WorldWideScience

Sample records for instrumentation state control

  1. Current state and prospects of the IBR-2M instrument control software

    International Nuclear Information System (INIS)

    Kirilov, A.S.

    2011-01-01

    The article is devoted to the main features and plans of future improvements of the Sonix + instrumental complex, which is used now to control experimental hardware at the IBR-2M spectrometers. The Sonix + software inherited basic solutions from the older Sonix system. In particular, those are the modular organization using special database for device control and reflection of the current system state, using script programming for the measured procedure. At the same time, some basic features were revised to make the system more unified, flexible and comfortable for the user. Main changes can be grouped as follows: structural enhancements, using the Python as a script language, GUI redesign and unification, remote supervision and instrument control via network. During the last years, this complex has been tested at some IBR-2 instruments (REMUR, NERA-PR) and on some instruments at other centers. We are planning to install it at the other instruments of IBR-2M as well

  2. [Controlling instruments in radiology].

    Science.gov (United States)

    Maurer, M

    2013-10-01

    Due to the rising costs and competitive pressures radiological clinics and practices are now facing, controlling instruments are gaining importance in the optimization of structures and processes of the various diagnostic examinations and interventional procedures. It will be shown how the use of selected controlling instruments can secure and improve the performance of radiological facilities. A definition of the concept of controlling will be provided. It will be shown which controlling instruments can be applied in radiological departments and practices. As an example, two of the controlling instruments, material cost analysis and benchmarking, will be illustrated.

  3. Reactor instrumentation and control

    International Nuclear Information System (INIS)

    Wach, D.; Beraha, D.

    1980-01-01

    The methods for measuring radiation are shortly reviewed. The instrumentation for neutron flux measurement is classified into out-of-core and in-core instrumentation. The out-of-core instrumentation monitors the operational range from the subcritical reactor to full power. This large range is covered by several measurement channels which derive their signals from counter tubes and ionization chambers. The in-core instrumentation provides more detailed information on the power distribution in the core. The self-powered neutron detectors and the aeroball system in PWR reactors are discussed. Temperature and pressure measurement devices are briefly discussed. The different methods for leak detection are described. In concluding the plant instrumentation part some new monitoring systems and analysis methods are presented: early failure detection methods by noise analysis, acoustic monitoring and vibration monitoring. The presentation of the control starts from an qualitative assessment of the reactor dynamics. The chosen control strategy leads to the definition of the part-load diagram, which provides the set-points for the different control systems. The tasks and the functions of these control systems are described. In additiion to the control, a number of limiting systems is employed to keep the reactor in a safe operating region. Finally, an outlook is given on future developments in control, concerning mainly the increased application of process computers. (orig./RW)

  4. State-of-the-art report for the instrumentation and control technology based on the nuclear-information technology convergence

    International Nuclear Information System (INIS)

    Kwon, Kee Choon; Kim, Chang Hwoi; Lee, Dong Young; Lee, Cheol Kwon; Lee, Hyun Chul

    2011-12-01

    As digitalized the instrumentation and control systems in nuclear power plants, in the past that were implemented in an analog system or circuit for monitoring, control and protection, most of the them is implemented in embedded software based on hardware platform. Digital instrumentation and control system hardware platforms and a digital safety systems have developed in Korea. The fundamental technology of the software part of MMIS (Man-Machine Interface System) has achieved the localization. But in order to secure our global competitiveness, in the -based software, the source of the content areas / It is needed to develop core technologies of the software and contents areas based on the nuclear-IT convergence technology. In this report, the IT technology centered for the characteristics of embedded software applied to nuclear power is described. Also state-of-the-art IT technologies that will converge to nuclear power plants are mentioned

  5. Control of training instrument

    International Nuclear Information System (INIS)

    Seo, K. W.; Joo, Y. C.; Park, J. C.; Hong, C. S.; Choi, I. K.; Cho, B. J.; Lee, H. Y.; Seo, I. S.; Park, N. K.

    1996-01-01

    This report describes the annual results on control of training instrument. The scope and contents are the following: 1. Control of Compact Nuclear Simulator 2. Control of Radiation/Radioactivity Measurement 3. Control of Non-Destructive Testing Equipment 4. Control of Chemical Equipment 5. Control of Personal Computer 6. Other related Lecture Aid Equipment. Efforts were employed to upgrade the training environment through retrofitting experimental facilities, compiling teaching materials and reforcing audio-visual aids. The Nuclear Training Center executed the open-door training courses for 2,496 engineers/scientists from the nuclear regulatory, nuclear industries, research institutes and other related organizations by means of offering 45 training courses during the fiscal year 1995. (author). 15 tabs., 7 figs., 13 refs

  6. State of art and next challenges in instrumentation for quality control in hadron therapy centres

    International Nuclear Information System (INIS)

    Karkar, S.; Pauna, N.; Testa, E.

    2008-01-01

    The in-beam positron emission tomography (PET) is currently the only feasible non-invasive method for in-situ monitoring of tumour treatments with ion beams. It is able of assessing parameters relevant for quality assurance, i.e. the particle range in tissue, the position of the irradiated volume and the local deviations between planned and applied distributions. It was used for the first time for quality assurance at GSI hadron-therapy center since 1997: the acquisition is performed during the irradiation and some minutes afterwards which allows the detection of both short-lived and long-lived isotopes and avoids to move the patient. Moreover we can imagine that such in-line PET could be improved to become an on-line PET in conditions that number of LOR detected (Lines of Responses) is large enough and time of reconstruction is short enough to provide typically an image every tens of seconds. The objectives pursued with the present work are to outline present limitations and future challenges of in-beam PET instrumentation. The aim of Part I is to present the prerequisites for a in-beam PET system as well as recent studies to optimise the detector geometry and its performances (by testing modern gamma ray detectors) as well as data processing methods (including adapted reconstruction methods for PET data).In Part II, in-beam and on-line PET challenges are identified. Performances of new fast scintillators and photodetectors are presented in correlation with expected tasks for an optimal delivered dose monitoring. The need of additional simulations for estimating the feasibility of a real time PET camera is obvious. This part also includes a discussion about the possibility of using gamma prompt radiation as a monitor of the dose inside patient under certain conditions

  7. State of art and next challenges in instrumentation for quality control in hadron therapy centres

    Energy Technology Data Exchange (ETDEWEB)

    Karkar, S. [Aix-Marseille Univ., CNRS/IN2P3, Centre de Physique des Particules de Marseille, CPPM, 13 - Marseille (France); Pauna, N. [Universite Blaise Pascal, CNRS/IN2P3, Lab. de Physique Corpusculaire (LPC) Clermont, 63 - Aubiere (France); Testa, E. [Lyon-1 Univ., CNRS/IN2P3, Institut de Physique Nucleaire de Lyon (IPNL), 69 - Villeurbanne (France)

    2008-07-01

    The in-beam positron emission tomography (PET) is currently the only feasible non-invasive method for in-situ monitoring of tumour treatments with ion beams. It is able of assessing parameters relevant for quality assurance, i.e. the particle range in tissue, the position of the irradiated volume and the local deviations between planned and applied distributions. It was used for the first time for quality assurance at GSI hadron-therapy center since 1997: the acquisition is performed during the irradiation and some minutes afterwards which allows the detection of both short-lived and long-lived isotopes and avoids to move the patient. Moreover we can imagine that such in-line PET could be improved to become an on-line PET in conditions that number of LOR detected (Lines of Responses) is large enough and time of reconstruction is short enough to provide typically an image every tens of seconds. The objectives pursued with the present work are to outline present limitations and future challenges of in-beam PET instrumentation. The aim of Part I is to present the prerequisites for a in-beam PET system as well as recent studies to optimise the detector geometry and its performances (by testing modern gamma ray detectors) as well as data processing methods (including adapted reconstruction methods for PET data).In Part II, in-beam and on-line PET challenges are identified. Performances of new fast scintillators and photodetectors are presented in correlation with expected tasks for an optimal delivered dose monitoring. The need of additional simulations for estimating the feasibility of a real time PET camera is obvious. This part also includes a discussion about the possibility of using gamma prompt radiation as a monitor of the dose inside patient under certain conditions.

  8. PEP instrumentation and control system

    Energy Technology Data Exchange (ETDEWEB)

    Melen, R.

    1980-06-01

    This paper describes the operating characteristics of the primary components that form the PEP Instrumentation and Control System. Descriptions are provided for the computer control system, beam monitors, and other support systems.

  9. PEP instrumentation and control system

    International Nuclear Information System (INIS)

    Melen, R.

    1980-06-01

    This paper describes the operating characteristics of the primary components that form the PEP Instrumentation and Control System. Descriptions are provided for the computer control system, beam monitors, and other support systems

  10. Performing instrumentation and controls upgrades

    International Nuclear Information System (INIS)

    Kessler, F. M.; Connell, T. J.; Ryan, M. P.

    1992-01-01

    control upgrades. Digital equipment provides state of the art status and has been proven by extensive use in both non-nuclear applications and nuclear applications. It is flexible, can reduce spare parts inventory, can support expanded I and C functions, and can be readily substituted for current safety and non-safety instrumentation and controls. The backbit and installation of instrumentation and control equipment will be described in this paper from many perspectives. Areas such as current technology, availability, testability, reliability, information display, and maintenance need to be considered. Various approaches available to carry out an I and C upgrade along with the PROM's and con's of certain methods will be discussed. Finally, the actual implementation of the upgrade will be described including specific examples of methods to ensure maximum efficiency and to minimize the 'in plant' requirements to support implementing the upgrade

  11. Notes on instrumentation and control

    CERN Document Server

    Roy, G J

    2013-01-01

    Notes on Instrumentation and Control presents topics on pressure (i.e., U-tube manometers and elastic type gauges), temperature (i.e. glass thermometer, bi-metallic strip thermometer, filled system thermometer, vapor pressure thermometer), level, and flow measuring devices. The book describes other miscellaneous instruments, signal transmitting devices, supply and control systems, and monitoring systems. The theory of automatic control and semi-conductor devices are also considered. Marine engineers will find the book useful.

  12. Tokamak instrumentation and controls

    International Nuclear Information System (INIS)

    Becraft, W.R.; Bettis, E.S.; Houlberg, W.A.; Onega, R.J.; Stone, R.S.

    1979-02-01

    The three areas of study emphasis to date are: (1) Physics implications for controls, (2) Computer simulation, and (3) Shutdown/aborts. This document reports on the FY 78 efforts (the first year of these studies) to address these problems. Transient scenario options for the startup of a tokamak are developed, and the implications for the control system are discussed. This document also presents a hybrid computer simulation (analog and digital) of the Impurity Study Experiment (ISX-B) which is now being used for corroborative controls investigations. The simulation will be expanded to represent a TNS/ETF machine

  13. INSTRUMENTATION CONTROLLING INDUSTRIAL PLANT

    Directory of Open Access Journals (Sweden)

    Марина Владимировна Чувашлова

    2013-04-01

    Full Text Available The purpose of this study is to analyze theoretical and practical basis of controlling and to provide implementation guidelines for enterprise controlling. The problem of controlling implementation was considered by two criteria: sphere of application and time of validity.Taking into account sphere of application criterion the objectives can be achieved by certain tools, namely: management accounting in the form of profit and loss statement; information flow in the form of workflow system and mapping of business processes; planning which includes budgeting and monitoring that could in turn allow to compare performance to predetermined standards, plans or objectives; responsibility accounting.The second criterion that is time of validity is considered as strategic.DOI: http://dx.doi.org/10.12731/2218-7405-2013-1-39

  14. Advances in control and instrumentation

    International Nuclear Information System (INIS)

    Surendar, Ch.

    1994-01-01

    Control and instrumentation systems have seen significant changes from pneumatic to electronic with the advent of transistors and integrated circuits. Miniaturization was realised. With the introduction of microprocessors there has been a revolutionary change in the approach in instrumentation and control systems in the areas of sensors, data acquisition/transmission, processing for control, and presentation of the information to the operator. An effort is made to give some insight into these areas, with some idea of the advantages to which these systems are being put to use in the nuclear facilities, particularly nuclear power reactors. (author)

  15. Experimental and Computational Instrumentation for Rotorcraft Noise and Vibration Control Research at the Penn State Rotorcraft Center

    National Research Council Canada - National Science Library

    Smith, Edward

    2001-01-01

    A team of faculty at the Penn State Rotorcraft Center of Excellence has integrated five new facilities into a broad range of research and educational programs focused on rotorcraft noise and vibration control...

