant service-water systems. Volume 2. Current status of biofouling surveillance and control techniques

    International Nuclear Information System (INIS)

    Daling, P.M.; Johnson, K.I.

    1985-03-01

    This report describes the current status of techniques for detection and control of cooling-water system fouling by bivalve mollusks at nuclear power plants. The effectiveness of these techniques is evaluated on the basis of information gathered from a literature review and in interviews with nuclear power plant personnel. Biofouling detection techniques examined in this report include regular maintenance, in-service inspection, and testing. Generally, these methods have been inadequate for detecting biofouling. Recommendations for improving biofouling detection capabilities are presented. Biofouling prevention (or control) methods that are examined in this report include intake screen systems, thermal treatment, preventive maintenance, chemical treatment alternatives, and antifoulant coatings. Recommendations for improving biofouling control methods at operating nuclear power plants are presented. Additional techniques that could be implemented at future power plants or that require further research are also described

  4. Evaluation of safety implications of control systems in LWR nuclear power plants

    International Nuclear Information System (INIS)

    Szukiewicz, A.J.

    1989-06-01

    An in-depth evaluation was performed on non-safety-related control systems (see Section 1) that are typically used during normal plant operation on four nuclear steam supply system plants: a General Electric Company boiling-water reactor, a Westinghouse 3-loop pressurized-water reactor (PWR), a Babcock ampersand Wilcox Co. (B ampersand W) once-through steam generator PWR, and a Combustion Engineering PWR design. A study was also conducted to determine the generic applicability of the results to the class of plants represented by the specific plants analyzed. Generic conclusions were then developed. Steam generator and reactor vessel overfill events and reactor vessel overcooling events were identified as major classes of events having the potential to be more severe than previously analyzed. Specific substasks of this issue were to study these events to determine the need for preventive and/or mitigating design measures. This report describes the technical studies performed by the laboratories, the NRC staff assessment of the results, the generic applicability of the evaluations, and the technical findings resulting from these studies. This final report contains the staff's responses to, and resolution of, the public comments that were solicited and received before September 16,1988, in response to the draft reports issued for public comment on May 27, 1988. 39 refs, 1 fig., 7 tabs

  5. Nuclear Power Plants. Revised.

    Science.gov (United States)

    Lyerly, Ray L.; Mitchell, Walter, III

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

  6. Studies on the coordinated operation and autonomous control for multi-modular nuclear power plants

    International Nuclear Information System (INIS)

    Hui Chao; Huang Xiaojin; Wang Jie

    2011-01-01

    The tendency has always been to build ever larger single-modular reactor plants with the objective of benefiting from economies of scale. These plants have compiled admirable safety records. Nevertheless, there is concern that conventional large single reactors have become too complex by reason of placing too much reliance on engineered safeguards. The multi-modular approach offers a solution in that its use of many small reactors in conjunction with several shared turbines permits a simpler core design while, at the same time, at least partially retaining economies of scale by increasing the number of modules. Specific advantages to the multi-modular approach are as follows. First, the small-sized of the reactor core may allow the incorporation of passive safety features such as natural circulation cooling on loss of off-site electricity. Second, the individual modules are to be sized so that components related to nuclear safety can be factory-fabricated. Moreover, once the major components are made, they are to be transported to the site for rapid installation. This construction method is expected to reduce the licensing effort because the modules will be pre-licensed, and only site-specific issues will have to be considered in the final licensing process. At present, related studies show that the multi-modular approach for Generation IV can retain both the inherent safety and good economies of scale. However, the unbalanced load operation of the multi-modular power plant in which each module operates at a different power level and strong coupling between multi modules creates a complex control challenge to safe operation and control. Firstly, this paper summarizes the unbalanced load operation characteristics and challenges faced by operation and control of multi-modular power plant in the dynamic operational characteristics and requirements of coordinated control between multi modules. Secondly, detailed analysis and comparison are given in the integral

  7. Modernization of instrumentation and control in nuclear power plants. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    1998-05-01

    The scope of the modernization activities described in this report includes the modernization of equipment in operating plants and partially built plants. It covers the full range of types of instrumentation and control (I and C) systems including protection, safety, control and information systems. It is applicable for a plant throughout its life. The report includes appropriate consideration of the increasingly international nature of the I and C systems supply industry and takes advantage of the activities and lessons learned in the different national approaches to develop general guidance and recommendations. An Annex includes 10 country reports which were separately indexed

  8. Modernization of instrumentation and control in nuclear power plants. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    The scope of the modernization activities described in this report includes the modernization of equipment in operating plants and partially built plants. It covers the full range of types of instrumentation and control (I and C) systems including protection, safety, control and information systems. It is applicable for a plant throughout its life. The report includes appropriate consideration of the increasingly international nature of the I and C systems supply industry and takes advantage of the activities and lessons learned in the different national approaches to develop general guidance and recommendations. An Annex includes 10 country reports which were separately indexed Refs, figs, tabs

  9. Human factors design of nuclear power plant control rooms including computer-based operator aids

    International Nuclear Information System (INIS)

    Bastl, W.; Felkel, L.; Becker, G.; Bohr, E.

    1983-01-01

    The scientific handling of human factors problems in control rooms began around 1970 on the basis of safety considerations. Some recent research work deals with the development of computerized systems like plant balance calculation, safety parameter display, alarm reduction and disturbance analysis. For disturbance analysis purposes it is necessary to homogenize the information presented to the operator according to the actual plant situation in order to supply the operator with the information he most urgently needs at the time. Different approaches for solving this problem are discussed, and an overview is given on what is being done. Other research projects concentrate on the detailed analysis of operators' diagnosis strategies in unexpected situations, in order to obtain a better understanding of their mental processes and the influences upon them when such situations occur. This project involves the use of a simulator and sophisticated recording and analysis methods. Control rooms are currently designed with the aid of mock-ups. They enable operators to contribute their experience to the optimization of the arrangement of displays and controls. Modern control rooms are characterized by increasing use of process computers and CRT (Cathode Ray Tube) displays. A general concept for the integration of the new computerized system and the conventional control panels is needed. The technical changes modify operators' tasks, and future ergonomic work in nuclear plants will need to consider the re-allocation of function between man and machine, the incorporation of task changes in training programmes, and the optimal design of information presentation using CRTs. Aspects of developments in control room design are detailed, typical research results are dealt with, and a brief forecast of the ergonomic contribution to be made in the Federal Republic of Germany is given

  10. A framework for evaluating distributed control systems in nuclear power plants

    International Nuclear Information System (INIS)

    O'Donell, C.; Jiang, J.

    2004-01-01

    A framework for evaluating the use of distributed control systems (DCS) in nuclear power plants (NPP) is proposed in this paper. The framework consists of advanced communication, control, hardware and software technology. This paper presents the results of an experiment using the framework test-bench, and elaborates on a variety of other research possibilities. Using a hardware in the loop system (HIL) a DeltaV M3 controller from Emerson Process is connected to a desktop NPP simulator. The industry standard communication protocol, Modbus, has been selected in this study. A simplified boiler pressure control (BPC) module is created on the NPP simulator. The test-bench provides an interface between the controller and the simulator. Through software monitoring the performance of the DCS can be evaluated. Controller access and response times over the Modbus network are observed and compared with theoretical values. The controller accomplishes its task under the specifications set out for the BPC. This novel framework allows a performance metric to be applied against different industrial controllers. (author)

  11. Review of international standards related to the design for control rooms on nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, Masashi; Yoshikawa, Hidekazu; Fujita, Yushi

    2005-01-01

    The improvement of Human-Machine Interface (HMI) design for control rooms on nuclear power plants (NPP) has been accomplished world wide, especially after the TMI-2 accident. The design process and guidelines are standardized in IEC60964 and supplemental standards as international standard. However, technological update is required due to the increased use of computerized control and monitoring equipment and systems in control rooms on NPP in recent years. Standards are becoming more important for computerized control rooms because there is more freedom to design than conventional hardware based system. For computerized control rooms, standards for hardware and software of HMI systems should be also considered. Standards and guidelines for computerized control rooms on NPP have been developed recently in each body such as IEC, ISO, and IEEE etc. Therefore, reviewing these standards and guidelines related to control rooms design of NPP can be useful not only for revision of the international standards such as IEC60964, but also for users of the standards and guidelines. In this paper, we reviewed the international standards related to the design for control rooms, in the two aspects of HMI design and hardware and software design, considering the undergoing revision work and their application. (author)

  12. Quality assurance and control in constructing the Dukovany nuclear power plant

    International Nuclear Information System (INIS)

    Lujka, T.

    1986-01-01

    A quality control and assurance department was established on the Dukovany nuclear power plant site as a unit independent of the production divisions of the plant. Its responsibility consists in testing activities including the development of testing techniques and cooperation in the compilation of specifications and binding technological regulations. The department consists of five sections. The concrete laying laboratory has a staff of 7 and concentrates on testing the quality of concrete mixes and their components in the central concrete production plant. The materials testing centre with a staff of 5 provides testing of steel and special structures and oversees the laying of heavy and very heavy concretes. A separate unit for the testing of surface finish of building structures is staffed with 4 people. The section of technological checks of building and assembly work with a staff of 4 is responsible for the quality of work in the main production unit zone but also of the other buildings on the site. Two people staff the unit for checking and filing the quality control documents for selected components. (Z.M.)

  13. Control of occupational radiation exposures in TVA nuclear power plants - design and operating philosophy

    International Nuclear Information System (INIS)

    Belvin, E.A.; Lyon, M.; Beasley, E.G. Jr.; Zobel, W.; Stone, G.F.

    1976-01-01

    TVA has some 21,000 MWe of nuclear generation in various phases of design, construction, or operation. When Browns Ferry was designed in the late 1960's, there were no guidelines available regarding implant radiation control features, so TVA relied on good engineering and health physics judgement in developing its design and operating criteria for radiation protection. After two years of operation at Browns Ferry, the authors experience shows that their design criteria were in most cases adequate or more than adequate. However, several areas present continuing problems relative to radiation and contamination control. In view of the recent NRC ALARA guidelines, they have instituted a program to ensure that the ALARA concept is made an integral part of their design and operating plans. Administrative documents were issued giving management support to the ALARA concept. A 4-member management audit team consisting of representatives from their design, operating, and radiation protection groups was established to review the effectiveness of radiation protection design features and operating activities on a plant-by-plant basis. Reports and recommendations from these audits are sent to top-level management staff. Their goal is to maintain an audit-appraisal system consisting of in-plant awareness of radiation and contamination conditions, assessment of trends in occupational radiation exposures, and feedback to their designers regarding problems encountered during operation and maintenance activities

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

    International Nuclear Information System (INIS)

    1989-01-01

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

  15. Ergonomic principles of control rooms in nuclear power plants. Vol. 1 and 2

    International Nuclear Information System (INIS)

    Becker, G.; Bohr, E.; Thau, G.

    1983-03-01

    This report describes the findings of a study on the present status and possible improvements in the design of nuclear power plant control rooms according to ergonomic principles and criteria. The findings have been acquired by observing the performance of control room operators, by interviewing operators and management personnel, and by analyzing major characteristics of the man-machine interface. The methods currently used for developing and designing control rooms have also been examined, and the pertinent scientific and technical literature has been reviewed. The results of the study indicate that there is a growing awareness and consideration of physical factors affecting operator performance and reliability whereas less attention is paid to the essential cognitive characteristics of work in the control room. The tasks of operators thus may contain avoidable hindrances and error possibilities that may adversely affect their contribution to reliable plant operation. Major areas of possible ergonomic advancements are set out in the study, and most of them are discussed in depth. Ergonomic requirements are identified for further improving the situation, and approaches, ways and means for solving of mitigating individual problems are indicated wherever possible. A more deliberate consideration of factors affecting operator performance and reliability is suggested, based on a systems ergonomics approach. Design objectives and criteria as well as specific design recommendations for individual areas are given separately. In conclusion, gaps in our existing knowledge are identified which require further research. (orig.) [de

  16. Strategy for Migration of Traditional to Hybrid Control Boards in a Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Ronald Laurids [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey Clark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ulrich, Thomas Anthony [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-07-01

    This strategy document describes the NUREG-0711 based human factors engineering (HFE) phases and associated elements required to support design, verification and validation (V&V), and implementation of new digital control room elements in a legacy analog main control room (MCR). Information from previous planning and analysis work serves as the foundation for creating a human-machine interface (HMI) specification for distributed control systems (DCSs) to be implemented as part of nuclear power plant (NPP) modernization. This document reviews ways to take the HMSI specification and use it when migrating legacy displays or designing displays with new functionality. These displays undergo iterative usability testing during the design phase and then an integrated system validation (ISV) in the full-scope control room training simulator. Following successful demonstration of operator performance using the systems during the ISV, the new DCS is implemented at the plant, first in the training simulator and then in the MCR. This document concludes with a sample project plan, including a 15-month timeline from DCS design through implementation. Included is a discussion of how the U.S. Department of Energy’s Human System Simulation Laboratory (HSSL) can be used to support design and V&V activities. This report completes a Level 4 (M4) milestone under the U.S. Department of Energy’s (DOE’s) Light Water Reactor Sustainability (LWRS) Program.