  16. Reconstruction of instrumentation and control system (SKR)

    International Nuclear Information System (INIS)

    Wiening, K.-H.

    2001-01-01

    For the first time extensive upgrades have been performed in all safety related areas of units with WWER 440/230 reactors. One of the most important actions was the replacement of the safety and safety related instrumentation and control. The state of the art digital safety instrumentation and control system TELEPERM XS has been implemented in units 1 and 2 of the Bohunice V1 power plant. The requirements as deduced from safety assessments conducted by commissions of international experts have been fulfilled, so that Bohunice V1 after this gradual reconstruction has been upgraded to an internationally accepted safety level for the remainder of its service life. (author)

  17. An improved instrument setpoint control program

    International Nuclear Information System (INIS)

    Cash, J.S. Jr.; George, R.T.; Kincaid, S.C.

    1991-01-01

    Instrument setpoints have a definite and often significant impact on plant safety, reliability, and availability. Although typically overshadowed by plant design, modification, and physical change activities, instrument setpoints can alter plant status and system operating characteristics just as significantly. Recognizing the need for a formal program that provides configuration control of instrument setpoints, provides a readily accessible and clearly documented basis for instrument setpoints, and integrates and coordinates operations, engineering, and maintenance activities that influence the basis for instrument setpoints, Philadelphia Electric Company (PECo) is developing an Improved Instrument Setpoint Control Program (IISCP) that incorporates current industry guidance and practices and state-of-the-art information systems technology. The IISCP was designed around PECo's then existing business processes for setpoint control, determination, and maintenance. A task force representing the various constituencies from both plants and the engineering and services organizations were formed to identify objectives and design features for the IISCP. Utilizing industry standards and guidance, regulatory documents, the experiences and good practices obtained from other utilities, and PECo's nuclear group strategies, objectives, and goals, specific objectives were identified to enhance the business processes

  18. Instrument Remote Control via the Astronomical Instrument Markup Language

    Science.gov (United States)

    Sall, Ken; Ames, Troy; Warsaw, Craig; Koons, Lisa; Shafer, Richard

    1998-01-01

    The Instrument Remote Control (IRC) project ongoing at NASA's Goddard Space Flight Center's (GSFC) Information Systems Center (ISC) supports NASA's mission by defining an adaptive intranet-based framework that provides robust interactive and distributed control and monitoring of remote instruments. An astronomical IRC architecture that combines the platform-independent processing capabilities of Java with the power of Extensible Markup Language (XML) to express hierarchical data in an equally platform-independent, as well as human readable manner, has been developed. This architecture is implemented using a variety of XML support tools and Application Programming Interfaces (API) written in Java. IRC will enable trusted astronomers from around the world to easily access infrared instruments (e.g., telescopes, cameras, and spectrometers) located in remote, inhospitable environments, such as the South Pole, a high Chilean mountaintop, or an airborne observatory aboard a Boeing 747. Using IRC's frameworks, an astronomer or other scientist can easily define the type of onboard instrument, control the instrument remotely, and return monitoring data all through the intranet. The Astronomical Instrument Markup Language (AIML) is the first implementation of the more general Instrument Markup Language (IML). The key aspects of our approach to instrument description and control applies to many domains, from medical instruments to machine assembly lines. The concepts behind AIML apply equally well to the description and control of instruments in general. IRC enables us to apply our techniques to several instruments, preferably from different observatories.

  19. Renovation of PARR instrumentation and controls

    International Nuclear Information System (INIS)

    Karim, A.; Haq, I.; Akhtar, K.M.; Alam, G.D.

    1987-01-01

    The Pakistan research reactor (PARR) was commissioned in 1965 and operated since then in accordance with the requirements. In the first instance, it was proposed that the controls and instrumentation be modernized according to the state of current technology and for meeting the more stringent safety, and operational needs. A computer has been added for data acquisition, logging and analysis. A closed circuit television system has been installed to monitor access of personnel to the reactor building and for viewing the reactor core with an underwater camera. This report gives a brief account of the old instrumentation and some details of the new replacements. (orig./A.B)

  20. Integrated Instrumentation and Control Upgrade Plan

    International Nuclear Information System (INIS)

    Wilkinson, D.; Sun, B.; Wray, L.; Smith, J.

    1992-02-01

    This document presents the first industry-wide integrated research and development plan to support upgrading instrumentation and control (I ampersand C) systems in nuclear power plants in the United States. The plan encompasses both solving obsolescence problems and introducing modern I ampersand C technology into the industry. Accomplishing this plan will provide the technological base to modernize existing plants, as well as bridge the gap to meet Advanced Light Water Reactor (ALWR) requirements for modern I ampersand C systems. This plan defines Research and Development tasks to meet the identified needs for the following technical elements: Instrumentation, Control and Protection, Man-Machine Support Systems, Maintenance, Communications, Verification and Validation, and Specifications and Standards

  1. Instrumentation, Control, and Intelligent Systems

    Energy Technology Data Exchange (ETDEWEB)

    2005-09-01

    Abundant and affordable energy is required for U.S. economic stability and national security. Advanced nuclear power plants offer the best near-term potential to generate abundant, affordable, and sustainable electricity and hydrogen without appreciable generation of greenhouse gases. To that end, Idaho National Laboratory (INL) has been charged with leading the revitalization of nuclear power in the U.S. The INL vision is to become the preeminent nuclear energy laboratory with synergistic, world-class, multi-program capabilities and partnerships by 2015. The vision focuses on four essential destinations: (1) Be the preeminent internationally-recognized nuclear energy research, development, and demonstration laboratory; (2) Be a major center for national security technology development and demonstration; (3) Be a multi-program national laboratory with world-class capabilities; (4) Foster academic, industry, government, and international collaborations to produce the needed investment, programs, and expertise. Crucial to that effort is the inclusion of research in advanced instrumentation, control, and intelligent systems (ICIS) for use in current and advanced power and energy security systems to enable increased performance, reliability, security, and safety. For nuclear energy plants, ICIS will extend the lifetime of power plant systems, increase performance and power output, and ensure reliable operation within the system's safety margin; for national security applications, ICIS will enable increased protection of our nation's critical infrastructure. In general, ICIS will cost-effectively increase performance for all energy security systems.

  2. Instrumentation, Control, and Intelligent Systems

    International Nuclear Information System (INIS)

    Not Available

    2005-01-01

    Abundant and affordable energy is required for U.S. economic stability and national security. Advanced nuclear power plants offer the best near-term potential to generate abundant, affordable, and sustainable electricity and hydrogen without appreciable generation of greenhouse gases. To that end, Idaho National Laboratory (INL) has been charged with leading the revitalization of nuclear power in the U.S. The INL vision is to become the preeminent nuclear energy laboratory with synergistic, world-class, multi-program capabilities and partnerships by 2015. The vision focuses on four essential destinations: (1) Be the preeminent internationally-recognized nuclear energy research, development, and demonstration laboratory; (2) Be a major center for national security technology development and demonstration; (3) Be a multi-program national laboratory with world-class capabilities; (4) Foster academic, industry, government, and international collaborations to produce the needed investment, programs, and expertise. Crucial to that effort is the inclusion of research in advanced instrumentation, control, and intelligent systems (ICIS) for use in current and advanced power and energy security systems to enable increased performance, reliability, security, and safety. For nuclear energy plants, ICIS will extend the lifetime of power plant systems, increase performance and power output, and ensure reliable operation within the system's safety margin; for national security applications, ICIS will enable increased protection of our nation's critical infrastructure. In general, ICIS will cost-effectively increase performance for all energy security systems

  3. IAEA safeguards instrumentation: Development, implementation and control

    International Nuclear Information System (INIS)

    Rundquist, D.E.

    1983-01-01

    Extensive development efforts over the last 5 years have produced a number of new instruments to help the IAEA meet its safeguards obligations. Implementation of these new instruments is proceeding at a necessarily slower pace. To optimize the performance and reliability of the instrumentation systems when used in safeguards applications, increasing attention is needed to be spent on performance monitoring and control of the instruments. (author)

  4. Activities at the electric power research institute to support the modernization of instrumentation and control systems in nuclear power plants in the United States of America

    International Nuclear Information System (INIS)

    Naser, J.

    1998-01-01

    Most nuclear power plants in the United States are operating with a vast majority of their original analog instrumentation and control (I and C) equipment. Many of the I and C systems in the plants need to be modernized in a reliable and cost-effective manner to replace obsolete equipment, to reduce operating and maintenance (O and M) costs, to improve plant performance, and to maintain safety. 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 the need for more cost-effective power production. The increasing O and M costs to maintain systems experiencing obsolescence problems is counter to the needs for more cost-effective power production and improved competitiveness. Modern technology, especially digital systems, offers improved functionality, performance, and reliability; solutions to obsolescence of equipment; reduction in O and M costs, and the potential to enhance safety. Digital I and C systems with their inherent advantages will be implemented only if reliable and cost-effective implementation and licensing acceptance is achieved and if the modernized system supports reduced power production costs. Increasing competition will continue to be a major factor in the operation of nuclear power plants. I will continue to dictate the need for improved productivity and cost-effectiveness. EPRI and its members utilities are working together on an industry-wide Instrumentation and Control Program to address I and C issues and to develop cost-effective solutions. (author)

  5. Component- and system-level degradation modeling of digital Instrumentation and Control systems based on a Multi-State Physics Modeling Approach

    International Nuclear Information System (INIS)

    Wang, Wei; Di Maio, Francesco; Zio, Enrico

    2016-01-01

    Highlights: • A Multi-State Physics Modeling (MSPM) framework for reliability assessment is proposed. • Monte Carlo (MC) simulation is utilized to estimate the degradation state probability. • Due account is given to stochastic uncertainty and deterministic degradation progression. • The MSPM framework is applied to the reliability assessment of a digital I&C system. • Results are compared with the results obtained with a Markov Chain Model (MCM). - Abstract: A system-level degradation modeling is proposed for the reliability assessment of digital Instrumentation and Control (I&C) systems in Nuclear Power Plants (NPPs). At the component level, we focus on the reliability assessment of a Resistance Temperature Detector (RTD), which is an important digital I&C component used to guarantee the safe operation of NPPs. A Multi-State Physics Model (MSPM) is built to describe this component degradation progression towards failure and Monte Carlo (MC) simulation is used to estimate the probability of sojourn in any of the previously defined degradation states, by accounting for both stochastic and deterministic processes that affect the degradation progression. The MC simulation relies on an integrated modeling of stochastic processes with deterministic aging of components that results to be fundamental for estimating the joint cumulative probability distribution of finding the component in any of the possible degradation states. The results of the application of the proposed degradation model to a digital I&C system of literature are compared with the results obtained by a Markov Chain Model (MCM). The integrated stochastic-deterministic process here proposed to drive the MC simulation is viable to integrate component-level models into a system-level model that would consider inter-system or/and inter-component dependencies and uncertainties.

  6. Fusion instrumentation and control: a development strategy

    International Nuclear Information System (INIS)

    Hsu, P.Y.; Greninger, R.C.; Longhurst, G.R.; Madden, P.