  17. Seismic isolation floor and vibration control equipment for nuclear power plant

    International Nuclear Information System (INIS)

    Niwa, H.; Fujimoto, S.; Aida, Y.; Miyano, H.

    1996-01-01

    We have developed a seismic isolation floor to improve protection against earthquakes for process computer systems, and a magnetic dynamic damper to reduce the mechanical vibrations of piping systems and pumps in nuclear power plants. Seismic excitation tests of the seismic isolation floor, on which process computer systems were installed, were performed using large earthquake simulators. The test results proved that the seismic isolation floor significantly reduced seismic forces. To control mechanical vibrations, a magnetic dynamic damper was designed using permanent magnets. This magnetic dynamic damper does not require mechanical springs, dampers and supports in the floors and walls of the building. Vibration tests using a rotating machine model confirmed that the magnetic dynamic damper effectively controlled vibrations in such a rotating machine model. (author)

  18. Team interaction skills evaluation criteria for nuclear power plant control room operators

    International Nuclear Information System (INIS)

    Montgomery, J.; Gaddy, C.; Toquam, J.

    1991-01-01

    This paper reports on previous research which has shown the value of good team interaction skills to group performance, yet little progress has been made in measuring such skills. Dimensions of team interaction skills developed in an earlier study were extensively revised and cast into a Behaviorally anchored Rating scales (BARS) and a Behavioral Frequency scale format. Rating data were collected using training instructors at a nuclear plant, who rated videotape scenarios of control room performance and later rated control room crews during requalification training. High levels of interrater agreement on both rating scales was, although the hypothesized factor structure did not emerge. Analysis of ratings of the videotapes using Cronbach's components of accuracy indicted that BARS ratings generally exhibited less error than did the Behavioral Frequency ratings. This paper discusses results in terms of both field and research implications

  19. Preparing and Conducting Review Missions of Instrumentation and Control Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2016-07-01

    The IERICS (Independent Engineering Review of Instrumentation and Control Systems) mission is a comprehensive engineering review service directly addressing strategy and the key elements for implementation of modern instrumentation and control (I&C) systems, noting in applicable cases, specific concerns related to the implementation of advanced digital I&C systems and the use of software and/or digital logic in safety applications of a nuclear power plant. The guidelines outlined in this publication provide a basic structure, common reference and checklist across the various areas covered by an IERICS mission. Publications referenced in these guidelines could provide additional useful information for the counterpart while preparing for the IERICS mission. A structure for the mission report is given in the Appendix. In 2016, this publication was revised by international experts who had participated in previous IERICS missions. The revision reflects experiences and lessons learned from the preparation and conduct of those missions

  20. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    International Nuclear Information System (INIS)

    Yang, Chih Wei; Cheng, Tsung Chieh; Lin, Chiuhsiang Joe

    2011-01-01

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner

  1. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chih Wei; Cheng, Tsung Chieh [Institute of Nuclear Energy Research, Taoyuan (China); Lin, Chiuhsiang Joe [Chung-Yuan Christian University, Chung Li (China)

    2011-08-15

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner.

  2. Licensing and regulatory control of nuclear power plants in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Obenhaus, W.

    1976-01-01

    The paper deals with the legal background, the role of the 'Bund' (Federation) and the 'Laender' (States) in the field of atomic energy and radiation protection law and the licensing procedure for nuclear power plants. (RW) [de

  3. Radioactivity measuring and control method and the system for facility of nuclear power plant

    International Nuclear Information System (INIS)

    Urata, Megumu.

    1996-01-01

    In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

  4. Radioactivity measuring and control method and the system for facility of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Urata, Megumu

    1996-12-03

    In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

  5. Verification of failover effects from distributed control system communication networks in digitalized nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Min, Moon Gi; Lee, Jae Ki; Lee, Kwang Hyun; Lee, Dong Il; Lim, Hee Taek [Korea Hydro and Nuclear Power Co., Ltd, Daejeon (Korea, Republic of)

    2017-08-15

    Distributed Control System (DCS) communication networks, which use Fast Ethernet with redundant networks for the transmission of information, have been installed in digitalized nuclear power plants. Normally, failover tests are performed to verify the reliability of redundant networks during design and manufacturing phases; however, systematic integrity tests of DCS networks cannot be fully performed during these phases because all relevant equipment is not installed completely during these two phases. In additions, practical verification tests are insufficient, and there is a need to test the actual failover function of DCS redundant networks in the target environment. The purpose of this study is to verify that the failover functions works correctly in certain abnormal conditions during installation and commissioning phase and identify the influence of network failover on the entire DCS. To quantify the effects of network failover in the DCS, the packets (Protocol Data Units) must be collected and resource usage of the system has to be monitored and analyzed. This study introduces the use of a new methodology for verification of DCS network failover during the installation and commissioning phases. This study is expected to provide insight into verification methodology and the failover effects from DCS redundant networks. It also provides test results of network performance from DCS network failover in digitalized domestic nuclear power plants (NPPs)

  6. REVIEW Of COMPUTERIZED PROCEDURE GUIDELINES FOR NUCLEAR POWER PLANT CONTROL ROOMS

    Energy Technology Data Exchange (ETDEWEB)

    David I Gertman; Katya Le Blanc; Ronald L Boring

    2011-09-01

    Computerized procedures (CPs) are recognized as an emerging alternative to paper-based procedures for supporting control room operators in nuclear power plants undergoing life extension and in the concept of operations for advanced reactor designs. CPs potentially reduce operator workload, yield increases in efficiency, and provide for greater resilience. Yet, CPs may also adversely impact human and plant performance if not designed and implemented properly. Therefore, it is important to ensure that existing guidance is sufficient to provide for proper implementation and monitoring of CPs. In this paper, human performance issues were identified based on a review of the behavioral science literature, research on computerized procedures in nuclear and other industries, and a review of industry experience with CPs. The review of human performance issues led to the identification of a number of technical gaps in available guidance sources. To address some of the gaps, we developed 13 supplemental guidelines to support design and safety. This paper presents these guidelines and the case for further research.

  7. Ionizing radiation dose control for workers in a nuclear plant working with unsealed sources

    International Nuclear Information System (INIS)

    Gerulis, Eduardo

    2006-01-01

    With the liberation of the use of the nuclear energy for peaceful applications, International Commission Radiological Protection, ICRP, founded in 1928, created a system of protection of the undesirable doses of ionizing radiation in 1958. This has been received by workers, members of the public and environment and hence it became possible for the introduction of these applications. This protection system is adopted by the International Agency of Energy Atomic, IAEA, that publishes recommendations in safety series, 88 and by the Comissao Nacional de Energia Nuclear, CNEN, which publishes these regulations. The international recommendations and national regulations were adapted and they need to be applied in this way. The present paper uses recommendations of the publication 75 from ICRP, of the publication 115 from 88 and regulations of the regulation NN 3.01 from CNEN to present, through radiological protection measures, the ionizing radiation dose control for workers in a nuclear plant that works in the research, production, division and packing of unsealed sources to be used in clinical applications. In that way it is possible to prevent appropriately the undesirable doses and to confirm the received doses. (author)

  8. Requirements and analysis of electromagnetic compatibility of safety-related instrumentation and control system in nuclear power plants

    International Nuclear Information System (INIS)

    Liu Sujuan

    2002-01-01

    The state-of-the-art instrumentation and control system and the influence of their application to the electromagnetic compatibility is analyzed. Based on the present situation of nuclear safety in China and relevant experiences from other countries, the author tries to probe into the requirements and test methods about how safety-related instrument and control system to accommodate electromagnetic interference, radio-frequency interference and power surges in the environments of nuclear power plant so as to develop Chinese safety standards

  9. Expert systems with fuzzy logic for intelligent diagnosis and control of nuclear power plants

    International Nuclear Information System (INIS)

    Abdelhai, M.I.; Upadhyaya, B.R.

    1990-01-01

    A model-based production-rule analysis system was developed for the tracking and diagnosis of the condition of a reactor coolant system (RCS) using a fuzzy logic algorithm. Since nuclear power plants are large and complex systems, it is natural that vagueness, uncertainty, and imprecision are introduced to such systems. Even in fully automated power plants, the critical diagnostic and control changes must be made by operators who usually express their diagnostic and control strategies linguistically as sets of heuristic decision rules. Therefore, additional imprecisions are introduced into the systems because of the imprecise nature of such qualitative strategies when they are converted into quantitative rules. Such problems, in which the source of imprecision is the absence of sharply defined criteria of class membership, could be dealt with using fuzzy set theory. Hence, a fuzzy logic algorithm could be initiated to implement a known heuristic whenever the given information is vague and qualitative, and it will allow operators to introduce certain linguistic assertions and commands to diagnose and control the system

  10. National supply of reactivity control rods for Embalse nuclear power plant (CNE)

    International Nuclear Information System (INIS)

    Biondo, C.D.; Carloni, J.G.; Aba, J.A.

    1987-01-01

    The manufacture and supply on industrial scale of reactivity control rods for CNE (Embalse nuclear power plant) were developed by the National Atomic Energy Commission (CNEA) together with the private industry, as part of a program aimed to the substitution of imported supplies used in the operation of power plants by materials manufactured in Argentina. So far, the control rods were imported from Canada. In this work, the different development stages performed by CNEA and CONUAR S.A. are described, leading to the supply of a set of 21 cobalt rods to be included in a reactor of CNE in order to qualify this component. Among the main activities performed, the following stand out: specifications development, particularly those concerning to cobalt cores, evaluation of design documentation and elaboration of bidding conditions and a plan of manufacture and control. According to the results obtained during the service and the post-irradiation measurements, the design will be reviewed in order to undertake new manufacturing plans. (Author)

  11. The role of instrumentation and control systems in power uprating projects for nuclear power plants

    International Nuclear Information System (INIS)

    2008-01-01

    The IAEA's activities in nuclear power plant operating performance and life cycle management are aimed at increasing Member State capabilities in utilizing good engineering and management practices developed and transferred by the IAEA. In particular, the IAEA supports activities focusing on the improvement of nuclear power plant (NPP) performance, plant life management, training, power uprating, operational licence renewal, and the modernization of instrumentation and control (I and C) systems of NPPs in Member States. The subject of the I and C systems' role in power uprating projects in NPPs was suggested by the Technical Working Group on Nuclear Power Plant Control and Instrumentation in 2003. The subject was then approved by the IAEA and included in the programmes for 2004-2007. The increasing importance of power uprating projects can be attributed to the general worldwide tendency to the deregulation of the electricity market. The greater demand for electricity and the available capacity and safety margins, as well as the pressure from several operating NPPs resulted in requests for licence modification to enable operation at a higher power level, beyond the original licence provisions. A number of nuclear utilities have already gone through the uprating process for their nuclear reactors, and many more are planning to go through this modification process. In addition to mechanical and process equipment changes, parts of the electrical and I and C systems and components may also need to be altered to accommodate the new operating conditions and safety limits. This report addresses the role of I and C systems in NPP power uprating projects. The objective of the report is to provide guidance to utilities, safety analysts, regulators and others involved in the preparation, implementation and licensing of power uprating projects, with particular emphasis on the I and C aspects of these projects. As the average age of NPPs is increasing, it is becoming common for

  12. Human Factors Engineering Incorporated into the Carolina Power and Light company's nuclear power plant control panel modifications

    International Nuclear Information System (INIS)

    Beith, D.M.; Shoemaker, E.M.; Horn, K.; Boush, D.

    1988-01-01

    Maintaining human factors conventions/practices that were established during the Detailed Control Design Review (DCRDR), is difficult if Human Factors Engineering (HFE) is not incorporated into the plant modification process. This paper presents the approach used at Carolina Power and Light's nuclear power plants that has successfully incorporated human factors engineering into their plant modification process. An HFE Design Guide or HFE Specification was developed which is used by the design engineers or plant engineering support groups in the preparation of plant modifications

  13. A study on the optimal replacement periods of digital control computer's components of Wolsung nuclear power plant unit 1

    International Nuclear Information System (INIS)

    Mok, Jin Il; Seong, Poong Hyun

    1993-01-01

    Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Even a trip of a single nuclear power plant (NPP) causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this paper we investigated the optimal replacement periods of the control computer's components of Wolsung nuclear power plant Unit 1. We first derived mathematical models of optimal replacement periods to the digital control computer's components of Wolsung NPP Unit 1 and calculated the optimal replacement periods analytically. We compared the periods with the replacement periods currently used at Wolsung NPP Unit 1. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained and those used in the field show a little difference. (Author)

  14. Modeling and control of a nuclear power plant using AI techniques

    International Nuclear Information System (INIS)

    Oliveira, Mauro Vitor de; Almeida, Jose Carlos Soares de

    2013-01-01

    In pressurized water reactor (PWR) nuclear power plants (NPPs) pressure control in the primary loops is fundamental for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral-derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study is to develop fuzzy controllers for the PWR pressurizer modeled by an artificial neural network (ANN) and compare their performance with conventional ones. Data from a 2785 MWth Westinghouse 3-loop PWR simulator was used to test both the conventional and the fuzzy controllers. The simulation results show that the fuzzy controllers have better performance compared with conventional ones. (author)

  15. Modeling and control of a nuclear power plant using AI techniques

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Mauro Vitor de; Almeida, Jose Carlos Soares de, E-mail: mvitor@ien.gov.br, E-mail: jcsa@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    In pressurized water reactor (PWR) nuclear power plants (NPPs) pressure control in the primary loops is fundamental for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral-derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study is to develop fuzzy controllers for the PWR pressurizer modeled by an artificial neural network (ANN) and compare their performance with conventional ones. Data from a 2785 MWth Westinghouse 3-loop PWR simulator was used to test both the conventional and the fuzzy controllers. The simulation results show that the fuzzy controllers have better performance compared with conventional ones. (author)

  16. Underground nuclear power plant

    International Nuclear Information System (INIS)

    Takahashi, Hideo.

    1997-01-01

    In an underground-type nuclear power plant, groups of containing cavities comprising a plurality of containing cavities connected in series laterally by way of partition walls are disposed in parallel underground. Controlled communication tunnels for communicating the containing cavities belonging to a control region to each other, and non-controlled communication tunnels for communicating containing cavities belonging to a non-controlled area to each other are disposed underground. A controlled corridor tunnel and a non-controlled corridor tunnel extended so as to surround the containing cavity groups are disposed underground, and the containing cavities belonging to the controlled area are connected to the controlled corridor tunnel respectively, and the containing cavities belonging to the non-controlled area are connected to the non-controlled corridor tunnel respectively. The excavating amount of earth and sand upon construction can be reduced by disposing the containing cavity groups comprising a plurality of containing cavities connected in series laterally. The time and the cost for the construction can be reduced, and various excellent effects can be provided. (N.H.)

  17. Views on nuclear power plant control and instrumentation activities in Sweden

    International Nuclear Information System (INIS)

    Blomberg, P.E.

    1986-01-01

    The purpose of this presentation is to provide a summary of the activities concerning human errors in test and maintenance in nuclear power plants, implementation of the advanced information technology and expanded use of on-site conceptual plant simulators in Sweden

  18. Verification tests for remote controlled inspection system in nuclear power plants

    International Nuclear Information System (INIS)

    Kohno, Tadaaki

    1986-01-01

    Following the increase of nuclear power plants, the total radiation exposure dose accompanying inspection and maintenance works tended to increase. Japan Power Engineering and Inspection Corp. carried out the verification test of a practical power reactor automatic inspection system from November, 1981, to March, 1986, and in this report, the state of having carried out this verification test is described. The objects of the verification test were the equipment which is urgently required for reducing radiation exposure dose, the possibility of realization of which is high, and which is important for ensuring the safety and reliability of plants, that is, an automatic ultrasonic flaw detector for the welded parts of bend pipes, an automatic disassembling and inspection system for control rod driving mechanism, a fuel automatic inspection system, and automatic decontaminating equipments for steam generator water chambers, primary system crud and radioactive gas in coolant. The results of the verification test of these equipments were judged as satisfactory, therefore, the application to actual plants is possible. (Kako, I.)

  19. Aging management of instrumentation and control sensors in nuclear power plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2010-01-01

    Pressure to improve plant efficiency and maximize safety and the increasing age of existing NPPs are forcing the global nuclear power industry to confront the challenges of aging - caused by stressors such as temperature, humidity, radiation, electricity, and vibration - in key instrument and control (I and C) components like pressure transmitters, temperature sensors, neutron detectors, and cables. Traditional aging management methods, such as equipment replacement, required the process to be shut down. Recent aging management technologies, collectively known as online monitoring (OLM), enable plants to monitor the condition and aging of their installed I and C while the plant is operating. Developed through R and D initiatives worldwide, such OLM techniques include low- and high-frequency methods that use existing sensors, such as noise analysis; methods based on test or diagnostic sensors, such as for vibration-measuring accelerometers; and methods, such as the power interrupt (PI) test, based on active measurements made by injecting a test signal into the component under test. A review of these aging management methods, their effectiveness, and their interrelation provides a foundation for understanding the next stage in the evolution of OLM: truly integrated hybrid OLM systems capable of robust condition monitoring in both novel and familiar operating conditions.

  20. Radioactive Control of Krsko Nuclear Power Plant Environment in the Year 1997

    International Nuclear Information System (INIS)

    Lulic, S.; Miklavzic, U.; Franic, Z.; Kanduc, M.

    1998-01-01

    Regular Krsko Nuclear Power Plant (NPPK) radioactivity control comprises the supervisions of the inventory of liquid and gaseous emissions at the source, and the independent supervisions of the input of radionuclides into larger environment (imisson). The controlled environment area consists primarily of a 12 kilometers large circle around the object, where the largest values of imission could be expected, and where possible changes in the Sava river and the underground waters could first be noticed. The circle has been enlarged upon the territory of the Republic of Croatia (RC) from Jesenice on Dolenjsko until Podsused (30 km of air - line distance). As reference points relevant for the readiness in the case of accident, especially for detection of iodine and aerosol air transport, the program comprises also measuring points in the RC at larger distances (from 14 to 27 km) in the direction of Zagreb its larger western surroundings (passive Thermoluminescent (TL) dosimeters in the each 42 km long). Continuous control of emission is performed by the radiological service of KNPP by routine procedures, supplemented by adequate measurements from other authorized institutions (intercomparisons, parallel measurements of representative and other samples). Summarised results of radioactive measurements for man-made and natural radionuclides are presented for different transfer media and exposure pathways in the form of assessed effective doses. Conservatively estimated dose burdens received by a member of the reference (critical) population group as the result of NPP emissions amount to a value of the committed effective dose equivalent smaller than 20 μSv/year. This value represents less than 1 % of the annual dose received on average from natural and artificial sources by a member of the general public in the normal environment. The yearly doses from natural radioactivity, global contamination (Chernobyl, atmospheric nuclear explosions), non-nuclear industries and

  1. Nuclear power plant siting

    International Nuclear Information System (INIS)

    Sulkiewicz, M.; Navratil, J.

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

  2. Modernization of the feedwater heaters control level of the Almaraz I Nuclear Power Plant by OVATION system

    International Nuclear Information System (INIS)

    Madronal Rodriguez, E.; Cabrero Munoz, J. E.

    2010-01-01

    As a result of the process of technological renovation of the heaters system and the power increase project, Almaraz Nuclear Power Plant has made several design changes in the feedwater heaters system. Within these changes, the old heaters control loops are replaced because the new power will increase the heaters drainage caudal. This modernization is carried out using the OVATION control system.

  3. Control Room Tasks During Refueling in Ringhals 1 Nuclear Power Plant - Operator performance during refuelling outages

    International Nuclear Information System (INIS)

    Stroebeck, Einar; Olausson, Jesper; Van Gemst, Paul

    1998-01-01

    This paper discusses the performance and tasks of the operators in the control room during refuelling outages. Analyses of such events have, during the last years, shown that the risk for nuclear accidents is not negligible compared with the risk at higher reactor power levels. Some experts have the opinion that, due to mistakes during an outage, the risk for such accidents during the outage and other accidents later on during power operation is higher than in other plant situations. The high risk level is mainly a result of errors at maintenance actions and supervision of lining up of safety systems. Most of the control rooms in existing NPPs were designed more than 10 years ago. At that time the activities and the tasks for the operators were not very well understood. Procedures for refuelling and other activities during the outages were not described very well. Often the utility organisation for refuelling outages was not established at the start of the control room design. Experience from operation during many years has shown that the performance of operators can be improved in existing plant, and thus risks be reduced, by upgrading the control room. These issues have been studied as a part of the modernisation project for Ringhals 1, an ABB Atom BWR owned by Vattenfall AB in Sweden. The paper will describe the working model for upgrading the control room and important issues to take care of with respect to refuelling outages. The identified issues will be used as the input for improving control room philosophy and the individual technical systems. (authors)

  4. Effectiveness of a large mimic panel in an existing nuclear power plant central control board

    International Nuclear Information System (INIS)

    Kubota, Ryuji; Satoh, Hiroyuki; Sasajima, Katsuhiro; Kawano, Ryutaro; Shibuya Shinya

    1999-01-01

    We conducted the analysis of the nuclear power plant (NPP) operators' behaviors under emergency conditions by using training simulators as a joint research project by Japanese BWR groups for twelve years. In the phase-IV of this project we executed two kinds of experiments to evaluate the effectiveness of the interfaces. One was for evaluations of the interfaces such as CRTs with touch screen, a large mimic panel, and a hierarchical annunciator system introduced in the newly developed ABWR type central control board. The other was that we analyzed the operators' behaviors in emergency conditions by using the first generation BWR type central control board which was added new interfaces such as a large display screen and demarcation on the board to help operators to understand the plant. The demarcation is one of the visual interface improvements and its technique is that a line enclosing several components causes them to be perceived as a group.The result showed that both the large display panel Introduced in ABWR central control board and the large display screen in the existing BWR type central control board improved the performance of the NPP operators in the experiments. It was expected that introduction of the large mimic panel into the existing BWR type central control boards would improve operators' performance. However, in the case of actual installation of the large display board into the existing central control boards, there are spatial and hardware constraints. Therefore the size of lamps, lines connecting from symbols of the pumps or valves to the others' will have to be modified under these constraints. It is important to evaluate the displayed information on the large display board before actual installation. We made experiments to solve these problems by using TEPCO's research simulator which is added a large mimic panel. (author)

  5. Upgrade of Control and Protection System of the Ignalina Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Wright, Ronald E.; Fletcher, Norman; Sidnev, Victor E.; Bickel, John H.; Vianello, Aldo; Pearsall, Raymond D.

    2003-01-01

    The Ignalina nuclear power plant (NPP) Units 1 and 2 are Soviet-designed, RBMK (Reaktor Bolshoi Moschnosti Kipyashchiy), channelized, large power-type reactors. The original-design electrical capacity for each unit was 1500 MW. Unit 1 began operating in 1983, and Unit 2 was started up in 1987. In 1994, the government of Lithuania agreed to accept grant support for the Ignalina NPP Safety Improvement Program with funding supplied by the Nuclear Safety Account of the European Bank for Reconstruction and Development (EBRD). As conditions for receiving this funding, the Ignalina NPP agreed to prepare a comprehensive safety analysis report that would undergo independent peer review after it was issued. The EBRD Safety Panel oversaw preparation and review of the report. In 1996, the safety analysis report for Unit 1 was completed and delivered to the EBRD. Part of the analyses covered anticipated transients without scram (ATWS). The analysis showed that some ATWS scenarios could lead to unacceptable consequences in <1 min. The EBRD Safety Panel recommended to the government of Lithuania that the Ignalina NPP develop and implement a program of compensatory measures for the control and protection system before the unit would be allowed to return to operation following its 1998 maintenance outage. A compensatory control and protection system that would mitigate the unacceptable consequences was designed, procured, manufactured, tested, and installed. The project was funded by U.S. Department of Energy

  6. Atucha I nuclear power plant transients analysis

    International Nuclear Information System (INIS)

    Castano, J.; Schivo, M.

    1987-01-01

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

  7. Pilot studies of management of ageing of nuclear power plant instrumentation and control components

    International Nuclear Information System (INIS)

    Burnay, S.G.; Simola, K.; Kossilov, A.; Pachner, J.

    1993-01-01

    This paper describes pilot studies which have been implemented to study the aging behavior of safety related component parts of nuclear power plants. In 1989 the IAEA initiated work on pilot studies related to the aging of such components. Four components were identified for study. They are the primary nozzle of a reactor vessel; a motor operated isolating valve; the concrete containment building; and instrumentation and control cables within the containment facility. The study was begun with phase 1 efforts directed toward understanding the aging process, and methods for monitoring and minimizing the effects of aging. Phase 2 efforts are directed toward aging studies, documentation of the ideas put forward, and research to answer questions identified in phase 1. This paper describes progress made on two of these components, namely the motor operated isolation valves, and in-containment I ampersand C cables

  8. Pressure fluctuation analysis for charging pump of chemical and volume control system of nuclear power plant

    Directory of Open Access Journals (Sweden)

    Chen Qiang

    2016-01-01

    Full Text Available Equipment Failure Root Cause Analysis (ERCA methodology is employed in this paper to investigate the root cause for charging pump’s pressure fluctuation of chemical and volume control system (RCV in pressurized water reactor (PWR nuclear power plant. RCA project task group has been set up at the beginning of the analysis process. The possible failure modes are listed according to the characteristics of charging pump’s actual pressure fluctuation and maintenance experience during the analysis process. And the failure modes are analysed in proper sequence by the evidence-collecting. It suggests that the gradually untightened and loosed shaft nut in service should be the root cause. And corresponding corrective actions are put forward in details.