    1981-01-01

    We have examined requirements for a fusion instrumentation and control development program to determine where emphasis is needed. The complex, fast, and closely coupled system dynamics of fusion reactors reveal a need for a rigorous approach to the development of instrumentation and control systems. A framework for such a development program should concentrate on three principal need areas: the operator-machine interface, the data and control system architecture, and fusion compatible instruments and sensors. System dynamics characterization of the whole fusion reactor system is also needed to facilitate the implementation process in each of these areas. Finally, the future need to make the instrumentation and control system compatible with the requirements of a commercial plant is met by applying transition technology. These needs form the basis for the program tasks suggested

  7. Evaluation of robotically controlled advanced endoscopic instruments

    NARCIS (Netherlands)

    Reilink, Rob; Kappers, Astrid M.L.; Stramigioli, Stefano; Misra, Sarthak

    Background Advanced flexible endoscopes and instruments with multiple degrees of freedom enable physicians to perform challenging procedures such as the removal of large sections of mucosal tissue. However, these advanced endoscopes are difficult to control and require several physicians to

  8. Evolution of the VLT instrument control system toward industry standards

    Science.gov (United States)

    Kiekebusch, Mario J.; Chiozzi, Gianluca; Knudstrup, Jens; Popovic, Dan; Zins, Gerard

    2010-07-01

    The VLT control system is a large distributed system consisting of Linux Workstations providing the high level coordination and interfaces to the users, and VME-based Local Control Units (LCU's) running the VxWorks real-time operating system with commercial and proprietary boards acting as the interface to the instrument functions. After more than 10 years of VLT operations, some of the applied technologies used by the astronomical instruments are being discontinued making it difficult to find adequate hardware for future projects. In order to deal with this obsolescence, the VLT Instrumentation Framework is being extended to adopt well established Commercial Off The Shelf (COTS) components connected through industry standard fieldbuses. This ensures a flexible state of the art hardware configuration for the next generation VLT instruments allowing the access to instrument devices via more compact and simpler control units like PC-based Programmable Logical Controllers (PLC's). It also makes it possible to control devices directly from the Instrument Workstation through a normal Ethernet connection. This paper outlines the requirements that motivated this work, as well as the architecture and the design of the framework extension. In addition, it describes the preliminary results on a use case which is a VLTI visitor instrument used as a pilot project to validate the concepts and the suitability of some COTS products like a PC-based PLCs, EtherCAT8 and OPC UA6 as solutions for instrument control.

  9. How To Control Color Appearance With Instrumentation

    Science.gov (United States)

    Burns, Margaret E.

    1980-05-01

    Colorimetry, as defined by the International Commission on Illumination, is the measurement of colors, made possible by the properties of the eye and based on a set of conventions. Instrumentation for measuring object color, therefore, must be based on a human observer. The intent is to design an instrument that in effect responds as a person would, so that research development, production control and quality control areas have some means of assessing the acceptability of the appearance of a product. Investigations of a human observer's psychological response to color, and the manner in which visual observations are made, give the instrument designer and manufacturer data necessary to answer two questions: a. How can we put numbers (instrument read-out) on a perception that occurs in the brain of the observer? b. What can we learn from examination of a visual observing situation that will guide us in our design of an instrumental simulation of this situation? Involving as it does our own daily, almost unconscious, practice of making judgments concerning the things we see, the design and manufacture of color measurement instruments is an exceedingly interesting field. The advances being made concurrently today in research concerning human color vision and in optical and electronic technology will make possible increasingly useful instrumentation for quality control of product color.

  10. Fuel fabrication instrumentation and control system overview

    International Nuclear Information System (INIS)

    Bennett, D.W.; Fritz, R.L.

    1980-10-01

    A process instrumentation and control system is being developed for automated fabrication of breeder reactor fuel at the Hanford Engineering Development Laboratory (HEDL) in Richland, Washington. The basic elements of the control system are a centralized computer system linked to distributed local computers, which direct individual process applications. The control philosophy developed for the equipment automation program stresses system flexibility and inherent levels of redundant control capabilities. Four different control points have been developed for each unit process operation

  11. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission`s dispositions

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Norio; Suzudo, Tomoaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission`s (USNRC`s) responses to the recommendations made by the NRC`s study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC`s dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  12. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission's dispositions

    International Nuclear Information System (INIS)

    Watanabe, Norio; Suzudo, Tomoaki

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission's (USNRC's) responses to the recommendations made by the NRC's study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC's dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  13. Planning instruments to control urban growth

    DEFF Research Database (Denmark)

    Jørgensen, Gertrud; Nielsen, Thomas Alexander Sick

    2010-01-01

    It is challenging to plan and control urban development in peri-urban areas. But if no planning is done, the result will often be unsustainable, including widespread, dispersed and uncoordinated urban growth. Spatial planning based on zoning remains the most important planning instrument and its...... success depend on regional coordination. Incentive based instruments may contrbute to growth management, but only few examples are available and their effects on urban growth patterns yet to be seen....

  14. Mechanical engineers' handbook, design, instrumentation, and controls

    CERN Document Server

    Kutz, Myer

    2015-01-01

    Full coverage of electronics, MEMS, and instrumentation andcontrol in mechanical engineering This second volume of Mechanical Engineers' Handbookcovers electronics, MEMS, and instrumentation and control, givingyou accessible and in-depth access to the topics you'll encounterin the discipline: computer-aided design, product design formanufacturing and assembly, design optimization, total qualitymanagement in mechanical system design, reliability in themechanical design process for sustainability, life-cycle design,design for remanufacturing processes, signal processing, dataacquisition and dis

  15. The NSTX Central Instrumentation and Control System

    International Nuclear Information System (INIS)

    G. Oliaro; J. Dong; K. Tindall; P. Sichta

    1999-01-01

    Earlier this year the National Spherical Torus Experiment (NSTX) at the Princeton Plasma Physics Laboratory achieved ''first plasma''. The Central Instrumentation and Control System was used to support plasma operations. Major elements of the system include the Process Control System, Plasma Control System, Network System, Data Acquisition System, and Synchronization System. This paper will focus on the Process Control System. Topics include the architecture, hardware interface, operator interface, data management, and system performance

  16. Quality control of nuclear medicine instruments 1991

    International Nuclear Information System (INIS)

    1991-05-01

    This document gives detailed guidance on the quality control of various instruments used in nuclear medicine. A first preliminary document was drawn up in 1979. A revised and extended version, incorporating recommended procedures, test schedules and protocols was prepared in 1982. The first edition of ''Quality Control of Nuclear Medicine Instruments'', IAEA-TECDOC-317, was printed in late 1984. Recent advances in the field of nuclear medicine imaging made it necessary to add a chapter on Camera-Computer Systems and another on SPECT Systems. Figs and tabs

  17. Quality control of nuclear medicine instruments, 1991

    International Nuclear Information System (INIS)

    1996-12-01

    This document gives detailed guidance on the quality control of various instruments used in nuclear medicine. A first preliminary document was drawn up in 1979. A revised and extended version, incorporating recommended procedures, test schedules and protocols was prepared in 1982. The first edition of 'Quality Control of Nuclear Medicine Instruments', IAEA-TECDOC-317, was printed in late 1984. Recent advances in the field of nuclear medicine imaging made it necessary to add a chapter on Camera-Computer Systems and another on SPECT Systems

  18. Measurement control program for NDA instruments

    International Nuclear Information System (INIS)

    Hsue, S.T.; Marks, T.

    1983-01-01

    Measurement control checks for nondestructive assay instruments have been a constant and continuing concern at Los Alamos National Laboratory. This paper summarizes the evolution of the measurement control checks in the various high-resolution gamma systems we have developed. In-plant experiences with these systems and checks will be discussed. Based on these experiences, a set of measurement control checks is recommended for high-resolution gamma-ray systems

  19. Neutronic control instrumentation of protection systems

    International Nuclear Information System (INIS)

    Furet, J.

    1977-01-01

    The aims of neutronic control instrumentation are briefly recalled and the present status of materials research and development is presented. As for the out-of-pile instrumentation, emphasis is put on the reliability and efficiency of the detectors and the new solutions of electric signal processing. The possible reactivity measurements at rest are examined. As for in-pile instrumentation results relating to mobile detectors of the type of miniaturized fission chambers are presented. The radiation tests on course of development for several years in the working conditions of neutron self-powdered detectors are analyzed so as to show that their use as built-in in-core instrumentation is to be envisaged at short term. Basic options inherent to the 'Nuclear Safety' philosophy that define the protection system are recalled. A definition and a justification of the performance testing of the instrumentation at rest and in-service are then derived. Some new solutions are envisaged for processing the digital data obtained from the various sensors . A quality control of the materials setting conditions (especially electric noise) ensures a high reliability and availability of the materials involved in the neutron control and the protection system in working conditions [fr

  20. Instrument ampersand controls section (IA) improvements

    International Nuclear Information System (INIS)

    Kramer, C.; Paul, J.

    1993-01-01

    This portion of the panel session briefly delineates improvements in the Instrument and Controls (IA) Section over the past few years. These improvements are listed briefly in summary form. The status of publication of the IA Section of AG-1 is reviewed

  1. Electrical, instrumentation, and control codes and standards

    International Nuclear Information System (INIS)

    Kranning, A.N.

    1978-01-01

    During recent years numerous documents in the form of codes and standards have been developed and published to provide design, fabrication and construction rules and criteria applicable to instrumentation, control and power distribution facilities for nuclear power plants. The contents of this LTR were prepared by NUS Corporation under Subcontract K5108 and provide a consolidated index and listing of the documents selected for their application to procurement of materials and design of modifications and new construction at the LOFT facility. These codes and standards should be applied together with the National Electrical Code, the ID Engineering Standards and LOFT Specifications to all LOFT instrument and electrical design activities

  2. 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)

  3. Quality control of nuclear medicine instrumentation

    International Nuclear Information System (INIS)

    Mould, R.F.

    1983-09-01

    The proceedings of a conference held by the Hospital Physicists' Association in London 1983 on the quality control of nuclear medicine instrumentation are presented. Section I deals with the performance of the Anger gamma camera including assessment during manufacture, acceptance testing, routine testing and long-term assessment of results. Section II covers interfaces, computers, the quality control problems of emission tomography and the quality of software. Section III deals with radionuclide measurement and impurity assessment and Section IV the presentation of images and the control of image quality. (U.K.)

  4. Electrical Bioimpedance-Controlled Surgical Instrumentation.

    Science.gov (United States)

    Brendle, Christian; Rein, Benjamin; Niesche, Annegret; Korff, Alexander; Radermacher, Klaus; Misgeld, Berno; Leonhardt, Steffen

    2015-10-01

    A bioimpedance-controlled concept for bone cement milling during revision total hip replacement is presented. Normally, the surgeon manually removes bone cement using a hammer and chisel. However, this procedure is relatively rough and unintended harm may occur to tissue at any time. The proposed bioimpedance-controlled surgical instrumentation improves this process because, for example, most risks associated with bone cement removal are avoided. The electrical bioimpedance measurements enable online process-control by using the milling head as both a cutting tool and measurement electrode at the same time. Furthermore, a novel integrated surgical milling tool is introduced, which allows acquisition of electrical bioimpedance data for online control; these data are used as a process variable. Process identification is based on finite element method simulation and on experimental studies with a rapid control prototyping system. The control loop design includes the identified process model, the characterization of noise as being normally distributed and the filtering, which is necessary for sufficient accuracy ( ±0.5 mm). Also, in a comparative study, noise suppression is investigated in silico with a moving average filter and a Kalman filter. Finally, performance analysis shows that the bioimpedance-controlled surgical instrumentation may also performs effectively at a higher feed rate (e.g., 5 mm/s).

  5. Instrumentation and controls of an ignited tokamak

    International Nuclear Information System (INIS)

    Becraft, W.R.; Golzy, J.; Houlberg, W.A.; Kukielka, C.A.; Onega, R.J.; Raju, G.V.S.; Stone, R.S.

    1980-10-01

    The instrumentation and controls (I and C) of an ignited plasma magnetically confined in a tokamak configuration needs increased emphasis in the following areas: (1) physics implications for control; (2) plasma shaping/position control; and (3) control to prevent disruptive instabilities. This document reports on the FY 1979 efforts in these and other areas. Also presented are discusssions in the areas of: (1) diagnostics suitable for the Engineering Test Facility (ETF); and (2) future research and development (R and D) needs. The appendices focus attention on some preliminary ideas about the measurement of the deuteron-triton (D-T) ratio in the plasma, synchrotron radiation, and divertor control. Finally, an appendix documenting the thermal consequences to the first wall of a MPD is presented

  6. Card controlled beta backscatter thickness measuring instrument

    International Nuclear Information System (INIS)

    Schlesinger, J.