  9. Applied means to increase stimulation in the control room work at the Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Blomberg, P.E.; Akerhielm, F.

    1988-01-01

    Nuclear power plants are generally designed and built with a quality which implies that the units seldom require intervention from the operating staff under normal operating conditions. This leaves the operators with the dominating task of only passively supervising the process. A number of measures have been taken to counteract the problem of under-stimulated individuals in the control rooms and to maintain active and purposeful working conditions. Basically these measures derive from the belief that augmented competence, increased responsibilities and a enhanced sense of indispensability functions as an inspiration even in a monotonous working situation. For this purpose a number of activities and tasks, parallel to the normal duties as member of the operating staff, have been implemented

  10. A Study of BUS Architecture Design for Controller of Nuclear Power Plant Using FPGA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dongil; Yun, Donghwa; Hwang, Sungjae; Kim, Myeongyun; Lee, Dongyun [PONUTech Co. Ltd., Seoul (Korea, Republic of)

    2014-05-15

    CPU (Central Processing Unit) operating speed and communication rate have been more technically improved than before. However, whole system is been a degradation of performance by electronic and structural limitation of parallel bus. Transmission quantity and speed have a limit and need arbiter in order to do arbitration because several boards shared parallel bus. Arbiter is a high complexity in implementing so it increases component per chip. If a parallel bus uses, it will occurs some problems what are reflection noise, power/ground noise (or ground bounce) as SSN (Simultaneous Switching Noise) and crosstalk noise like magnetic coupling. In this paper, in order to solve a problem of parallel bus in controller of NPP (Nuclear Power Plant), proposes the bus architecture design using FPGA (Field Programmable Gate Array) based on LVDS (Low Voltage Differential Signaling)

  11. A Study of BUS Architecture Design for Controller of Nuclear Power Plant Using FPGA

    International Nuclear Information System (INIS)

    Lee, Dongil; Yun, Donghwa; Hwang, Sungjae; Kim, Myeongyun; Lee, Dongyun

    2014-01-01

    CPU (Central Processing Unit) operating speed and communication rate have been more technically improved than before. However, whole system is been a degradation of performance by electronic and structural limitation of parallel bus. Transmission quantity and speed have a limit and need arbiter in order to do arbitration because several boards shared parallel bus. Arbiter is a high complexity in implementing so it increases component per chip. If a parallel bus uses, it will occurs some problems what are reflection noise, power/ground noise (or ground bounce) as SSN (Simultaneous Switching Noise) and crosstalk noise like magnetic coupling. In this paper, in order to solve a problem of parallel bus in controller of NPP (Nuclear Power Plant), proposes the bus architecture design using FPGA (Field Programmable Gate Array) based on LVDS (Low Voltage Differential Signaling)

  12. Team interaction skills evaluation criteria for nuclear power plant control room operators

    International Nuclear Information System (INIS)

    Montgomery, J.C.; Toquam, J.; Gaddy, C.

    1991-09-01

    Previous research has shown the value of good team interaction skills to group performance, yet little progress has been made on in terms of how such skills can be measured. In this study rating scales developed previously (Montgomery, et al., 1990) were extensively revised and cast into a Behaviorally Anchored Rating Scale (BARS) and a Behavioral Frequency format. Rating data were collected using 13 training instructors at the Diablo Canyon Nuclear Plant, who rated three videotapes of simulator scenario performance during a day-long training session and later evaluated control room crews during requalification training. High levels of interrater agreement on both rating scales were found. However, the factor structure of the ratings was generally inconsistent with that hypothesized. Analysis of training ratings using Cronbach's components of accuracy (Cronbach, 1955) indicated that BARS ratings generally exhibited less error than did the Behavioral Frequency ratings. The results are discussed in terms of both field and research implications

  13. Intelligent software system for the advanced control room of a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Choi, Seong Soo; Park, Jin Kyun; Heo, Gyung Young [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Kim, Han Gon [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The intelligent software system for nuclear power plants (NPPs) has been conceptually designed in this study. Its design goals are to operate NPPs in an improved manner and to support operators` cognitive takes. It consists of six major modules such as {sup I}nformation Processing,{sup {sup A}}larm Processing,{sup {sup P}}rocedure Tracking,{sup {sup P}}erformance Diagnosis,{sup a}nd {sup E}vent Diagnosis{sup m}odules for operators and {sup M}alfunction Diagnosis{sup m}odule for maintenance personnel. Most of the modules have been developed for several years and the others are under development. After the completion of development, they will be combined into one system that would be main parts of advanced control rooms in NPPs. 5 refs., 4 figs. (Author)

  14. Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Grison, J [Compagnie Generale des Matieres Nucleaires (COGEMA), Centre de la Hague, 50 - Cherbourg (France)

    1980-10-01

    The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis.

  15. Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Grison, J.

    1980-01-01

    The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis [fr

  16. Human factors review of nuclear power plant control room design. Summary report

    International Nuclear Information System (INIS)

    Seminara, J.L.; Gonzalez, W.R.; Parsons, S.O.

    1976-11-01

    Human factors engineering is an interdisciplinary specialty concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. The human factors aspects of five representative nuclear power plant control rooms were evaluated using such methods as a checklist-guided observation system, structured interviews with operators and trainers, direct observations of operator behavior, task analyses and procedure evaluation, and historical error analyses. The human factors aspects of design practices are illustrated, and many improvements in current practices are suggested. The study recommends that a detailed set of applicable human factors standards be developed to stimulate a uniform and systematic concern for human factors in design considerations

  17. Intelligent software system for the advanced control room of a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Choi, Seong Soo; Park, Jin Kyun; Heo, Gyung Young [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Kim, Han Gon [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    The intelligent software system for nuclear power plants (NPPs) has been conceptually designed in this study. Its design goals are to operate NPPs in an improved manner and to support operators` cognitive takes. It consists of six major modules such as {sup I}nformation Processing,{sup {sup A}}larm Processing,{sup {sup P}}rocedure Tracking,{sup {sup P}}erformance Diagnosis,{sup a}nd {sup E}vent Diagnosis{sup m}odules for operators and {sup M}alfunction Diagnosis{sup m}odule for maintenance personnel. Most of the modules have been developed for several years and the others are under development. After the completion of development, they will be combined into one system that would be main parts of advanced control rooms in NPPs. 5 refs., 4 figs. (Author)

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

    International Nuclear Information System (INIS)

    2016-01-01

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

  19. Knowledge management for modelling nuclear power plants control in incidental and accidental states

    International Nuclear Information System (INIS)

    MIllerat, P.

    1996-11-01

    A knowledge model uses different techniques of complex systems management. Progress realised in the computer representation of links between different documents allows us to design a software facilitating the comprehension of the model built. This model is a qualitative model of the operators' behaviour in nuclear power plant accidental control. This model concerned three topics closely linked together. The first gives a description of every physical phenomena implied the application of the State-oriented Approach (APE in French) procedures. It's referred as model of process. The second gives a description of every activities used by the operators' team to manage all thermohydraulic incidents and accidents. It's a functional model also referred as tasks model. The quality of the method, based on the Systems' Science, capitalized a know-how simply transferable to design a new software on industrial process to support the operators. (author)

  20. Regulatory perspective on digital instrumentation and control systems for future advanced nuclear power plants

    International Nuclear Information System (INIS)

    Chiramal, M.

    1993-01-01

    This paper deals with the question of using digital technology in instrumentation and control systems for modern nuclear power reactors. The general opinion in the industry and among NRC staff is that such technology provides the opportunity for enhanced safety and reliable reactor operations. The major concern is the safe application of this technology so as to avoid common mode or common cause failures in systems. There are great differences between digital and analog system components. SECY-91-292 identifies some general regulatory concerns with regard to digital systems. There is clearly a lack of adequate regulatory direction on the application of digital equipment at this time, but the issue is being addressed by the industry, outside experts, and NRC staff. NRC staff presents a position on the issue of defense-in-depth and diversity with regard to insuring plant safety. Independent manual controls and readouts must be available to allow safe shutdown and monitoring of the plant in the event of safety system failures

  1. Report on nuclear power plant control and instrumentation activities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Bastl, W.

    1986-01-01

    The overall situation in I and C of nuclear power plants in the Federal Republic of Germany can be characterized by three aspects. a) The improvement of man-machine communication by introducing integral information concepts for the control room by means of VDUs. b) Along with a) new data acquisition systems based upon process computers which facilitate the integration of operator aids like alarm analyses, disturbance analyses, post-mortem analyses, etc. c) The penetration of programmable processors into limitation systems in order to provide soft setback measures. d) The transition to I and C systems making use of the new generation of electronic components. The most important step towards advanced control rooms was the development of the Process Information System (PRINS) by KWU, which will be used with the German convoi-plants. The main emphasis regarding further R and D work in the field of operator aids is placed upon expert systems. Work will begin with a two years project aiming at the development of a basic module for a laboratory prototype

  2. Simulations research of the global predictive control with self-adaptive in the gas turbine of the nuclear power plant

    International Nuclear Information System (INIS)

    Su Jie; Xia Guoqing; Zhang Wei

    2007-01-01

    For further improving the dynamic control capabilities of the gas turbine of the nuclear power plant, this paper puts forward to apply the algorithm of global predictive control with self-adaptive in the rotate speed control of the gas turbine, including control structure and the design of controller in the base of expounding the math model of the gas turbine of the nuclear power plant. the simulation results show that the respond of the change of the gas turbine speed under the control algorithm of global predictive control with self-adaptive is ten second faster than that under the PID control algorithm, and the output value of the gas turbine speed under the PID control algorithm is 1%-2% higher than that under the control slgorithm of global predictive control with self-adaptive. It shows that the algorithm of global predictive control with self-adaptive can better control the output of the speed of the gas turbine of the nuclear power plant and get the better control effect. (authors)

  3. Evaluation of the control system checkout test at 100% power for Yonggwang Nuclear Power Plant Unit 3

    International Nuclear Information System (INIS)

    Kim, Shin Whan; Lee, Joo Han; Baek, Jong Man; Seo, Jong Tae; Lee, Sang Keun; Kang, In Koo; Ju, Hee Wan; Min, Kyung Soo; Kim, Byung Gon

    1995-01-01

    Control system checkout tests at various powers for Yonggwang Nuclear Power Plant Unit 3(YGN3) were performed to demonstrate the accuracies and proper performances of the control systems of the plant. Tested control systems included the feedwater control system, steam bypass control system, reactor regulation system, control element drive mechanism control system, pressurizer level control system, and pressurizer pressure control system. The measured test data during the control system checkout test at 100% power are evaluated. The test results showed that the control systems of YGN 3 properly control system was simulated by using the LTC code which is the performance analysis code for YGN 3 and 4 design. Comparisons of the predicted results with the measured data confirmed that the feedwater control system controls the steam generator level as designed

  4. Information integration in control rooms and technical offices in nuclear power plants. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2001-11-01

    The majority of the nuclear power plants in the world were designed 25 to 45 years ago. The information, instrumentation, safety, and control systems in these plant designs were based on analog, relay, and primitive digital technology. Computers that were available when most of the nuclear power plants were built were unsophisticated compared with those currently available. These less powerful machines with limited computational capabilities and memory were used to collect and store information. The main means for obtaining information from the plant were analog meters and strip chart recorders. In many cases these pieces of data had to be integrated and correlated with other data manually, in order to be usable. Procedures and plant information resided on paper only and were frequently hard to find and access in a timely manner. This report provides guidance to help with the integration of information in order to enhance the usability and usefulness of the information. It can also be used to help avoid the pitfalls that can occur when implementing new systems with respect to the information they need and produce. This reports philosophy is based on three important issues that allow the convenient structuring of the problem and to keep all of its important features. The first issue is the process of information systems integration and use. This is achieved by long term planning and the creation of the plant infrastructure plan. The second is to take care of the end users' needs in relation to their abilities. This is realized through analyses of user needs. Third is the design of the human-system interface (HSI), for example to distinguish between types of information for use in the plant control room and in technical offices. The development of this report was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is a logical follow-up to IAEA-TECDOC-1016, Modernization of Instrumentation and Control

  5. Nuclear power plant

    International Nuclear Information System (INIS)

    Uruma, Hiroshi

    1998-01-01

    In the first embodiment of the present invention, elements less activated by neutrons are used as reactor core structural materials placed under high neutron irradiation. In the second embodiment of the present invention, materials less activated by neutrons when corrosive materials intrude to a reactor core are used as structural materials constituting portions where corrosion products are generated. In the third embodiment, chemical species comprising elements less activated by neutrons are used as chemical species to be added to reactor water with an aim of controlling water quality. A nuclear power plant causing less radioactivity can be provided by using structural materials comprising a group of specific elements hardly forming radioactivity by activation of neutrons or by controlling isotope ratios. (N.H.)

  6. Nuclear power plant construction

    International Nuclear Information System (INIS)

    Lima Moreira, Y.M. de.

    1979-01-01

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

  7. Psychological factors of professional success of nuclear power plant main control room operators

    Directory of Open Access Journals (Sweden)

    Kosenkov A.A.

    2014-12-01

    Full Text Available Aim: to conduct a comparative analysis of the psychological characteristics of the most and least successful main control room operators. Material and Methods. Two NPP staff groups: the most and least successful main control room operators, who worked in routine operating conditions, were surveyed. Expert evaluation method has been applied to identify the groups. The subjects were administered the Minnesota Multiphasic Personality Inventory (MMPI, Cattell's Sixteen Personality Factor Questionnaire (16PF form A and Raven's Progressive Matrices test. Results. Numerous significant psychological differences between the groups of most and least successful control room operators were obtained: the best operators were significantly more introverted and correctly solved more logical tasks with smaller percentage of mistakes under time pressure than worst ones. Conclusions: 1. The psychodiagnostic methods used in the study were adequate to meet research objective 2. Tendency to introversion, as well as developed the ability to solve logic problems undertime pressure, apparently, are important professional qualities for control room operators. These indicators should be considered in the process of psychological selection and professional guidance of nuclear power plant operators.

  8. Design of nuclear power plant control rooms: some findings and possible improvements

    International Nuclear Information System (INIS)

    Bohr, E.

    1984-01-01

    Major findings are described of a study on the present status and possible improvements in the design of nuclear power plant control rooms according to ergonomic principles and criteria. The findings have been acquired by observing the performance of control room operators, by interviewing operators and management personnel, and by analysing major characteristics of the man-machine interface. The methods currently used for developing and designing control rooms have also been examined. The results of the study indicate that there is a growing awareness and consideration of physical factors affecting performance. More attention should be paid to the essential cognitive characteristics of work in the control room with the aim of avoiding unnecessary hindrances and possible errors. Examples are given of some of these problems, and approaches, ways and means for solving or mitigating them are indicated. A more deliberate consideration of factors affecting operator performance and reliability is suggested, based on a systems ergonomics approach. Analyses of critical tasks would be a major feature of this approach. Its main objective is to ensure that operators are able to carry out their tasks reliably. (author)

  9. Structural integrity of rod cluster control assembly of Chashma Nuclear Power Plant -1

    International Nuclear Information System (INIS)

    Siddiqui, A.; Zafar, F.; Murtaza, G.

    2008-01-01

    This study has been made in an attempt to verify the structural integrity of Rod Cluster Control Assembly (RCCA) of Chashma Nuclear Power Plant-1(CHASNUPP-1) using ANSYS computer code. The CHASNUPP-1 (PWR type, 300 MWe capacity, unit 1) was built by China at Chashma (District Mianwali), Pakistan. The plant is successfully operating since 2000. The rod cluster control assemblies (RCCA) are used to control fast reactivity changes in PWR type reactors during the normal operation and accident conditions. To fulfill this function the RCCA is stepped upwards or downwards by control rod drive mechanism (CRDM). The stepping action produces a large amount of acceleration. The load produced during stepping is normally considered as limiting one. In this work we have considered the experimental results of a test conducted in China. The test was performed to measure the acceleration produced in upward and downward stepping by CRDM on RCCA, at room temperatures, both in air and static water. The test results showed acceleration (g, m/s 2 ) values, 10.8 - 51.0 and 46.4 - 78.0, in air and static water environments, respectively. Making the analysis on conservative side we selected the highest value of acceleration, 78 g, for our study. To ensure the structural strength, a finite element model of CHASNUPP-1 RCCA has been developed simulating the loading conditions prevailing during reactor operation. This model has been analyzed using the Finite Element Code. The Maximum Stress intensity obtained through this analysis, 186 MPa, is less than the yield stress of RCCA material (∼SS 321), 205 MPa, thus fulfills its structural integrity criteria. (authors)

  10. Key Regulatory Issues for Digital Instrumentation and Control Systems at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Korsah, Kofi; Wood, Richard Thomas

    2008-01-01

    To help reduce the uncertainty associated with application of digital instrumentation and controls (I and C) technology in nuclear power plants, the Nuclear Regulatory Commission (NRC) has issued six Interim Staff Guidance (ISG) documents that address the current regulatory positions on what are considered the significant digital I and C issues. These six documents address the following topics: Cyber Security, Diversity and Defense-in-Depth, Risk Informed Digital I and C Regulation, Communication issues, Human Factors and the Digital I and C Licensing Process (currently issued as Draft). After allowing for further refinement based on additional technical insight gathered by NRC staff through near-term research and detailed review of relevant experience, it is expected that updated positions ultimately will be incorporated into regulatory guides and staff review procedures. This paper presents an overview of the guidance provided by the NRC-issued ISGs on key technology considerations (i.e., the first five documents above) for safety-related digital I and C systems.

  11. Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

    International Nuclear Information System (INIS)

    Horvath, J.; Dugovic, L.

    1999-01-01

    Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

  12. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

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

  13. A Pilot Study Investigating the Effects of Advanced Nuclear Power Plant Control Room Technologies: Methods and Qualitative Results

    Energy Technology Data Exchange (ETDEWEB)

    BLanc, Katya Le [Idaho National Lab. (INL), Idaho Falls, ID (United States); Powers, David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Brandon [Idaho National Lab. (INL), Idaho Falls, ID (United States); Fitzgerald, Kirk [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-08-01

    Control room modernization is an important part of life extension for the existing light water reactor fleet. None of the 99 currently operating commercial nuclear power plants in the U.S. has completed a full-scale control room modernization to date. Nuclear power plant main control rooms for the existing commercial reactor fleet remain significantly analog, with only limited digital modernizations. Upgrades in the U.S. do not achieve the full potential of newer technologies that might otherwise enhance plant and operator performance. The goal of the control room upgrade benefits research is to identify previously overlooked benefits of modernization, identify candidate technologies that may facilitate such benefits, and demonstrate these technologies through human factors research. This report describes a pilot study to test upgrades to the Human Systems Simulation Laboratory at INL.

  14. Radioactive control of Krsko Nuclear Power Plant in the year 1995

    International Nuclear Information System (INIS)

    Lulic, S.; Miklavzic, U.; Franic, Z.; Kanduc, M.

    1996-01-01

    Regular Krsko Nuclear Power Plant (NPPK) radioactivity control comprises the supervisions of the inventory of liquid and gaseous emissions at the source, and the independent supervisions of the input of radionuclides into larger environment. The controlled environment area consist primarily of a 12 kilometers large circle around the object, where the largest values of immission could be expected, and where possible changes in the Sava river and the underground waters could first be noticed. The circle has been enlarged upon the territory of the Republic of Croatia (RC) from Jesenice on Dolenjsko until Podsused (30 km of air-line distance). As reference points relevant for the readiness in the case of accident, especially for detection of iodine and aerosol air transport, the program comprises also measuring points in the RC at larger distances (from 14 to 27 km) in the direction of Zagreb its larger western surroundings (passive Thermoluminescent (TL) dosimeters in each 42 km long). Continuous of control of emission is performed by the radiological service of (KNPP) by routine procedures, supplemented by adequate measurements from other authorized institutions. Summarized results of radioactive measurements for man-made and natural radionuclides are presented for different transfer media and exposure pathways in the form of assessed effective doses. Conservatively estimated dose burdens received by a member of the reference (critical) population group as the result of NPP emissions amount to a value of the committed effective dose equivalent smaller than 20 μSv/year. This value represents less than 1% of the annual dose received on average from natural and artificial sources by a member of the general public in the normal environment. The yearly doses from natural radioactivity, global contamination , non-nuclear industries and hospitals are also estimated from the measured data in some media. (author)

  15. Loviisa nuclear power plant analyzer

    International Nuclear Information System (INIS)

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

    1992-12-01

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

  16. Safety Evaluation Approach with Security Controls for Safety I and C Systems on Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, D. H.; Jeong, S. Y.; Kim, Y. M.; Park, H. S.; Lee, M. S.; Kim, T. H.

    2016-01-01

    This paper addresses concepts of safety and security and relations between them for assessing effects of security features in safety systems. Also, evaluation approach for avoiding confliction with safety requirements and cyber security features which may be adopted in safety-related digital I and C system will be described. In this paper, safety-security life cycle model based confliction avoidance method was proposed to evaluate the effects when the cyber security control features are implemented in the safety I and C system. Also, safety effect evaluation results using the proposed evaluation method were described. In case of technical security controls, many of them are expected to conflict with safety requirements, otherwise operational and managerial controls are not relatively. Safety measures and cyber security measures for nuclear power plants should be implemented not to conflict with one another. Where safety function and security features are both required within the systems, and also where security features are implemented within safety systems, they should be justified

  17. Measuring Situation Awareness of Operating Team in Different Main Control Room Environments of Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Seung Woo Lee

    2016-02-01

    Full Text Available Environments in nuclear power plants (NPPs are changing as the design of instrumentation and control systems for NPPs is rapidly moving toward fully digital instrumentation and control, and modern computer techniques are gradually introduced into main control rooms (MCRs. Within the context of these environmental changes, the level of performance of operators in a digital MCR is a major concern. Situation awareness (SA, which is used within human factors research to explain to what extent operators of safety-critical systems know what is transpiring in the system and the environment, is considered a prerequisite factor to guarantee the safe operation of NPPs. However, the safe operation of NPPs can be guaranteed through a team effort. In this regard, the operating team's SA in a conventional and digital MCR should be measured in order to assess whether the new design features implemented in a digital MCR affect this parameter. This paper explains the team SA measurement method used in this study and the results of applying this measurement method to operating teams in different MCR environments. The paper also discusses several empirical lessons learned from the results.

  18. Safety Evaluation Approach with Security Controls for Safety I and C Systems on Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, D. H.; Jeong, S. Y.; Kim, Y. M.; Park, H. S. [KINS, Daejeon (Korea, Republic of); Lee, M. S.; Kim, T. H. [Formal Works Inc., Seoul (Korea, Republic of)

    2016-05-15

    This paper addresses concepts of safety and security and relations between them for assessing effects of security features in safety systems. Also, evaluation approach for avoiding confliction with safety requirements and cyber security features which may be adopted in safety-related digital I and C system will be described. In this paper, safety-security life cycle model based confliction avoidance method was proposed to evaluate the effects when the cyber security control features are implemented in the safety I and C system. Also, safety effect evaluation results using the proposed evaluation method were described. In case of technical security controls, many of them are expected to conflict with safety requirements, otherwise operational and managerial controls are not relatively. Safety measures and cyber security measures for nuclear power plants should be implemented not to conflict with one another. Where safety function and security features are both required within the systems, and also where security features are implemented within safety systems, they should be justified.

  19. Integrated Cost and Schedule Control Systems for Nuclear Power Plant Construction: Leveraging Strategic Advantages to Owners and EPC Firms

    Directory of Open Access Journals (Sweden)

    Youngsoo Jung

    2015-01-01

    Full Text Available As the owners expect that the cost and time for nuclear power plant construction would decrease with new entrants into the market, there will be severer competition in the nuclear industry. In order to achieve performance improvement and to attain competitive advantages under the globalized competition, practitioners and researchers in the nuclear industry have recently exerted efforts to develop an advanced and efficient management methodology for the nuclear mega-projects. Among several candidates, integrated cost and schedule control system is of great concern because it can effectively manage the three most important project performances including cost, time, and quality. In this context, the purpose of this paper is to develop a project numbering system (PNS of integrated cost and schedule control system for nuclear power plant construction. Distinct attributes of nuclear power plant construction were investigated first in order to identify influencing variables that characterize real-world implementation of advanced cost and schedule controls. A scenario was then developed and analysed to simulate a case-project. By using this case-project, proposed management requirements, management methods, measurement techniques, data structure, and data collection methods for integrated cost and schedule PNS were illustrated. Finally, findings and implications are outlined, and recommendations for further research are presented.