    1978-01-01

    An improved beta backscatter instrument for the nondestructive measurement of the thickness of thin coatings on a substrate is described. Included therein is the utilization of a bank of memory stored data representative of isotope, substrate, coating material and thickness range characteristics in association with a control card having predetermined indicia thereon selectively representative of a particular isotope, substrate material, coating material and thickness range for conditioning electronic circuit means by memory stored data selected in accord with the predetermined indicia on a control card for converting backscattered beta particle counts into indicia of coating thickness

  7. Designer's handbook of instrumentation and control circuits

    CERN Document Server

    Carr, Joseph J

    1991-01-01

    Here is a comprehensive, practical guide to the entire process of analog instrumentation and control, from sensor input to data conversion circuitry and final output. This readable handbook avoids complex mathematical treatments, instead taking an applications-oriented approach and presenting many sample circuits and concrete examples. It is an essential reference for engineers and high-level technicians in a variety of scientific and engineering fields--anywhere data is collected electronically and where such data is used to control physical processes.Key Features* Covers design o

  8. Interpreting two state instruments for intermediary values

    International Nuclear Information System (INIS)

    Good, R.R.

    1979-01-01

    Interpolating data from instruments which produce only two distinct binary outputs is discussed. The problem of determining void fraction, given an instrument which produces only a liquid or a no-liquid output, is used to demonstrate three different methods of data interpolation. The three methods involve a form of time averaging. The methods are signal amplitude histogram, signal derivative, and signal derivative discriminator. The advantages, disadvantages, and accuracies of each method are described

  9. Declarative flow control for distributed instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    Parvin, Bahram; Taylor, John; Fontenay, Gerald; Callahan, Daniel

    2001-06-01

    We have developed a 'microscopy channel' to advertise a unique set of on-line scientific instruments and to let users join a particular session, perform an experiment, collaborate with other users, and collect data for further analysis. The channel is a collaborative problem solving environment (CPSE) that allows for both synchronous and asynchronous collaboration, as well as flow control for enhanced scalability. The flow control is a declarative feature that enhances software functionality at the experimental scale. Our testbed includes several unique electron and optical microscopes with applications ranging from material science to cell biology. We have built a system that leverages current commercial CORBA services, Web Servers, and flow control specifications to meet diverse requirements for microscopy and experimental protocols. In this context, we have defined and enhanced Instrument Services (IS), Exchange Services (ES), Computational Services (CS), and Declarative Services (DS) that sit on top of CORBA and its enabling services (naming, trading, security, and notification) IS provides a layer of abstraction for controlling any type of microscope. ES provides a common set of utilities for information management and transaction. CS provides the analytical capabilities needed for online microscopy. DS provides mechanisms for flow control for improving the dynamic behavior of the system.

  10. Proceedings: Instrumentation and control test reduction workshop

    International Nuclear Information System (INIS)

    1991-09-01

    Instrumentation and control (I ampersand C) surveillance and testing is a significant contributor to operations and management costs. Several techniques to eliminate or reduce manual testing requirements could reduce costs while improving plant safety and performance. I ampersand C test reduction was the subject of this 1991 workshop. The workshop covered test elimination, test reduction, test automation, and relevant standards and benefits. The conclusions of the workshop were the following: More utility information sharing is important. There is a significant amount of information available throughout the industry, but it is not available in a concise, useable form. An I ampersand C utility users group is needed to address items such as instrument calibration reduction, set-point methodologies, and other current I ampersand C issues. The workshop was well received. The timing is right to initiate actions to reduce testing

  11. Instrumentation between science, state and industry

    CERN Document Server

    Shinn, Terry

    2001-01-01

    these. In this book, we appropriate their conception of research-technology, and ex­ tend it to many other phenomena which are less stable and less localized in time and space than the Zeeman/Cotton situation. In the following pages, we use the concept for instances where research activities are orientated primarily toward technologies which facilitate both the production of scientific knowledge and the production of other goods. In particular, we use the tenn for instances where instruments and meth­ ods· traverse numerous geographic and institutional boundaries; that is, fields dis­ tinctly different and distant from the instruments' and methods' initial focus. We suggest that instruments such as the ultra-centrifuge, and the trajectories of the men who devise such artefacts, diverge in an interesting way from other fonns of artefacts and careers in science, metrology and engineering with which students of science and technology are more familiar. The instrument systems developed by re­ search-technolo...

  12. Instrumentation and control doctrine for VVER upgrading

    International Nuclear Information System (INIS)

    Pernette, R.; Cucciniello, J.; Trebot, R.

    1997-01-01

    The main results are reported of analyses carried out on the WWER-400 and WWER-1000 series, and the reasons are summed up underlying the decision to establish a policy of WWER instrumentation and control upgrading. It is shown that such a policy forms a key stage in any upgrading project and contributes to the improvement of reactor safety at several levels: it helps to optimize the integration of safety requirements; it makes it easier to achieve a high level of automation and a better man-machine interaction; it should raise the culture of reactor safety. Four annexes demonstrate the factual fundamentals and structure of such a policy. (A.K.)

  13. CARMENES instrument control system and operational scheduler

    Science.gov (United States)

    Garcia-Piquer, Alvaro; Guàrdia, Josep; Colomé, Josep; Ribas, Ignasi; Gesa, Lluis; Morales, Juan Carlos; Pérez-Calpena, Ana; Seifert, Walter; Quirrenbach, Andreas; Amado, Pedro J.; Caballero, José A.; Reiners, Ansgar

    2014-07-01

    The main goal of the CARMENES instrument is to perform high-accuracy measurements of stellar radial velocities (1m/s) with long-term stability. CARMENES will be installed in 2015 at the 3.5 m telescope in the Calar Alto Observatory (Spain) and it will be equipped with two spectrographs covering from the visible to the near-infrared. It will make use of its near-IR capabilities to observe late-type stars, whose peak of the spectral energy distribution falls in the relevant wavelength interval. The technology needed to develop this instrument represents a challenge at all levels. We present two software packages that play a key role in the control layer for an efficient operation of the instrument: the Instrument Control System (ICS) and the Operational Scheduler. The coordination and management of CARMENES is handled by the ICS, which is responsible for carrying out the operations of the different subsystems providing a tool to operate the instrument in an integrated manner from low to high user interaction level. The ICS interacts with the following subsystems: the near-IR and visible channels, composed by the detectors and exposure meters; the calibration units; the environment sensors; the front-end electronics; the acquisition and guiding module; the interfaces with telescope and dome; and, finally, the software subsystems for operational scheduling of tasks, data processing, and data archiving. We describe the ICS software design, which implements the CARMENES operational design and is planned to be integrated in the instrument by the end of 2014. The CARMENES operational scheduler is the second key element in the control layer described in this contribution. It is the main actor in the translation of the survey strategy into a detailed schedule for the achievement of the optimization goals. The scheduler is based on Artificial Intelligence techniques and computes the survey planning by combining the static constraints that are known a priori (i.e., target

  14. Quality control of nuclear medicine instruments

    International Nuclear Information System (INIS)

    1984-11-01

    This document, which gives detailed guidance on the quality control of the various electronic instruments used for radiation detection and measurement in nuclear medicine, stems from the work of two Advisory Groups convened by the International Atomic Energy Agency (IAEA). A preliminary document, including recommended test schedules but lacking actual protocols for the tests, was drawn up by the first of these groups, meeting at the IAEA Headquarters in Vienna in 1979. A revised and extended version, incorporating recommended test protocols, was prepared by the second Group, meeting likewise in Vienna in 1982. This version is the model for the present text. The document should be of value to all nuclear medicine units, and especially to those in developing countries, in the initiation or revision of schemes for the quality control of their instruments. Its recommendations have provided the basis for instruction in two IAEA regional technical co-operation projects in the subject field, one initiated in 1981 for countries of Latin America and one initiated in 1982 for countries of Asia and the Pacific

  15. Instrumentation and Control in Anaerobic Digestion

    DEFF Research Database (Denmark)

    Anaerobic digestion is a multistep process, and is most applied to solids destruction and wastewater treatment for energy production. Despite wide application, and long-term industrial proof of application, some industries are still reluctant to apply this technology. One of the classical reasons...... benchmark. There has therefore been, overall, a quantum advance in application and sophistication of instrumentation and control in anaerobic digestion, and it is an effective option for improved process loading rate and conversion efficiency....... are still a limitation, but this is being partly addressed by the increased complexity of digestion processes. Methods for control benchmarking have also been improved, as there is now an industry standard model (the IWA ADM1), and this is being applied in an improved whole wastewater treatment plant...

  16. Instrumentation

    International Nuclear Information System (INIS)

    Prieur, G.; Nadi, M.; Hedjiedj, A.; Weber, S.

    1995-01-01

    This second chapter on instrumentation gives little general consideration on history and classification of instrumentation, and two specific states of the art. The first one concerns NMR (block diagram of instrumentation chain with details on the magnets, gradients, probes, reception unit). The first one concerns precision instrumentation (optical fiber gyro-meter and scanning electron microscope), and its data processing tools (programmability, VXI standard and its history). The chapter ends with future trends on smart sensors and Field Emission Displays. (D.L.). Refs., figs

  17. Web based remote instrumentation and control

    International Nuclear Information System (INIS)

    Dhekne, P.S.; Patil, Jitendra; Kulkarni, Jitendra; Babu, Prasad; Lad, U.C.; Rahurkar, A.G.; Kaura, H.K.

    2001-01-01

    The Web-based technology provides a very powerful communication medium for transmitting effectively multimedia information containing data generated from various sources, which may be in the form of audio, video, text, still or moving images etc. Large number of sophisticated web based software tools are available that can be used to monitor and control distributed electronic instrumentation projects. For example data can be collected online from various smart sensors/instruments such as images from CCD camera, pressure/ humidity sensor, light intensity transducer, smoke detectors etc and uploaded in real time to a central web server. This information can be processed further, to take control action in real time from any remote client, of course with due security care. The web-based technology offers greater flexibility, higher functionality, and high degree of integration providing standardization. Further easy to use standard browser based interface at the client end to monitor, view and control the desired process parameters allow you to cut down the development time and cost to a great extent. A system based on a web client-server approach has been designed and developed at Computer division, BARC and is operational since last year to monitor and control remotely various environmental parameters of distributed computer centers. In this paper we shall discuss details of this system, its current status and additional features which are currently under development. This type of system is typically very useful for Meteorology, Environmental monitoring of Nuclear stations, Radio active labs, Nuclear waste immobilization plants, Medical and Biological research labs., Security surveillance and in many such distributed situations. A brief description of various tools used for this project such as Java, CGI, Java Script, HTML, VBScript, M-JPEG, TCP/IP, UDP, RTP etc. along with their merits/demerits have also been included

  18. Human machine interface for research reactor instrumentation and control system

    International Nuclear Information System (INIS)

    Mohd Sabri Minhat; Mohd Idris Taib; Izhar Abu Hussin; Zareen Khan Abdul Jalil Khan; Nurfarhana Ayuni Joha

    2010-01-01

    Most present design of Human Machine Interface for Research Reactor Instrumentation and Control System is modular-based, comprise of several cabinets such as Reactor Protection System, Control Console, Information Console as well as Communication Console. The safety, engineering and human factor will be concerned for the design. Redundancy and separation of signal and power supply are the main factor for safety consideration. The design of Operator Interface absolutely takes consideration of human and environmental factors. Physical parameters, experiences, trainability and long-established habit patterns are very important for user interface, instead of the Aesthetic and Operator-Interface Geometry. Physical design for New Instrumentation and Control System of RTP are proposed base on the state-of- the-art Human Machine Interface design. (author)

  19. 30 CFR 77.314 - Automatic temperature control instruments.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Automatic temperature control instruments. 77... UNDERGROUND COAL MINES Thermal Dryers § 77.314 Automatic temperature control instruments. (a) Automatic temperature control instruments for thermal dryer system shall be of the recording type. (b) Automatic...

  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. 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

  2. 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.)