  20. NUCLEAR POWER PLANT

    Science.gov (United States)

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

    1963-05-14

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

  1. Tenth meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation, Vienna, 3-5 March 1986

    International Nuclear Information System (INIS)

    1986-07-01

    The meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) was organized in order to summarize operating experience of NPP control systems, gain a general overview of activities in development of modern control systems and receive recommendations on the further directions and particular measures within the Agency's programme. The papers and discussions mostly dealt with practical experience and described actual problems encountered. Emphasis was placed on the technical, industrial and economic aspects of the introduction of modern, highly automated control systems and on the improvement of plant availability and safety. A separate abstract was prepared for each of the 20 presentations of the meeting

  2. Support for cooperative control and maintenance operation in advanced nuclear power plant from generalized and intuitive viewpoints

    International Nuclear Information System (INIS)

    Numano, Masayoshi; Niwa, Yasuyuki; Miyazaki, Keiko; Fukuto, Junji; Tanaka, Kunihiko; Okazaki, Tadatsugi; Itoh, Hiroko; Matsuoka, Takeshi

    2002-01-01

    To keep safety and effectiveness in control and maintenance operations of large and complex plants like nuclear power plants, cooperative operation among human and machine agents is proposed. The concept is that the cooperation augments human capability as an individual by closely related team members with adequate interfaces. This paper describes a basic concept of the cooperation, necessary interface functions, infrastructure of the cooperation and communication logging for accumulation and sharing of knowledge. (author)

  3. Water chemistry: cause and control of corrosion degradation in nuclear power plants

    International Nuclear Information System (INIS)

    Kain, Vivekanand

    2008-01-01

    The corrosion degradation of a material is directly determined by the water chemistry, material (composition, fabrication procedure and microstructure) and by the stress/strain in the material under operating conditions. Water chemistry plays an important role in both uniform corrosion and localized forms of corrosion of materials. Once we understand how water chemistry is contributing to corrosion of a material, it is logical to modify/change that water chemistry to control the corrosion degradation. In nuclear power plants, different water chemistries have been used in different components/systems. This paper will cover the origin of corrosion degradation in the Primary Heat Transport system of different reactor types, Steam Generator tubing, secondary circuit pipelines, service water pipelines and auxiliary systems and establish the role of water chemistry in causing corrosion degradation. The history of changes in water chemistry adopted in these systems to control corrosion degradation is also described. It is shown by examples that there is an obvious limitation in changing water chemistry to control corrosion degradation and in those cases, a change of material or change of the state of stresses/fabrication procedure becomes necessary. The role of water chemistry as a causative factor and also as a controlling parameter on particular types of corrosion degradation e.g. stress corrosion cracking, flow accelerated corrosion, pitting, crevice corrosion is illustrated. It will be shown that increase in dissolved oxygen content (due to radiolysis in nuclear reactors) is sufficient to make even the de-mineralized water to cause stress corrosion cracking in Boiling Water Reactors. Hydrogen Water Chemistry (by hydrogen injection) to control dissolved oxygen is shown to control the stress corrosion cracking. However, it is not possible to control dissolved oxygen at all parts of the Boiling Water Reactors. Therefore, a further refinement in terms of noble metal

  4. Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

    International Nuclear Information System (INIS)

    Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin

    2014-01-01

    Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor

  5. Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin [University of Illinois, Urbana (United States)

    2014-08-15

    Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor.

  6. Nuclear power plants maintenance

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

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

  7. Nuclear Power Plants (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

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

    1973-01-01

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

  8. Team interaction skills evaluation criteria for nuclear power plant control room operators

    International Nuclear Information System (INIS)

    Montgomery, J.C.; Hauth, J.T.

    1991-01-01

    Team interaction skills are an essential aspect of safe nuclear power plant control room operations. Previous research has shown that, when a group works together, rather than as individuals, more effective operations are possible. However, little research has addressed how such team interaction skills can be measured. In this study rating scales were developed specifically for such a measurement purpose. Dimensions of team skill performance were identified from previous research and experience in the area, incorporating the input of Pacific Northwest Laboratory (PNL) contract operator licensing examiners. Rating scales were developed on the basis of these dimensions, incorporating a modified Behaviorally Anchored Rating Scale (BARS) as well as Behavioral Frequency formats. After a pilot-testing/revision process, rating data were collected using 11 control room crews responding to simulator scenarios at a boiling water and a pressurized water reactor. Statistical analyses of the resulting data revealed moderate inter-rater reliability using the Behavioral Frequency scales, relatively low inter-rater reliability using the BARS, and moderate support for convergent and discriminant validity of the scales. It was concluded that the scales show promise psychometrically and in terms of user acceptability, but that additional scale revision is needed before field implementation. Recommendations for scale revision and directions for future research were presented

  9. Framework for modeling supervisory control behavior of operators of nuclear power plants

    International Nuclear Information System (INIS)

    Baron, S.; Feehrer, C.; Muralidharan, R.; Pew, R.; Horwitz, P.

    1982-01-01

    The importance of modeling the human-machine system has long been recognized, and many attempts have been made to estimate the operator's effect on system performance and reliability. The development of reliability models has been aimed at providing the means for exploring the physical consequences of specific classes of human error. However, the total impact of human performance on system operation and the adequacy of existing design and operating standards cannot be adequatly captured or assessed by simple error probabilities, or even by the combination of such probabilities. The behaviors of relevance are supervisory in nature, with a substantial cognitive component. The broad requirements for a model of human supervisory control are extensive and suggest that a highly sophisticated computer model will be needed. The purpose of this paper is to provide a brief overview of the approach employed in developing such supervisory control models; of some proposed specializations and extensions to adapt them for the nuclear power plant case; and of the potential utility of such a model

  10. 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

  11. Regular control of monitors for effluents from nuclear power plant stacks

    International Nuclear Information System (INIS)

    Stroem, L.

    1979-01-01

    The report describes a test procedure for emission monitoring devices for nuclear power plants. The follosing procedures are described, inspection, determination of the air flow through the stack, measurement and adjustment of the flow in the stack loop, measurement and adjustment of flow and density in the measuring loop, calibration of the gas detector, efficiency of sampling of methyliodide and aerosol. (K.K.)

  12. Operational control of material release and discharges from nuclear power plant

    International Nuclear Information System (INIS)

    Szabo, I. C.; Ranga, T.; Daroczi, L.; Deme, S.; Kerekes, A.

    2003-01-01

    The operational control of radioactive materials during atmospheric release and aquatic discharge from nuclear power plant is a licensing criterion for NPPs. Originally at the Paks NPP the release control was based on activity limits for four groups of elements. These groups were noble gases, long living radio-aerosols, radioiodine and radiostrontium for atmospheric release and specified activity limit for beta emitters, strontium and tritium for aquatic discharge into Danube. These groups were controlled with proper sampling and/or measuring instrumentation. The limit for atmospheric release was given as a 30-day moving average, for liquid discharges the annual limit was stipulated. The new release and discharge limitation system is based on the environmental dose limitation. The dose constraint for Paks NPP is 90 Sv/year of the critical group for all release pathways and the investigation dose limit is equal to 27 Sv/year. The regulation did not subdivide the dose limit for atmospheric and liquid components but for operational control subdivision of dose limits for atmospheric release and aquatic discharge and shorter time period (one day-one month) seems to be useful. The subdivision can be based on past release data and/or previous activity limits. To satisfy dose below the investigation dose limit there should be a proper operation control level for each separately measured component and pathway belonging to reasonable time interval significantly shorter than one year. The main task of the NPP staff is elaboration of reasonable control levels and reference time intervals for different radionuclide and element groups to be used in operational control. Operational control levels are based on measured daily or monthly release rates. In case of noble gases, aerosols and iodine the daily release rates have several sharp peaks per year. Operational control levels give opportunity to detect these peaks for internal investigation purposes. Investigation release limits

  13. Human factors verification and validation of the advanced nuclear plant control room design

    International Nuclear Information System (INIS)

    Gutierrez, Richard; Zizzo, David; Yu, Kim

    2005-01-01

    The GE Advanced Boiling Water Reactor (ABWR) design has implemented the applicable human factors engineering (HFE) principles in the design of human-system interfaces (HSI). The ABWR uses unique features such as large mimic and touch-screen technology to present plant overviews and system operating details to the control room operating staff. The HSI designs, both in the console panels and the software generated graphical user interfaces, have been developed and evaluated using HFE guidelines. In addition to HFE guidelines reviews performed during design and implementation, broader reviews have been performed under the HFE Verification and Validation Implementation Plan (HFE V and VIP). Based upon the NUREG-0711, Nuclear Regulatory Commission (NRC) HFE Program Review Model (HFE PRM) (Reference 1), the HFE V and VIP, hereafter also referred to as V and V, has provided feedback during the various phases of design, implementation, and integration of the HSI. As one of the ten elements of the HFE PRM, the V and V activities reaffirm that the design of the HSI conforms to the HFE design principles and that the plant operating staff in the control room can perform their assigned tasks. This rigorous HFE V and V process is now being applied in the implementation of the ABWR design for Taiwan Power Company's Lungmen Power Station. Two 1350 MWe ABWR units are currently under construction at Lungmen. The HFE V and V ensures that the process for the design is compliant with the HFE principles. An important aspect of the Lungmen HFE program has been the direct involvement of the end user, Taiwan Power Company (TPC), throughout the design development and implementation. These HFE V and V activities, performed in three phases, ensures that the necessary displays, control, and alarms are provided to support the identified personnel tasks. The HFE V and V also checks to determine that the design of each identified component is compliant with the HFE principles. The V and V ensures

  14. Recent developments of and future prospects for nuclear power plant instrumentation and control in Belgium

    International Nuclear Information System (INIS)

    Naisse, J.C.

    1990-01-01

    The production of electricity in Belgium is covered for almost 70% by seven nuclear power plants all of pressurized water reactor type. Four major topics are representative of the evolution of nuclear power production in Belgium: The suspentions of the studies for the new Belgian PWR unit (DOEL 5), the commissioning of the simulators in DOEL and TIHANGE, the revamping of the oldest nuclear units, the studies of new storage installations for radioactive waste. The delay imposed on the construction of DOEL 5 will allow to go further into the examination of the implications arising from the new technologies in I and C. The use modern I and C systems for modifications in existing plants will allow a better estimation of their advantages and disadvantages. (author)

  15. Nuclear power plant safety

    International Nuclear Information System (INIS)

    Otway, H.J.

    1974-01-01

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

  16. Risks and challenges associated with the design and construction of a nuclear power plant; Control de riesgos y retos asociados al diseno y construccion de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Liebana Martinez, B.; Armas Garcia, A.; Martinez Gozalo, I.

    2011-07-01

    The construction of a nuclear power plant project, considering the period prior to the operation of the plant, requires a very strict risk control to ensure compliance with a series of challenges. The present paper identifying the most important challenges facing the construct ability and license requirements of the process, identifying the interfaces and proposing a methodology of construction to meet the challenge of a construction process in 5 years.

  17. Building of nuclear power plant

    International Nuclear Information System (INIS)

    Saito, Takashi.

    1997-01-01

    A first nuclear plant and a second nuclear power plant are disposed in adjacent with each other in a building for a nuclear reactor. A reactor container is disposed in each of the plants, and each reactor container is surrounded by a second containing facility. A repairing chamber capable of communicating with the secondary containing facilities for both of the secondary containing facilities is disposed being in contact with the second containing facility of each plant for repairing control rod driving mechanisms or reactor incorporated-type recycling pumps. Namely, the repairing chamber is in adjacent with the reactor containers of both plants, and situated between both of the plants as a repairing chamber to be used in common for both plants. Air tight inlet/exit doors are formed to the inlets/exits of both plants of the repairing chamber. Space for the repairing chamber can be reduced to about one half compared with a case where the repairing chamber is formed independently on each plant. (I.N.)

  18. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    1999-01-01

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

  19. The reactor power control system based on digital control in nuclear power plant

    International Nuclear Information System (INIS)

    Liu Chong; Zhou Jianliang; Tan Ping

    2010-01-01

    The PLC (Programmable Logical Controller), digital communication and redundant techniques are applied in the rod control and position indication system(namely the reactor power control system) to perform the power control in the 300 MW reactor automatically and integrally in Qinshan Phase I project. This paper introduces the features, digital design methods of hardware of the instrumentation and control system (I and C) in the reactor power control. It is more convenient for the information exchange by human-machine interface (HMI), operation and maintenance, and the system reliability has been greatly improved after the project being reconstructed. (authors)

  20. Implementation of a digital feedwater control system at Dresden Nuclear Power Plant, Units 2 and 3: Final report

    International Nuclear Information System (INIS)

    Zapotocky, A.; Popovic, J.R.; Fournier, R.D.

    1988-12-01

    This report describes the Digital Feedwater Control System Implementation at the Dresden 2 or 3 Units of the BWR Nuclear Power Plant owned by the Commonwealth Edison Company. The digital system has been operational in Unit 3 since August 1986, and in Unit 2 since April 1987. The Bailey Control's Network 90 based digital control system replaced the obsolete GE/MAC 5000 analog control system in the reactor feedwater control loop as a ''like-for-like'' replacement. Operational experience from the Digital Feedwater Control installations has been good and the system demonstrated better performance than the old analog systems. 14 refs., 15 figs., 17 tabs

  1. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Nakayama, Ryoichi; Kimura, Motohiko; Abe, Akira

    1993-01-01

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

  2. Nuclear plant life extension

    International Nuclear Information System (INIS)

    Negin, C.A.

    1989-01-01

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

  3. Review of safety related control room function research based on experience from nuclear power plants in Finland

    International Nuclear Information System (INIS)

    Juslin, K.; Wahlstroem, B.; Rinttilae, E.

    1985-01-01

    A comprehensive human engineering research programme was established in the second half of the 1970's at the Technical Research Centre of Finland (VTT). The research is performed in cooperation with the utility companies Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (TVO) and includes topics such as Handling of alarm information, Disturbance analysis systems, Assessment of control rooms and Validation of safety parameter display systems. Reference is also made to the Finnish contribution to the OECD Halden Reactor Project (Halden) and the Nordic Liaison Committee for Atomic Energy (NKA) research projects. In this paper feasible realization alternatives of safety related control room functions are discussed on the basis of experience from the nuclear power plants in Finland, which at present are equipped with extensive process computer systems. A proposal for future power plant information systems is described. It is intended that this proposal will serve as the basis for future computer systems at nuclear power plants in Finland. (author)

  4. Probabilistic safety assessment for instrumentation and control systems in nuclear power plants. A literature survey

    International Nuclear Information System (INIS)

    Lu, Lixuan; Jiang, Jin

    2003-01-01

    Deregulation in electricity market will create a great deal of challenges for Nuclear Power Plants (NPP). To stay competitive, NPP will need to find new ways to reduce their operation costs. In NPP, Instrumentation and Control (I and C) systems play an important role in reducing the cost of producing electricity while maintaining and/or enhancing safety. Therefore, it is extremely important that one should manage the I and C systems more efficiently and economically. Meanwhile, obsolescence problem associated with I and C systems encouraged the usage of advanced digital techniques in I and C systems. Thus, new methodologies are needed to analyze the reliability and determine the maintenance strategy for the digital I and C systems. Probabilistic Safety Assessment (PSA) has been probed to be a promising method to deal with this issue. This paper provides a literature survey on the development of digital I and C systems in NPP, followed by a detailed review of PSA including its benefits, limitations and the future direction of its development. Most importantly, potential applications of PSA in various aspects of I and C systems are brought into perspective throughout the paper. Furthermore, the applicability of PSA in the regulation of safety-related I and C systems is demonstrated. Detailed information on PSA applications in 1) the resource allocation for I and C systems: 2) the determination of surveillance testing strategies; and 3) I and C system designs, is provided. (author)

  5. BNL ALARA Center experience with an information exchange system on dose control at nuclear power plants

    International Nuclear Information System (INIS)

    Baum, J.W.; Khan, T.A.

    1992-01-01

    The essential elements of an international information exchange system on dose control at nuclear power plants are summarized. Information was collected from literature abstracting services, by attending technical meetings, by circulating data collection forms, and through personal contacts. Data are assembled in various databases and periodically disseminated to several hundred interested participants through a variety of publications and at technical meetings. Immediate on-line access to the data is available to participants with modems, commercially available communications software, and a password that is provided by the Brookhaven National Laboratory (BNL) ALARA Center to authorized users of the system. Since January 1992, rapid access also has been provided to persons with fax machines. Some information is available for ''polling'' the BNL system at any time, and other data can be installed for polling on request. Most information disseminated to data has been through publications; however, new protocols, simplified by the ALARA Center staff, and the convenience of fax machines are likely to make the earlier availability of information through these mechanisms increasingly important

  6. Advanced plant design recommendations from Cook Nuclear Plant experience

    International Nuclear Information System (INIS)

    Zimmerman, W.L.

    1993-01-01

    A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

  7. Full scope simulator of a nuclear power plant control room using 3D stereo virtual reality techniques for operators training

    International Nuclear Information System (INIS)

    Aghina, Mauricio A.C.; Mol, Antonio Carlos A.; Almeida, Adino Americo A.; Pereira, Claudio M.N.A.; Varela, Thiago F.B.

    2007-01-01

    Practical training of nuclear power plants operators are partially performed by means of simulators. Usually these simulators are physical copies of the original control roam, needing a large space on a facility being also very expensive. In this way, the proposal of this paper is to implement the use of Virtual Reality techniques to design a full scope control room simulator, in a manner to reduce costs and physical space usage. (author)

  8. Benchmarking Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jakic, I.

    2016-01-01

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

  9. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-03-01

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

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

    International Nuclear Information System (INIS)

    Nordling, Anna; Haakansson, Goeran

    2012-01-01

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

  12. Authorization of nuclear power plant control room personnel: Methods and practices with emphasis on the use of simulators

    International Nuclear Information System (INIS)

    2006-07-01

    In 2002 the IAEA published a revision to Safety Guide NS-G-2.8, Recruitment, Qualification and Training of Personnel for Nuclear Power Plants. This Safety Guide provides recommendations on the authorization of designated personnel who have a direct impact on nuclear safety. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional report be prepared that provided information on the practices in Member States on the use of simulators in the authorization of control room staff. This publication has been prepared in response to that recommendation. In gathering information for the report, Member States were asked to: respond to a survey on the use of simulators and the involvement of regulatory body in operator authorization; and to complete a questionnaire on their practices in authorizing control room staff. Safety analysis and operating experience consistently indicate that human error is a major contributor to nuclear power plant (NPP) accident risk. With the recent world wide emphasis and implementation of full scope simulators for nuclear power plant personnel training, operators spend a large portion of their training time on simulators. As described in the foreword to IAEA-TECDOC-1411, Use of Control Room Simulators for Training of Nuclear Power Plant Personnel, simulators provide operators an opportunity to learn and practice the abilities that are required in accident and infrequently used plant evolutions. Because of their fidelity, full scope simulators are now used by most Member States in the authorization examinations of control room personnel. This situation is becoming more common as more plants acquire modern full scope plant referenced simulators. This publication provides information and examples based upon experience in a variety of Member States. The body of the report provides general information that represents the practices of the Member States that contributed to the

  13. Nuclear power plant V-2

    International Nuclear Information System (INIS)

    1998-01-01

    The nuclear power plant Bohunice V -2 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - December 1976; first controlled reactor power - 7 August 1984, 2 August 1985; connection to the grid - 20 August 1984, 9 August 1985; commercial operation - 14 February 1985, 18 December 1985. This leaflet contains: NPP V-2 construction; Major technological equipment [WWER 440 V230 type reactor; Nuclear Power plant operation safety (Safety barriers; Safety systems [Active safety systems, Passive safety systems]); Centralized heat supply system; Scheme of Bohunice V-2 NPP and technical data

  14. Control-oriented modeling of the energy-production of a synchronous generator in a nuclear power plant

    International Nuclear Information System (INIS)

    Fodor, Attila; Magyar, Attila; Hangos, Katalin M.

    2012-01-01

    Nuclear Power Plant (Hungary) is developed in this paper based on first engineering principles that is able to describe the time-varying active and reactive power output of the generator. These generators are required to take part in the reactive power support of the power grid following the demand of a central dispatch center, and also contribute to the frequency control of the grid. The developed model has been verified under the usual controlled operating conditions when the frequency and the active power are controlled. Static and dynamic sensitivity analysis has been applied to determine the model parameters to be estimated. The model parameters have been estimated applying the asynchronous parallel pattern search method using real measured data from the nuclear power plant. The confidence regions in the parameter space have been analyzed by investigating the geometry of the estimation error function. The developed model can serve as a basis for controlling the optimal energy production of the generator using both the active and reactive power components. -- Highlights: ► A dynamic model of a synchronous generator in a Nuclear Power Plant is developed. ► The model has been verified under the usual controlled operating conditions. ► The sensitivity analysis has been applied to determine the model parameters. ► The parameters have been estimated applying the APPS method using measured data. ► The model serves as a basis for controlling the optimal energy production of the generator.

  15. Role of expert systems in the operation and control of nuclear power plants

    International Nuclear Information System (INIS)

    Rozenholc, M.

    1985-09-01

    This paper summarizes the past improvements and remaining limitations of plant control systems, defines knowledge engineering and proposes some prospects for future uses of expert systems in plant operation, discusses the present involvement in expert systems and the status of the first applications and, finally, draws some simple conclusions

  16. Severe accident management: radiation dose control, Fukushima Daiichi and TMI-2 nuclear plant accidents

    International Nuclear Information System (INIS)

    Shaw, Roger

    2014-01-01

    This presentation presents valuable dose information related to the Fukushima Daiichi and Three Mile Island Unit 2 (TMI-2) Nuclear Plant accidents. Dose information is provided for what is well known for TMI-2, and what is available for Fukushima Daiichi. Particular emphasis is placed on the difference between the type of reactors involved, overarching plant damage issues, and radiation worker dose outcomes. For TMI-2, more in depth dose data is available for the accident and the subsequent recovery efforts. The comparisons demonstrate the need to understand the wide variation in potential dose management measures and outcomes for severe reactor accidents. (author)

  17. Structural optimization of static power control programs of nuclear power plants with WWER-1000

    International Nuclear Information System (INIS)

    Kokol, E.O.

    2015-01-01

    The question of possibility the power control programs switching for WWER-1000 is considered. The aim of this research is to determine the best program for the power control of nuclear reactor under cyclic diurnal behavior of electrical generation, as well as the switching implementation. The considered problem of finding the best control program refers to the multicriteria optimization class of problems. Operation of the nuclear power generation system simulated using the following power control programs: with constant average temperature of transfer fluid, with constant pressure in the reactor secondary circuit, with constant temperature in input of the nuclear reactor. The target function was proposed. It consists of three normalized criteria: the burn up fraction, the damage level of fuel rod array shells, as well as changes in the power values. When simulation of the nuclear power generation system operation within the life was done, the values of the selected criteria were obtained and inserted in the target function. The minimum of three values of the target function depending on the control program at current time defined the criterion of switching of considered static power control programs for nuclear power generation system

  18. Control of subcontractors by civil works contractor for a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Xinguo, Jiang [Huaxing Construction Company, Yizheng, JS (China)

    1995-10-01

    The civil works (CW) contractor is responsible for managing its subcontractors according to the requirements of quality assurance programme including the establishment of organization, quality assurance management, document control, material control, construction schedule control, inspection and test control, non-conformance control, corrective actions and executive technical files. The responsibilities of the plant owner, the CW contractor and its subcontractors in relation to performing their functions in the above-mentioned activities are described in detail.

  19. Control of subcontractors by civil works contractor for a nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Xinguo

    1995-10-01

    The civil works (CW) contractor is responsible for managing its subcontractors according to the requirements of quality assurance programme including the establishment of organization, quality assurance management, document control, material control, construction schedule control, inspection and test control, non-conformance control, corrective actions and executive technical files. The responsibilities of the plant owner, the CW contractor and its subcontractors in relation to performing their functions in the above-mentioned activities are described in detail

  20. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 5. Control of population densities surrounding nuclear power plants

    International Nuclear Information System (INIS)

    Nero, A.V.; Schroeder, C.H.; Yen, W.W.S.

    1977-01-01

    In view of the requirement that the California Energy Resources Conservation and Development Commission must specify land-use/population-density control measures to be used in the vicinity of nuclear power plants being granted land use, the possible forms of such measures are examined. Since these measures must maintain population densities below Nuclear Regulatory Commission criteria, if appropriate, NRC criteria for land use and population densities are given particular attention. In addition, a preliminary comparison of the cost of possible control measures with the reduced potential for damage to the public health and safety is made, yielding the result that control measures within approximately one mile of the plant site may be justified, in certain cases, on a strictly cost-benefit basis. However, it is not clear whether controls over such a limited region would satisfy the legal mandate

  1. Experience in incorporation control of operation personnel of the Reinsberg nuclear power plant (1967 - 1973)

    International Nuclear Information System (INIS)

    Pul'khajm, K.F.; Klyuke, Kh.

    1976-01-01

    A theoretic estimate of fission products and corrosion nuclides in a WWR type reactor is given. The results of radiation monitoring of the personnel irradiation at the Reinsberg (DDR) nuclear power plant are presented. It is supposed that the intake of fission and corrosion products has been realized through inhalation. The equivalent doses of internal irradiation are calculated. The estimate of the results of radiation monitoring are presented [ru

  2. Advanced digital instrumentation and control system for nuclear power plant protection

    Energy Technology Data Exchange (ETDEWEB)

    Sabino, D [VVER Engineering, Westinghouse Electric Corporation (United States)

    1998-12-31

    The Diverse Protection System is a back-up to the Primary Reactor Protection System developed for use at the Temelin nuclear power plant. The DPS is a digital system which provides a wealth of benefits from today`s advanced technology. These benefits include a compact hardware design with high performance microprocessors and a structured software design using a high level language. An overview of the DPS functions, hardware and software is provided. (author). 1 fig., 1 tab.

  3. Export Control Guide: Loose Parts Monitoring Systems for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Langenberg, Donald W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2012-12-01

    This report describes a typical LPMS, emphasizing its application to the RCS of a modern NPP. The report also examines the versatility of AE monitoring technology by describing several nuclear applications other than loose parts monitoring, as well as some non-nuclear applications. In addition, LPMS implementation requirements are outlined, and LPMS suppliers are identified. Finally, U.S. export controls applicable to LPMSs are discussed.