  3. 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)

  4. Designing communication and remote controlling of virtual instrument network system

    Science.gov (United States)

    Lei, Lin; Wang, Houjun; Zhou, Xue; Zhou, Wenjian

    2005-01-01

    In this paper, a virtual instrument network through the LAN and finally remote control of virtual instruments is realized based on virtual instrument and LabWindows/CVI software platform. The virtual instrument network system is made up of three subsystems. There are server subsystem, telnet client subsystem and local instrument control subsystem. This paper introduced virtual instrument network structure in detail based on LabWindows. Application procedure design of virtual instrument network communication, the Client/the programming mode of the server, remote PC and server communication far realizing, the control power of the workstation is transmitted, server program and so on essential technical were introduced. And virtual instruments network may connect to entire Internet on. Above-mentioned technology, through measuring the application in the electronic measurement virtual instrument network that is already built up, has verified the actual using value of the technology. Experiment and application validate that this design is resultful.

  5. Designing communication and remote controlling of virtual instrument network system

    International Nuclear Information System (INIS)

    Lei Lin; Wang Houjun; Zhou Xue; Zhou Wenjian

    2005-01-01

    In this paper, a virtual instrument network through the LAN and finally remote control of virtual instruments is realized based on virtual instrument and LabWindows/CVI software platform. The virtual instrument network system is made up of three subsystems. There are server subsystem, telnet client subsystem and local instrument control subsystem. This paper introduced virtual instrument network structure in detail based on LabWindows. Application procedure design of virtual instrument network communication, the Client/the programming mode of the server, remote PC and server communication far realizing, the control power of the workstation is transmitted, server program and so on essential technical were introduced. And virtual instruments network may connect to entire Internet on. Above-mentioned technology, through measuring the application in the electronic measurement virtual instrument network that is already built up, has verified the actual using value of the technology. Experiment and application validate that this design is resultful

  6. An investigation of secure remote instrument control

    International Nuclear Information System (INIS)

    Schissel, D.P.; Abla, G.; Fredian, T.; Greenwald, M.; Penaflor, B.G.; Stillerman, J.; Walker, M.L.; Ciarlette, D.J.

    2010-01-01

    This paper examines the computer science issues associated with secure remote instrumentation control for magnetic fusion experiments. Computer science research into enhancing the ability to scientifically participate in a fusion experiment remotely has been growing in size in an attempt to better address the needs of fusion scientists worldwide. The natural progression of this research is to examine how to move from remote scientific participation to remote hardware control. The vision is to define a gatekeeper software system that will be the only channel of interaction for incoming requests to the secured area of the experimental site. The role of the gatekeeper is to validate the identification and access privilege of the requestor and to insure the general validity of the proposed request. The vision for the gatekeeper is that it be a modular system that is simple in design and defined in a way that makes its implementation and operation transparent and obvious. The architecture of the module interface is flexible enough that it can easily allow the future addition of new modules. At the same time, it should be transparent to end-users and allow a high volume of activity so as to not provide a work bottleneck. The results of the gatekeeper design and initial implementation are presented as well as a discussion on the implication of this research on the operation of fusion experimental machines such as ITER.

  7. An investigation of secure remote instrument control

    Energy Technology Data Exchange (ETDEWEB)

    Schissel, D.P., E-mail: schissel@fusion.gat.co [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States); Abla, G. [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States); Fredian, T.; Greenwald, M. [Massachusetts Institute of Technology, Cambridge, MA (United States); Penaflor, B.G. [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States); Stillerman, J. [Massachusetts Institute of Technology, Cambridge, MA (United States); Walker, M.L. [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States); Ciarlette, D.J. [US ITER Project Office, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2010-07-15

    This paper examines the computer science issues associated with secure remote instrumentation control for magnetic fusion experiments. Computer science research into enhancing the ability to scientifically participate in a fusion experiment remotely has been growing in size in an attempt to better address the needs of fusion scientists worldwide. The natural progression of this research is to examine how to move from remote scientific participation to remote hardware control. The vision is to define a gatekeeper software system that will be the only channel of interaction for incoming requests to the secured area of the experimental site. The role of the gatekeeper is to validate the identification and access privilege of the requestor and to insure the general validity of the proposed request. The vision for the gatekeeper is that it be a modular system that is simple in design and defined in a way that makes its implementation and operation transparent and obvious. The architecture of the module interface is flexible enough that it can easily allow the future addition of new modules. At the same time, it should be transparent to end-users and allow a high volume of activity so as to not provide a work bottleneck. The results of the gatekeeper design and initial implementation are presented as well as a discussion on the implication of this research on the operation of fusion experimental machines such as ITER.

  8. An Investigation of Secure Remote Instrument Control

    Energy Technology Data Exchange (ETDEWEB)

    Schissel, D.; Abla, G.; Penaflor, B. [General Atomics, San Diego (United States); Ciarlette, D. [Oak Ridge National Laboratory, Oak Ridge (United States)

    2009-07-01

    This paper examines the computer science issues associated with secure remote instrumentation control for magnetic fusion experiments. Computer science research into enhancing the ability to scientifically participate in a fusion experiment remotely has been growing in size in an attempt to better address the needs of fusion scientists worldwide. The natural progression of this research is to examine how to move from remote scientific participation to remote hardware control. The vision is to define a gatekeeper software system that will be the only channel of interaction for incoming requests to the experimental site. The role of the gatekeeper is to validate the identification and access privilege of the requester and to insure the validity of the proposed request. The vision for the gatekeeper is that it be a modular system that is simple in design and defined in a way that makes its implementation and operation transparent and obvious. The architecture of the module interface is flexible enough that it can easily allow the future addition of new modules. At the same time, it should be transparent to end-users and allow a high volume of activity so as to not provide a work bottleneck. Appropriate security requires the ability to verify identity (authentication), verify access control (authorization), and validate the appropriateness of requests. The validation process can include provenance and semantic methodologies. The results of the gatekeeper design and initial prototype testing will be presented as well as a discussion on the implication of this research on the operation of fusion experimental machines such as ITER. (authors)

  9. Development of NPTC-11 intelligence control instrument with digital display

    International Nuclear Information System (INIS)

    Wang Chengming; Pu Li; Yu Jiang; Xue Yuping; Zhang Bo; Chen Yong

    2007-01-01

    The accurate of the process control gauge has direct influence on the safe operation of nuclear power plants. Therefore it is necessary to accumulate experiences for the domestic development of this Instrument. In this paper, NPTC-11 intelligence control Instrument with digital display is developed based on the design code for nuclear Instrument, considering the actual application requirements and technical redundancy. Its application in nuclear power plant for almost one year indicates that this Instrument satisfies the development purpose and requirements. (authors)

  10. DOE Fundamentals Handbook: Instrumentation and Control, Volume 1

    International Nuclear Information System (INIS)

    1992-06-01

    The Instrumentation and Control Fundamentals Handbook was developed to assist nuclear facility operating contractors provide operators, maintenance personnel, and the technical staff with the necessary fundamentals training to ensure a basic understanding of instrumentation and control systems. The handbook includes information on temperature, pressure, flow, and level detection systems; position indication systems; process control systems; and radiation detection principles. This information will provide personnel with an understanding of the basic operation of various types of DOE nuclear facility instrumentation and control systems

  11. DOE Fundamentals Handbook: Instrumentation and Control, Volume 2

    International Nuclear Information System (INIS)

    1992-06-01

    The Instrumentation and Control Fundamentals Handbook personnel, and the technical staff facility operating contractors provide operators, maintenance personnel, and the technical staff with the necessary fundamentals training to ensure a basic understanding of instrumentation and control systems. The handbook includes information on temperature, pressure, flow, and level detection systems; position indication systems; process control systems; and radiation detection principles. This information will provide personnel with an understanding of the basic operation of various types of DOE nuclear facility instrumentation and control systems

  12. DOE Fundamentals Handbook: Instrumentation and Control, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1992-06-01

    The Instrumentation and Control Fundamentals Handbook was developed to assist nuclear facility operating contractors provide operators, maintenance personnel, and the technical staff with the necessary fundamentals training to ensure a basic understanding of instrumentation and control systems. The handbook includes information on temperature, pressure, flow, and level detection systems; position indication systems; process control systems; and radiation detection principles. This information will provide personnel with an understanding of the basic operation of various types of DOE nuclear facility instrumentation and control systems.

  13. Computer utility for interactive instrument control

    International Nuclear Information System (INIS)

    Day, P.

    1975-08-01

    A careful study of the ANL laboratory automation needs in 1967 led to the conclusion that a central computer could support all of the real-time needs of a diverse collection of research instruments. A suitable hardware configuration would require an operating system to provide effective protection, fast real-time response and efficient data transfer. An SDS Sigma 5 satisfied all hardware criteria, however it was necessary to write an original operating system; services include program generation, experiment control real-time analysis, interactive graphics and final analysis. The system is providing real-time support for 21 concurrently running experiments, including an automated neutron diffractometer, a pulsed NMR spectrometer and multi-particle detection systems. It guarantees the protection of each user's interests and dynamically assigns core memory, disk space and 9-track magnetic tape usage. Multiplexor hardware capability allows the transfer of data between a user's device and assigned core area at rates of 100,000 bytes/sec. Real-time histogram generation for a user can proceed at rates of 50,000 points/sec. The facility has been self-running (no computer operator) for five years with a mean time between failures of 10 []ays and an uptime of 157 hours/week. (auth)

  14. XML in an Adaptive Framework for Instrument Control

    Science.gov (United States)

    Ames, Troy J.

    2004-01-01

    NASA Goddard Space Flight Center is developing an extensible framework for instrument command and control, known as Instrument Remote Control (IRC), that combines the platform independent processing capabilities of Java with the power of the Extensible Markup Language (XML). A key aspect of the architecture is software that is driven by an instrument description, written using the Instrument Markup Language (IML). IML is an XML dialect used to describe interfaces to control and monitor the instrument, command sets and command formats, data streams, communication mechanisms, and data processing algorithms.

  15. Instrumentation and process control for fossil demonstration plants. Quarterly technical progress report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    LeSage, L.G.

    1977-07-01

    Work has been performed on updating the study of the state-of-the-art of instrumentation for Fossil Demonstration Plants (FDP), development of mass-flow and other on-line instruments for FDP, process control analysis for FDP, and organization of a symposium on instrumentation and control for FDP. A Solids/Gas Flow Test Facility (S/GFTF) under construction for instrument development, testing, evaluation, and calibration is described. The development work for several mass-flow and other on-line instruments is described: acoustic flowmeter, capacitive density flowmeter, neutron activation flowmeter and composition analysis system, gamma ray correlation flowmeter, optical flowmeter, and capacitive liquid interface level meter.

  16. Virtual instrumentation: a new approach for control and instrumentation - application in containment studies facility

    International Nuclear Information System (INIS)

    Gole, N.V.; Shanware, V.M.; Sebastian, A.; Subramaniam, K.