  4. Electrical supply and controls for induced-draft cooling towers at Browns Ferry Nuclear Plant

    International Nuclear Information System (INIS)

    Mock, C.H.; Boehms, J.H.

    1975-01-01

    Design considerations are given for selection of electrical features as required for addition of mechanical-draft-type cooling towers at an existing multiunit nuclear generating station. Environmental and nuclear safety problems were solved economically by use of enclosed 161-kV power connections, oil-filled transformers, supervisory-type control, and unique schemes for redundancy to minimize need for Class 1E construction

  5. Nuclear power plant analyzer

    International Nuclear Information System (INIS)

    Stritar, A.

    1986-01-01

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

  6. Nuclear plant scram reduction

    International Nuclear Information System (INIS)

    Wiegle, H.R.

    1986-01-01

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

  7. Nuclear power plant control and instrumentation activities in Argentina during 1989-1991

    International Nuclear Information System (INIS)

    Lorenzetti, J.R.

    1992-01-01

    A brief resume of the activities in the different areas of control and instrumentation is included. As there was a delay in the construction of the new power plant most of the effort were dedicated to the plants that they are in operation. It has been added instrumentation to have better information in the control room and to check new variables of the plant according with the experience learned from the operation. It was dedicated special strength in the areas of training simulators and in service inspection. (author)

  8. Development of Export Control Comprehensive Management Model for Nuclear Power Plants and Others Projects

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chansuh; Seo, Hana; Choi, Sundo [Korea Institute of Nuclear Nonproliferation And Control, Daejeon (Korea, Republic of)

    2014-05-15

    It is required that there are lots of managements of care and concern if the project contains strategic items such as NPPs. The Korean nuclear industry and its related companies, such as the Korea Hydro and Nuclear Power (KHNP), are promoting greater exports of NPPs. It is likely that Korea will export more this technology to newcomer states in the future. As a result, the ROK has been improving its export control management system for NPPs. In keeping with this national effort, Korea Institute of Nuclear Nonproliferation And Control (KINAC) developed comprehensive export control management model for NPPs and other projects, in preparation for this projected growth in the industry. This model also applies to the nuclear export case of the UAE, aims to manage the project from bidding to the end of the contract. The recent Export Licensing of Nuclear Facility Technology was reflected in the Notice on Export and Import of Strategic Items in January 2014. Through this license, the large-scale project legislation framework was established. It can also minimize nonproliferation concerns of the international community through strict management. It is expected that the Korea will be able to enhance transparency and secure the nuclear use, while meeting nonproliferation purpose.

  9. Development of Export Control Comprehensive Management Model for Nuclear Power Plants and Others Projects

    International Nuclear Information System (INIS)

    Lee, Chansuh; Seo, Hana; Choi, Sundo

    2014-01-01

    It is required that there are lots of managements of care and concern if the project contains strategic items such as NPPs. The Korean nuclear industry and its related companies, such as the Korea Hydro and Nuclear Power (KHNP), are promoting greater exports of NPPs. It is likely that Korea will export more this technology to newcomer states in the future. As a result, the ROK has been improving its export control management system for NPPs. In keeping with this national effort, Korea Institute of Nuclear Nonproliferation And Control (KINAC) developed comprehensive export control management model for NPPs and other projects, in preparation for this projected growth in the industry. This model also applies to the nuclear export case of the UAE, aims to manage the project from bidding to the end of the contract. The recent Export Licensing of Nuclear Facility Technology was reflected in the Notice on Export and Import of Strategic Items in January 2014. Through this license, the large-scale project legislation framework was established. It can also minimize nonproliferation concerns of the international community through strict management. It is expected that the Korea will be able to enhance transparency and secure the nuclear use, while meeting nonproliferation purpose

  10. Nuclear plant license renewal

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  11. A distributed architecture in the control of the PWR 1300 MW nuclear plants of electricite de France

    International Nuclear Information System (INIS)

    Guesnier, G.; Varaldi, G.

    1980-01-01

    Since 1974, EDF has developed the control and instrumentation technology in its nuclear power plants. Technological improvements in microelectronics led to the development by CGEE ALSTHOM of automation equipment, so called CONTROBLOC, meeting the following objectives: introduction of automation at high security and availability level; progressive implementation in design offices and on sites by operators not specialized in electronics or data processing; great flexibility, permitting the configuration of various systems; survivability to first failure; and capability of self-diagnosis. Characterized by modular, programmed and multiplexed structure with distributed software, the CONTROBLOC equipment is under commissioning in the first 1300 MW nuclear plant. An introduction is given to the main characteristics of the equipment peculiar to 1300 MW power plants, and descriptions are offered of working methods adopted by the design offices, problems met during development, and operating conditions in the first months. (auth)

  12. Optimal replacement and inspection periods of safety and control boards in Wolsung nuclear power plant unit 1

    International Nuclear Information System (INIS)

    Mok, Jin Il

    1993-02-01

    In nuclear power plants, the safety and control systems are important for operating and maintaining safety of nuclear power plants. Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Since the start of first commercial operation of Kori nuclear power plant (NPP) unit 1, the trips caused by instrument and control systems account for 28% of total trips of NPPs in Korea. Even a single trip of a nuclear power plant causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this work we investigated the optimal replacement periods of the digital control computer's (DCC) and the programmable digital comparator's (PDC) electronic circuit boards of Wolsung nuclear power plant Unit 1. We first derived mathematical models which calculate optimal replacement periods for electronic circuit boards of digital control computer (DCC) and for those of the programmable digital comparator (PDC) in Wolsung NPP unit 1. And we analytically obtained the optimal replacement periods of electronic circuit boards by using these models. We compared these periods with the replacement periods currently used at Wolsung NPP Unit. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained for the electronic circuit boards of DCC and those used in the field shown small difference : the optimal replacement periods analytically obtained for the electronic circuit boards of PDC are shorter than those used in the field in general. The engineered safeguards of Wolsung nuclear power plant unit 1 contains redundant systems of 2-out-of-3 logic which are not operating under normal conditions but they are called

  13. Artificial intelligence expert system for nuclear power plant control and maintenance

    International Nuclear Information System (INIS)

    Westrom, G.B.

    1987-01-01

    A major concern in emergency response in a nuclear power plant is the lack of real experience with a catastrophic condition. Experts do more than just follow a set of rules. They have experience and insight into problems and are able to use their professional judgement. The objectives of this expert system are: Detect subtle off-normal trends in a reactor power plant system. Alert the operator with color graphics and synthesized voice commands. Identify the source of the problem and advise the operator on steps to restore the plant to normal operation. Provide an explanation facility and database to supply detailed information on component history and reasoning process. The RHRS (Residual Heat Removal System) was selected for the initial expert systems development because it is extremely important during refueling and cold shutdown operations

  14. Primary Water Chemistry Control at Units of Paks Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Schunk, J.; Pinter, G. Patek T.; Tilky, P.; Doma, A. [Paks Nuclear Power Plant Co. Ltd., Paks (Hungary); Osz, J. [Budapest University of Technology and Economics, Budapest (Hungary)

    2013-03-15

    The primary water chemistry of the four identical units of Paks Nuclear Power Plant has been developed based on Western type PWR units, taking into consideration some Russian modifications. The political changes in the 1990s have also influenced the water chemistry specifications and directions. At PWR units the transition operational modes have been developed while in case of WWER units - in lack of central uniform regulation - this question has become the competence and responsibility of each individual plant. This problem has resulted in separate water chemistry developments with a considerable time delay. The need for lifetime extensions worldwide has made the development of startup and shutdown chemistry procedures extremely important, since they considerably influence the long term and safe operation of plants. The uniformly structured limit value system, the principles applied for the system development, and the logic schemes for actions to be taken are discussed in the paper, both for normal operation and transition modes. (author)

  15. Development of control room design in French PWR nuclear power plants

    International Nuclear Information System (INIS)

    Guesnier, G.

    1996-01-01

    The layouts of the control rooms of the French nuclear power stations have undergone great development in the period 1970-1990. The control rooms, with an architecture similar to that of the oil fired power stations, were similar to those of the 1300 MW blocks in which the human factor was emphasised. For the selection of a computerised control room for the N4 series, comprehensive functional and ergonomical validation on a full simulator was required. (author) 3 figs., 7 refs

  16. Nuclear plant safety

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

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

  17. Commentary on nuclear power plant control room habitability - including a review of related LERs (1981-1983)

    International Nuclear Information System (INIS)

    Moeller, D.W.; Kotra, J.P.

    1985-01-01

    A review of Licensee Event Reports filed by the operator of commercial nuclear power plants from 1981 through 1983 has revealed that approximately 3% pertain to systems that maintain or monitor control room habitability. Dominant contributors were deficiencies in normal and emergency trains of heating, ventilation, air conditioning and air cleaning systems (45%), deficiencies in atmospheric monitors for toxic and radioactive substances (27%) and deficiencies in fire protection systems (13%). To correct the situation revealed by these analyses and by information provided from other sources, it is recommended that the NRC incorporate into its program plan the development of information that anticipates the conditions within a control room during emergencies, and that criteria for habitability within the control room be better defined. In addition, it is suggested than an improved protocol for testing control room air-related systems be developed, that the required thickness and number of layers of charcoal adsorption beds for control room air cleaning systems be re-evaluated, and that steps be taken to improve the quality of heating, ventilating, air conditioning and air cleaning components. It is also recommended that greater emphasis be placed on maintaining nuclear power plant control rooms in a habitable condition during emergencies so that the operators can remain there and safely shut down the plant, in contrast to placing reliance on the use of remote shutdown panels or auxiliary control facilities

  18. Single event upset mitigation techniques for FPGAs utilized in nuclear power plant digital instrumentation and control

    International Nuclear Information System (INIS)

    Wang Xin; Holbert, Keith E.; Clark, Lawrence T.

    2011-01-01

    Highlights: → Triple modular redundancy (TMR) implementation is the best solution for digital I and C. → Maximal probability of two simultaneous errors with TMR maximum partition is 4.44%. → Dual modular redundancy minimum logic partitioning design is an additional option. - Abstract: Field programmable gate arrays (FPGAs) are integrated circuits being increasingly used for digital instrumentation and control (I and C) in nuclear power plants (NPPs) because of low cost, re-configurability and low design turn-around time. However, to ensure reliability, proper design techniques must be employed since the memory and logic in FPGAs are susceptible to single event upsets (SEUs). Triple modular redundancy (TMR) has become a common SEU mitigation design technique because of its straightforward implementation and reliable results. Partitioned TMR approaches are introduced in this paper, and formulae derived indicate that the maximum probability of two simultaneous errors [P E ] max is inversely proportional to the number of logic partitions in a TMR design, when each redundant logic block in every logic partition has the same number of sensitive nodes. However, the maximum logic partitioning design cannot completely eliminate the possibility of two simultaneous upsets. For the example test circuit it is found that [P E ] max is reduced dramatically from 66.67% for minimum logic partitioning to 4.44% for maximum logic partitioning. Because TMR introduces significant overhead due to its full hardware redundancy, a dual modular redundancy approach is also examined for application to less demanding situations. By comparative analysis this study reaches the conclusion that the maximum logic partitioning TMR implementation is the best solution for digital I and C applications in NPPs where obtaining robustness is of the highest importance, despite its higher area overhead.

  19. Human factors design, verification, and validation for two types of control room upgrades at a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Laurids Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-10-01

    This paper describes the NUREG-0711 based human factors engineering (HFE) phases and associated elements required to support design, verification and validation (V&V), and implementation of a new plant process computer (PPC) and turbine control system (TCS) at a representative nuclear power plant. This paper reviews ways to take a human-system interface (HSI) specification and use it when migrating legacy PPC displays or designing displays with new functionality. These displays undergo iterative usability testing during the design phase and then undergo an integrated system validation (ISV) in a full scope control room training simulator. Following the successful demonstration of operator performance with the systems during the ISV, the new system is implemented at the plant, first in the training simulator and then in the main control room.

  20. Human factors design, verification, and validation for two types of control room upgrades at a nuclear power plant

    International Nuclear Information System (INIS)

    Boring, Laurids Ronald

    2014-01-01

    This paper describes the NUREG-0711 based human factors engineering (HFE) phases and associated elements required to support design, verification and validation (V&V), and implementation of a new plant process computer (PPC) and turbine control system (TCS) at a representative nuclear power plant. This paper reviews ways to take a human-system interface (HSI) specification and use it when migrating legacy PPC displays or designing displays with new functionality. These displays undergo iterative usability testing during the design phase and then undergo an integrated system validation (ISV) in a full scope control room training simulator. Following the successful demonstration of operator performance with the systems during the ISV, the new system is implemented at the plant, first in the training simulator and then in the main control room.