    2001-01-01

    PC based data-acquisition has emerged as a rapidly developing area particularly with respect to process instrumentation. Computer based data acquisition in process instrumentation combined with Supervisory Control and Data Acquisition (SCADA) software has introduced extensive possibilities with respect to formats for presentation of information. The concept of presenting data using any instrument format with the help of software tools to simulate the instrument on screen, needs to be understood, in order to be able to make use of its vast potential. The purpose of this paper is to present the significant features of the Virtual Instrumentation concept and discuss its application in the instrumentation and control system of containment studies facility (CSF). Factors involved in the development of the virtual instrumentation based I and C system for CSF are detailed and a functional overview of the system configuration is given. (author)

  17. Distributed Framework for Dynamic Telescope and Instrument Control

    Science.gov (United States)

    Ames, Troy J.; Case, Lynne

    2002-01-01

    Traditionally, instrument command and control systems have been developed specifically for a single instrument. Such solutions are frequently expensive and are inflexible to support the next instrument development effort. NASA Goddard Space Flight Center is developing an extensible framework, known as Instrument Remote Control (IRC) that applies to any kind of instrument that can be controlled by a computer. IRC combines the platform independent processing capabilities of Java with the power of the Extensible Markup Language (XML). A key aspect of the architecture is software that is driven by an instrument description, written using the Instrument Markup Language (IML). IML is an XML dialect used to describe graphical user interfaces to control and monitor the instrument, command sets and command formats, data streams, communication mechanisms, and data processing algorithms. The IRC framework provides the ability to communicate to components anywhere on a network using the JXTA protocol for dynamic discovery of distributed components. JXTA (see httD://www.jxta.org,) is a generalized protocol that allows any devices connected by a network to communicate in a peer-to-peer manner. IRC uses JXTA to advertise a device's IML and discover devices of interest on the network. Devices can join or leave the network and thus join or leave the instrument control environment of IRC. Currently, several astronomical instruments are working with the IRC development team to develop custom components for IRC to control their instruments. These instruments include: High resolution Airborne Wideband Camera (HAWC), a first light instrument for the Stratospheric Observatory for Infrared Astronomy (SOFIA); Submillimeter And Far Infrared Experiment (SAFIRE), a Principal Investigator instrument for SOFIA; and Fabry-Perot Interferometer Bolometer Research Experiment (FIBRE), a prototype of the SAFIRE instrument, used at the Caltech Submillimeter Observatory (CSO). Most recently, we have

  18. Reliability Estimation for Digital Instrument/Control System

    International Nuclear Information System (INIS)

    Yang, Yaguang; Sydnor, Russell

    2011-01-01

    Digital instrumentation and controls (DI and C) systems are widely adopted in various industries because of their flexibility and ability to implement various functions that can be used to automatically monitor, analyze, and control complicated systems. It is anticipated that the DI and C will replace the traditional analog instrumentation and controls (AI and C) systems in all future nuclear reactor designs. There is an increasing interest for reliability and risk analyses for safety critical DI and C systems in regulatory organizations, such as The United States Nuclear Regulatory Commission. Developing reliability models and reliability estimation methods for digital reactor control and protection systems will involve every part of the DI and C system, such as sensors, signal conditioning and processing components, transmission lines and digital communication systems, D/A and A/D converters, computer system, signal processing software, control and protection software, power supply system, and actuators. Some of these components are hardware, such as sensors and actuators, their failure mechanisms are well understood, and the traditional reliability model and estimation methods can be directly applied. But many of these components are firmware which has software embedded in the hardware, and software needs special consideration because its failure mechanism is unique, and the reliability estimation method for a software system will be different from the ones used for hardware systems. In this paper, we will propose a reliability estimation method for the entire DI and C system reliability using a recently developed software reliability estimation method and a traditional hardware reliability estimation method

  19. Reliability Estimation for Digital Instrument/Control System

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Yaguang; Sydnor, Russell [U.S. Nuclear Regulatory Commission, Washington, D.C. (United States)

    2011-08-15

    Digital instrumentation and controls (DI and C) systems are widely adopted in various industries because of their flexibility and ability to implement various functions that can be used to automatically monitor, analyze, and control complicated systems. It is anticipated that the DI and C will replace the traditional analog instrumentation and controls (AI and C) systems in all future nuclear reactor designs. There is an increasing interest for reliability and risk analyses for safety critical DI and C systems in regulatory organizations, such as The United States Nuclear Regulatory Commission. Developing reliability models and reliability estimation methods for digital reactor control and protection systems will involve every part of the DI and C system, such as sensors, signal conditioning and processing components, transmission lines and digital communication systems, D/A and A/D converters, computer system, signal processing software, control and protection software, power supply system, and actuators. Some of these components are hardware, such as sensors and actuators, their failure mechanisms are well understood, and the traditional reliability model and estimation methods can be directly applied. But many of these components are firmware which has software embedded in the hardware, and software needs special consideration because its failure mechanism is unique, and the reliability estimation method for a software system will be different from the ones used for hardware systems. In this paper, we will propose a reliability estimation method for the entire DI and C system reliability using a recently developed software reliability estimation method and a traditional hardware reliability estimation method.

  20. Control of Squeezed States

    OpenAIRE

    Bloch, Anthony M.; Rojo, Alberto G.

    2000-01-01

    In this paper we consider the classical and quantum control of squeezed states of harmonic oscillators. This provides a method for reducing noise below the quantum limit and provides an example of the control of under-actuated systems in the stochastic and quantum context. We consider also the interaction of a squeezed quantum oscillator with an external heat bath.

  1. Human factors survey of advanced instrumentation and controls

    International Nuclear Information System (INIS)

    Carter, R.J.

    1989-01-01

    A survey oriented towards identifying the human factors issues in regard to the use of advanced instrumentation and controls (I ampersand C) in the nuclear industry was conducted. A number of United States (US) and Canadian nuclear vendors and utilities were participants in the survey. Human factors items, subsumed under the categories of computer-generated displays (CGD), controls, organizational support, training, and related topics, were discussed. The survey found the industry to be concerned about the human factors issues related to the implementation of advanced I ampersand C. Fifteen potential human factors problems were identified. They include: the need for an advanced I ampersand C guideline equivalent to NUREG-0700; a role change in the control room from operator to supervisor; information overload; adequacy of existing training technology for advanced I ampersand C; and operator acceptance and trust. 11 refs., 1 tab

  2. Economic instruments and marine litter control

    NARCIS (Netherlands)

    Oosterhuis, F.H.; Papyrakis, E.; Boteler, B.

    2014-01-01

    This paper provides a comprehensive up-to-date review of the literature on the economic instruments that can reduce marine litter. We assess their cost of implementation, level of effectiveness as well as indirect environmental and socio-economic effects (externalities) that may arise as a result of

  3. Instrumentation

    International Nuclear Information System (INIS)

    Umminger, K.

    2008-01-01

    A proper measurement of the relevant single and two-phase flow parameters is the basis for the understanding of many complex thermal-hydraulic processes. Reliable instrumentation is therefore necessary for the interaction between analysis and experiment especially in the field of nuclear safety research where postulated accident scenarios have to be simulated in experimental facilities and predicted by complex computer code systems. The so-called conventional instrumentation for the measurement of e. g. pressures, temperatures, pressure differences and single phase flow velocities is still a solid basis for the investigation and interpretation of many phenomena and especially for the understanding of the overall system behavior. Measurement data from such instrumentation still serves in many cases as a database for thermal-hydraulic system codes. However some special instrumentation such as online concentration measurement for boric acid in the water phase or for non-condensibles in steam atmosphere as well as flow visualization techniques were further developed and successfully applied during the recent years. Concerning the modeling needs for advanced thermal-hydraulic codes, significant advances have been accomplished in the last few years in the local instrumentation technology for two-phase flow by the application of new sensor techniques, optical or beam methods and electronic technology. This paper will give insight into the current state of instrumentation technology for safety-related thermohydraulic experiments. Advantages and limitations of some measurement processes and systems will be indicated as well as trends and possibilities for further development. Aspects of instrumentation in operating reactors will also be mentioned.

  4. Using XML and Java Technologies for Astronomical Instrument Control

    Science.gov (United States)

    Ames, Troy; Case, Lynne; Powers, Edward I. (Technical Monitor)

    2001-01-01

    Traditionally, instrument command and control systems have been highly specialized, consisting mostly of custom code that is difficult to develop, maintain, and extend. Such solutions are initially very costly and are inflexible to subsequent engineering change requests, increasing software maintenance costs. Instrument description is too tightly coupled with details of implementation. NASA Goddard Space Flight Center, under the Instrument Remote Control (IRC) project, is developing a general and highly extensible framework that applies to any kind of instrument that can be controlled by a computer. The software architecture combines the platform independent processing capabilities of Java with the power of the Extensible Markup Language (XML), a human readable and machine understandable way to describe structured data. A key aspect of the object-oriented architecture is that the software is driven by an instrument description, written using the Instrument Markup Language (IML), a dialect of XML. IML is used to describe the command sets and command formats of the instrument, communication mechanisms, format of the data coming from the instrument, and characteristics of the graphical user interface to control and monitor the instrument. The IRC framework allows the users to define a data analysis pipeline which converts data coming out of the instrument. The data can be used in visualizations in order for the user to assess the data in real-time, if necessary. The data analysis pipeline algorithms can be supplied by the user in a variety of forms or programming languages. Although the current integration effort is targeted for the High-resolution Airborne Wideband Camera (HAWC) and the Submillimeter and Far Infrared Experiment (SAFIRE), first-light instruments of the Stratospheric Observatory for Infrared Astronomy (SOFIA), the framework is designed to be generic and extensible so that it can be applied to any instrument. Plans are underway to test the framework

  5. Plans for the CIT [Compact Ignition Tokamak] instrumentation and control system

    International Nuclear Information System (INIS)

    Preckshot, G.G.

    1987-01-01

    Extensive experience with previous fusion experiments (TFTR, MFTF-B and others) is driving the design of the Instrumentation and Control System (I and C) for the Compact Ignition Tokamak (CIT) to be built at Princeton. The new design will reuse much equipment from TFTR and will be subdivided into six major parts: machine control, machine data acquisition, plasma diagnostic instrument control and instrument data acquisition, the database, shot sequencing and safety interlocks. In a major departure from previous fusion experiment control systems, the CIT machine control system will be a commercial process control system. Since the machine control system will be purchased as a completely functional product, we will be able to concentrate development manpower in plasma diagnostic instrument control, data acquisition, data processing and analysis, and database systems. We will discuss the issues driving the design, give a design overview and state the requirements upon any prospective commercial process control system

  6. Applying improved instrumentation and computer control systems

    International Nuclear Information System (INIS)

    Bevilacqua, F.; Myers, J.E.

    1977-01-01

    In-core and out-of-core instrumentation systems for the Cherokee-I reactor are described. The reactor has 61m-core instrument assemblies. Continuous computer monitoring and processing of data from over 300 fixed detectors will be used to improve the manoeuvering of core power. The plant protection system is a standard package for the Combustion Engineering System 80, consisting of two independent systems, the reactor protection system and the engineering safety features activation system, both of which are designed to meet NRC, ANS and IEEE design criteria or standards. The plants protection system has its own computer which provides plant monitoring, alarming, logging and performance calculations. (U.K.)

  7. An automated instrument for controlled-potential coulometry: System documentation

    Energy Technology Data Exchange (ETDEWEB)

    Holland, M K; Cordaro, J V

    1988-06-01

    An automated controlled-potential coulometer has been developed at the Savannah River Plant for the determination of plutonium. Two such coulometers have been assembled, evaluated, and applied. The software is based upon the methodology used at the Savannah River Plant, however the system is applicable with minimal software modifications to any of the methodologies used throughout the nuclear industry. These state-of-the-art coulometers feature electrical calibration of the integration system, background current corrections, and control-potential adjustment capabilities. Measurement precision within 0.1% has been demonstrated. The systems have also been successfully applied to the determination of pure neptunium solutions. The design and documentation of the automated instrument are described herein. Each individual module's operation, wiring layout, and alignment are described. Interconnection of the modules and system calibration are discussed. A complete set of system prints and a list of associated parts are included. 9 refs., 10 figs., 6 tabs.

  8. The Aspects Of Inventory Controlling Instruments Implementation In The System Of Retail Chains Finance Management

    OpenAIRE

    Nataliya Buratchuk

    2014-01-01

    The article deals with issues of implementation of inventory controlling instruments in the system of retail chains finance management. The author suggests expanded classification of methods and instruments of inventory controlling distinguishing 3 groups of specific instruments: logistic controlling instruments, expenditures and supply chains controlling instruments and inventory special controlling mechanisms. Based on investigation of controlling methods and instruments, the approximate li...

  9. Performance and quality control of nuclear medicine instrumentation

    International Nuclear Information System (INIS)

    Paras, P.

    1981-01-01

    The status and the recent developments of nuclear medicine instrumentation performance, with an emphasis on gamma-camera performance, are discussed as the basis for quality control. New phantoms and techniques for the measurement of gamma-camera performance parameters are introduced and their usefulness for quality control is discussed. Tests and procedures for dose calibrator quality control are included. Also, the principles of quality control, tests, equipment and procedures for each type of instrument are reviewed, and minimum requirements for an effective quality assurance programme for nuclear medicine instrumentation are suggested. (author)

  10. The State Financial Policy as Instrument of Economic Growth

    Directory of Open Access Journals (Sweden)

    Mostitskaya Natalya А.

    2017-12-01

    Full Text Available The article is aimed at disclosing the essence and defining the role of the State financial policy as instrument of economic growth in the conditions of economic transformation. The main functions of the country’s financial policy were analyzed. The necessity of formation of institutional and methodological bases of the State financial mechanism with the purpose of strengthening of efficiency of structural changes of economy and social sphere has been substantiated. Directions of formation and implementation of the State financial policy on maintenance of socio-economic development of the country have been proposed.

  11. 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

  12. EPROM-based LSI-11 for distributed instrumentation control

    International Nuclear Information System (INIS)

    Hunt, D.N.

    1981-01-01

    The LLNL Nuclear Chemistry Counting Facility (NCCF) is being converted to a modern production facility. A computer network has been designed and built to implement this conversion. The outermost node of the computer network is a dedicated EPROM-based controller. The controller handles the details of driving the attached nuclear instrumentation, providing a standard interface to the remainder of the network. This paper addresses the design and the implementation of the dedicated instrumentation controller

  13. Legal control scenario applied to embedded software in measuring instruments

    International Nuclear Information System (INIS)

    Castro, C.G. de; Brandao, P.C.; Leitao, F.O.

    2013-01-01

    This paper presents a scenario of legal control of software in measuring instruments. Such control is hampered by intrinsic problems related to software analysis and verification. To circumvent these difficulties, several projects are being developed to attack different stages of legal control, such as the model type approval, periodic verifications and metrological expertise. The proposals that will arise from these projects will be discussed among the parts and may be incorporated into the measuring instruments. (author)

  14. An instrumentation for control and measurement of activated mineral samples

    International Nuclear Information System (INIS)

    Skaarup, P.

    1976-01-01

    A description is given of an instrumentation for control of a pneumatic tube system used to transport mineral samples for activation in a reactor and from there to a detector arrangement. A possible content of uranium in the samples can be seen from the radiation measured. The instrumentation includes a PDP-11 computer and a CAMAC crate

  15. State Controled Avantgarde?

    DEFF Research Database (Denmark)

    Kreutzfeldt, Jacob

    2016-01-01

    State controlled radio developed in the Nordic countries by the middle of the 1920es. Danish Radio was established for a trial period in April 1925, and was permanently founded in April 1926. Swedish radio was founded in 1925 and Norwegian radio in 1933. The new and unquestionably powerful medium...... to the program sheet from Danish Broadcasting Corporation (DBC) the program included transmission of music from the Radio Orchestra, sound film and transmissions from theatres and dance restaurants in Copenhage...

  16. International Working Group on Nuclear Power Plant Control and Instrumentation: Recent activities and future prospects

    International Nuclear Information System (INIS)

    Kossilov, A.

    1992-01-01

    The IWG-NPPCI working group exists to consider developments, disseminate and exchange experience in all aspects of instrumentation, control and information technology relevant to the safety and economics of NPP design and operation. The main topics dealt with are: nuclear instrumentation, control systems, protection systems, early failure detection and diagnosis, use of computer technology in NPP operation, instrumentation for accidental situation, operator support systems, man-machine interface. The main objectives of the IWG-NPPCI are: to assist the IAEA to provide the Member States with information and recommendations on technical aspects of the NPP control and instrumentation with the aim to assure reliable functions; to promote and exchange of information on national programs, new developments and experience from operating NPPs, and to stimulate the coordination of research on NPP control and instrumentation

  17. International Working Group on Nuclear Power Plant Control and Instrumentation: Recent activities and future prospects

    Energy Technology Data Exchange (ETDEWEB)

    Kossilov, A [International Atomic Energy Agency, Vienna (Austria)

    1992-07-01

    The IWG-NPPCI working group exists to consider developments, disseminate and exchange experience in all aspects of instrumentation, control and information technology relevant to the safety and economics of NPP design and operation. The main topics dealt with are: nuclear instrumentation, control systems, protection systems, early failure detection and diagnosis, use of computer technology in NPP operation, instrumentation for accidental situation, operator support systems, man-machine interface. The main objectives of the IWG-NPPCI are: to assist the IAEA to provide the Member States with information and recommendations on technical aspects of the NPP control and instrumentation with the aim to assure reliable functions; to promote and exchange of information on national programs, new developments and experience from operating NPPs, and to stimulate the coordination of research on NPP control and instrumentation.

  18. Emergency Diesel: Safety-related instrumentation and control with programmable logic controllers

    International Nuclear Information System (INIS)

    Breidenich, G.; Luedtke, M.

    2004-01-01

    This report presents a new concept for the design of emergency diesel equipment protection circuits as a part of the safety related instrumentation in the nuclear power plant Biblis, units A and B. The concept was implemented with state of the art SIMATIC S7/316 programmable logic controllers (PLCs) and can be adapted to any system with high availability requirements (e.g. power plant turbines, aircraft engines, mining pumps etc). (orig.)

  19. Nuclear Instrumentation and Control Cyber Testbed Considerations – Lessons Learned

    Energy Technology Data Exchange (ETDEWEB)

    Jonathan Gray; Robert Anderson; Julio G. Rodriguez; Cheol-Kwon Lee

    2014-08-01

    Abstract: Identifying and understanding digital instrumentation and control (I&C) cyber vulnerabilities within nuclear power plants and other nuclear facilities, is critical if nation states desire to operate nuclear facilities safely, reliably, and securely. In order to demonstrate objective evidence that cyber vulnerabilities have been adequately identified and mitigated, a testbed representing a facility’s critical nuclear equipment must be replicated. Idaho National Laboratory (INL) has built and operated similar testbeds for common critical infrastructure I&C for over ten years. This experience developing, operating, and maintaining an I&C testbed in support of research identifying cyber vulnerabilities has led the Korean Atomic Energy Research Institute of the Republic of Korea to solicit the experiences of INL to help mitigate problems early in the design, development, operation, and maintenance of a similar testbed. The following information will discuss I&C testbed lessons learned and the impact of these experiences to KAERI.

  20. Nuclear Instrumentation and Control Cyber Testbed Considerations - Lessons Learned

    International Nuclear Information System (INIS)

    Jonathan, Peter Grey; Robert, S Anderson; Julio, G Rodriguez; Lee, Cheol Kwon

    2014-01-01

    Identifying and understanding digital instrumentation and control (I and C) cyber vulnerabilities within nuclear power plants and other nuclear facilities is critical if nation states desire to operate nuclear facilities safely, reliably, and securely. To demonstrate objective evidence that cyber vulnerabilities have been adequately identified and mitigated, a test bed representing a facility's critical nuclear equipment must be replicated. Idaho National Laboratory (INL) has built and operated similar test beds for common critical infrastructure I and C for over 10 years. This experience developing, operating, and maintaining an I and C test bed in support of research identifying cyber vulnerabilities has led the Korean Atomic Energy Research Institute of the Republic of Korea to solicit the experiences of INL to help mitigate problems early in the design, development, operation, and maintenance of a similar test bed. The following information will discuss I and C test bed lessons learned and the impact of these experiences to KAERI

  1. Volcano-Monitoring Instrumentation in the United States, 2008

    Science.gov (United States)

    Guffanti, Marianne; Diefenbach, Angela K.; Ewert, John W.; Ramsey, David W.; Cervelli, Peter F.; Schilling, Steven P.

    2010-01-01

    The United States is one of the most volcanically active countries in the world. According to the global volcanism database of the Smithsonian Institution, the United States (including its Commonwealth of the Northern Mariana Islands) is home to about 170 volcanoes that are in an eruptive phase, have erupted in historical time, or have not erupted recently but are young enough (eruptions within the past 10,000 years) to be capable of reawakening. From 1980 through 2008, 30 of these volcanoes erupted, several repeatedly. Volcano monitoring in the United States is carried out by the U.S. Geological Survey (USGS) Volcano Hazards Program, which operates a system of five volcano observatories-Alaska Volcano Observatory (AVO), Cascades Volcano Observatory (CVO), Hawaiian Volcano Observatory (HVO), Long Valley Observatory (LVO), and Yellowstone Volcano Observatory (YVO). The observatories issue public alerts about conditions and hazards at U.S. volcanoes in support of the USGS mandate under P.L. 93-288 (Stafford Act) to provide timely warnings of potential volcanic disasters to the affected populace and civil authorities. To make efficient use of the Nation's scientific resources, the volcano observatories operate in partnership with universities and other governmental agencies through various formal agreements. The Consortium of U.S. Volcano Observatories (CUSVO) was established in 2001 to promote scientific cooperation among the Federal, academic, and State agencies involved in observatory operations. Other groups also contribute to volcano monitoring by sponsoring long-term installation of geophysical instruments at some volcanoes for specific research projects. This report describes a database of information about permanently installed ground-based instruments used by the U.S. volcano observatories to monitor volcanic activity (unrest and eruptions). The purposes of this Volcano-Monitoring Instrumentation Database (VMID) are to (1) document the Nation's existing

  2. Using XML and Java for Astronomical Instrumentation Control

    Science.gov (United States)

    Ames, Troy; Koons, Lisa; Sall, Ken; Warsaw, Craig

    2000-01-01

    Traditionally, instrument command and control systems have been highly specialized, consisting mostly of custom code that is difficult to develop, maintain, and extend. Such solutions are initially very costly and are inflexible to subsequent engineering change requests, increasing software maintenance costs. Instrument description is too tightly coupled with details of implementation. NASA Goddard Space Flight Center is developing a general and highly extensible framework that applies to any kind of instrument that can be controlled by a computer. The software architecture combines the platform independent processing capabilities of Java with the power of the Extensible Markup Language (XML), a human readable and machine understandable way to describe structured data. A key aspect of the object-oriented architecture is software that is driven by an instrument description, written using the Instrument Markup Language (IML). ]ML is used to describe graphical user interfaces to control and monitor the instrument, command sets and command formats, data streams, and communication mechanisms. Although the current effort is targeted for the High-resolution Airborne Wideband Camera, a first-light instrument of the Stratospheric Observatory for Infrared Astronomy, the framework is designed to be generic and extensible so that it can be applied to any instrument.

  3. 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)

  4. Modernization of the Ukrainian NPP instrumentation and control systems

    International Nuclear Information System (INIS)

    Yastrebenetsky, M.

    1998-01-01

    Modernization of many instrumentation and control systems for all type of reactors is under way now in Ukraine. Main principles of modernization, standards that are used for modernization are described in the report. (author)

  5. Instrumentation and control for fossil-energy processes

    Energy Technology Data Exchange (ETDEWEB)

    1982-09-01

    The 1982 symposium on instrumentation and control for fossil energy processes was held June 7 through 9, 1982, at Adam's Mark Hotel, Houston, Texas. It was sponsored by the US Department of Energy, Office of Fossil Energy; Argonne National Laboratory; and the Society for Control and Instrumentation of Energy Processes. Fifty-two papers have been entered individually into EDB and ERA; eleven papers had been entered previously from other sources. (LTN)

  6. Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Bruce Hallbert

    2012-09-01

    Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.

  7. Environmental Licensing: an Instrument of Command and Control by Exception?

    OpenAIRE

    Sleman Chams, Juliette; Gestión Ambiental de la Corporación Autónoma Regional del Atlántico-CRA, autoridad ambiental del Departamento del Atlántico,; Velásquez Muñoz, Carlos Javier; Universidad del Norte (Barranquilla)

    2016-01-01

    This article analyzes the situation of the most important instrument of command and control existing in the Colombian environmental legislation: the environmental license. Since its first formal regulation, on behalf of Decree 1753 of August 3, 1994, has received several modifications which, apparently, have made, in spite of its importance, in an instrument of command and control by exception. The article revises on the scope of each of the modifications and the justifications put forward by...

  8. Service-oriented architecture for the ARGOS instrument control software

    Science.gov (United States)

    Borelli, J.; Barl, L.; Gässler, W.; Kulas, M.; Rabien, Sebastian

    2012-09-01

    The Advanced Rayleigh Guided ground layer Adaptive optic System, ARGOS, equips the Large Binocular Telescope (LBT) with a constellation of six rayleigh laser guide stars. By correcting atmospheric turbulence near the ground, the system is designed to increase the image quality of the multi-object spectrograph LUCIFER approximately by a factor of 3 over a field of 4 arc minute diameter. The control software has the critical task of orchestrating several devices, instruments, and high level services, including the already existing adaptive optic system and the telescope control software. All these components are widely distributed over the telescope, adding more complexity to the system design. The approach used by the ARGOS engineers is to write loosely coupled and distributed services under the control of different ownership systems, providing a uniform mechanism to offer, discover, interact and use these distributed capabilities. The control system counts with several finite state machines, vibration and flexure compensation loops, and safety mechanism, such as interlocks, aircraft, and satellite avoidance systems.

  9. Concluding from operating experience to instrumentation and control systems

    International Nuclear Information System (INIS)

    Pleger, H.; Heinsohn, H.

    1997-01-01

    Where conclusions are drawn from operating experience to instrumentation and control systems, two general statements should be made. First: There have been braekdowns, there have also been deficiencies, but in principle operating experience with the instrumentation and control systems of German nuclear power plants has been good. With respect to the debates about the use of modern digital instrumentation and control systems it is safe to say, secondly, that the instrumentation and control systems currently in use are working reliably. Hence, there is no need at present to replace existing systems for reasons of technical safety. However, that time will come. It is a good thing, therefore, that the use of modern digital instrumentation and control systems is to begin in the field of limiting devices. The operating experience which will thus be accumulated will benefit digital instrumentation and control systems in their qualification process for more demanding applications. This makes proper logging of operating experience an important function, even if it cannot be transferred in every respect. All parties involved therefore should see to it that this operating experience is collected in accordance with criteria agreed upon so as to prevent unwanted surprises later on. (orig.) [de

  10. Instrumental color control for metallic coatings

    Science.gov (United States)

    Chou, W.; Han, Bing; Cui, Guihua; Rigg, Bryan; Luo, Ming R.

    2002-06-01

    This paper describes work investigating a suitable color quality control method for metallic coatings. A set of psychological experiments was carried out based upon 50 pairs of samples. The results were used to test the performance of various color difference formulae. Different techniques were developed by optimising the weights and/or the lightness parametric factors of colour differences calculated from the four measuring angles. The results show that the new techniques give a significant improvement compared to conventional techniques.

  11. Technical evaluation of available state of Nevada survey instruments

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-02-01

    Argonne National Laboratory (ANL) is reviewing the survey research studies completed by Mountain West Research (1987-1989) for the state of Nevada`s Nuclear Waste Project Office. In this research, 14 survey instruments were used to seek data on whether perceptions of risk could be associated with the possible siting of a high-level radioactive waste repository in Nevada and could be a dominant source of potential, significant, adverse economic impacts. This report presents results from phase 1 of the review, in which ANL contracted with the National Opinion Research Center (NORC) at the University of Chicago to evaluate the technical merits of the nine survey instruments that ANL had been able to acquire. The scope of NORC`s work was limited to rating the questions and stating their strengths and weaknesses. NORC concluded that the surveys could provide valuable data about risk perceptions and potential behavioral responses. NORC identified a few minor problems with a number of questions and the calculated response rates but claimed these problems would probably not have any major biasing effect. The NORC evaluation would have been more complete if the terms used in the questionnaires had been defined, all survey instruments had been acquired, and all data had been made available to the public.

  12. Technical evaluation of available state of Nevada survey instruments

    International Nuclear Information System (INIS)

    1993-02-01

    Argonne National Laboratory (ANL) is reviewing the survey research studies completed by Mountain West Research (1987-1989) for the state of Nevada's Nuclear Waste Project Office. In this research, 14 survey instruments were used to seek data on whether perceptions of risk could be associated with the possible siting of a high-level radioactive waste repository in Nevada and could be a dominant source of potential, significant, adverse economic impacts. This report presents results from phase 1 of the review, in which ANL contracted with the National Opinion Research Center (NORC) at the University of Chicago to evaluate the technical merits of the nine survey instruments that ANL had been able to acquire. The scope of NORC's work was limited to rating the questions and stating their strengths and weaknesses. NORC concluded that the surveys could provide valuable data about risk perceptions and potential behavioral responses. NORC identified a few minor problems with a number of questions and the calculated response rates but claimed these problems would probably not have any major biasing effect. The NORC evaluation would have been more complete if the terms used in the questionnaires had been defined, all survey instruments had been acquired, and all data had been made available to the public

  13. AFRRI's conversion to a microprocessor-based reactor instrumentation and control system

    International Nuclear Information System (INIS)

    Moore, Mark L.; Hodgdon, Kenneth M.

    1986-01-01

    The Armed Forces Radiobiology Research Institute (AFRRI) is procuring a state-of- the-art microprocessor-based instrumentation and control system to operate AFRRI's 1 MW (steady-state), 3000 MW (pulse) TRIGA Mark-F reactor. This system will replace the current control console while improving or maintaining the existing operational capabilities and safety characteristics. The new unit will have a 15-year design life using state-of-the-art components

  14. ADAA: new software for intelligent instrument control

    International Nuclear Information System (INIS)

    Butman, M.; Wannberg, A.; Mellergaard, A.; Zetterstroem, P.; McGreevy, R.L.

    2004-01-01

    Automated data acquisition and analysis (ADAA) is a new platform for automation of experiments, including data reduction, analysis and feedback. The objective of ADAA is to develop software that enables scientific control of the progress of an experiment, e.g. monitoring in terms of analysed data as opposed to measured data, one obvious aim being to maximize the scientific output from a given period of beam time. Basic design considerations will be outlined and discussed in the context of several types of experiments

  15. Instrumentation and control of turbine, generator and associated systems

    International Nuclear Information System (INIS)

    Vogtland, U.

    1982-01-01

    The purpose of this presentation is to give some information on Instrumentation and Control (I and C) for turbine-generators, in this case for nuclear application. The I and C scope of supply for such a turbine-generator can be divided as follows: - Closed-loop controls - Turbine stress control systems - Supervisory instrumentation - Protection systems - Open-loop controls. The main systems used for nuclear application are presented by means of examples taken from these a.m. categories. (orig./RW)

  16. TFTR movable limiter instrumentation and controls

    International Nuclear Information System (INIS)

    Frankenberg, J.; Collins, D.; Kaufmann, D.; Mamoun, A.

    1983-01-01

    The TFTR movable limiter is a single poloidal limiter located within one 18 /SUP o/ segment of the vacuum vessel. It consists of three (3) interconnected inconel backing plates covered with titanium carbide coated graphite tiles. The backing plates are positioned by three independent screw drive actuators. Cooling water is fed through the horizontal port cover to tubes brazed onto the backs of the backing plates. Thermocouples monitor the limiter temperature. (1) and more fully described in refs. (1) and (2). The positioning actuators are driven by independently controlled DC servo motors, controlled either locally or from CICADA. Drive motor shaft position is monitored by chain driven encoders and potentiometers. Limiter blade position can be varied to suit any plasma within the operating range. CICADA is programmed to keep the limiter stroke within safe operating limits. A microprocessor duplicates the CICADA protective function allowing limiter operation without CICADA. The potentiometer signal is sent to an analog computer, which safeguards the limiter against failure of the encoders or the micro-processor. Cooling water flows through the limiter in 3 separate paths, one for each blade. The flow rate and temperature rise through each loop are measured accurately to allow CICADA to calculate the heat into each blade. The water system is also interlocked and alarmed to prevent dumping of water into the vacuum vessel

  17. The proposed Diagnostic Instrumentation and Analysis Laboratory, Mississippi State University

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-11-01

    The Department of Energy (DOE) proposes to authorize Mississippi State University (MSU) to proceed with the detailed design, construction and equipping of the proposed Diagnostic Instrumentation and Analysis Laboratory (DIAL). DOE grant funds are available to the University for the limited purpose of performing preliminary studies, including analysis necessary to conduct this environmental assessment. The proposed facility would be located in the Mississippi Research and Technology Park, adjacent to the Mississippi Agriculture and Forestry Experiment Station campus in Starkville, Mississippi. Total project cost is estimated at $7,953,600. This proposed laboratory would be designed to conduct research into combustion devices related to waste management and environmental restoration that is of importance to industry and government. The proposed facility`s role would be to develop diagnostic instrumentation capabilities in the area of combustion and related processes.

  18. Cardiac output measurement instruments controlled by microprocessors

    International Nuclear Information System (INIS)

    Spector, M.; Barritault, L.; Boeri, C.; Fauchet, M.; Gambini, D.; Vernejoul, P. de

    The nuclear medicine and biophysics laboratory of the Necker-Enfants malades University Hospital Centre has built a microprocessor controlled Cardiac flowmetre. The principle of the cardiac output measurement from a radiocardiogram is well established. After injection of a radioactive indicator upstream from the heart cavities the dilution curve is obtained by the use of a gamma-ray precordial detector. This curve normally displays two peaks due to passage of the indicator into the right and left sides of the heart respectively. The output is then obtained from the stewart Hamilton principle once recirculation is eliminated. The graphic method used for the calculation however is long and tedious. The decreasing fraction of the dilution curve is projected in logarithmic space in order to eliminate recirculation by determining the mean straight line from which the decreasing exponential is obtained. The principle of the use of microprocessors is explained (electronics, logics) [fr

  19. Implementation of programmable logic controller for proposed new instrumentation and control system of RTP

    International Nuclear Information System (INIS)

    Mohd Khairulezwan Abdul Manan; Mohd Idris Taib; Mohd Dzul Aiman Aslan

    2010-01-01

    Reactor Monitoring System is one of very important part of Reactor Instrumentation and Control system. Current monitoring system is using analog system whereby all circuits are discrete circuit and all displays and indicators are not digitalized. The proposed new system will use using a Commercial Off-The-Shelf, state of the art, Supervisory Control and Data Acquisition system such as Programmable Logic Controller as well as Computer System. The implementations of Programmable Logic Controller are used for Data Acquisition System and as a sub-system for Computer System where all the activities involved are stored for operation record and report as well as use for research purposes. Programmable Logic Controller receives galvanised or optically isolated signal from Reactor Protection System. Programmable Logic Controller also receives signal from other parameters as a digital and analog input related to reactor system. (author)

  20. Acceptance for Beneficial Use Pumping Instrumentation and Control Skid N

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This is a final Acceptance for Beneficial Use (ABU) for Pumping and Instrumentation Control (PIC) skid ''N''. PIC skid ''N'' is ready for pumping tank U-109. All the testing and documentation has been completed as required on the AE3U checklist. This AE3U covers only the readiness of the PIC skid ''N''. Other U-farm preparations including dilution tank fabrication, portable exhauster readiness, leak detection, valve pit preparation, and the Operation Control Station readiness are not part of this ABU. PIC skid ''N'' is a new skid fabricated and tested at Site Fabrication Services. The skid controls the jet pump and monitors various instruments associated with the pumping operation. This monitoring includes leak detection along the waste transfer route and flammable gases in the pump pit. This Acceptance for Beneficial Use documents that Pumping Instrumentation and Control (PIC) skid ''N'' is ready for field use. This document does not cover the field installation or operational testing

  1. Design type testing for digital instrumentation and control systems

    International Nuclear Information System (INIS)

    Bastl, W.; Mohns, G.

    1997-01-01

    The design type qualification of digital safety instrumentation and control is outlined. Experience shows that the concepts discussed, derived from codes, guidelines and standards, achieve useful results. It has likewise become clear that the systematics of design type qualification of the hardware components is also applicable to the software components. Design type qualification of the software, a premiere, could be performed unexpectedly smoothly. The hardware design type qualification proved that the hardware as a substrate of functionality and reliability is an issue that demands full attention, as compared to conventional systems. Another insight is that design qualification of digital instrumentation and control systems must include plant-independent systems tests. Digital instrumentation and control systems simply work very differently from conventional control systems, so that this testing modality is inevitable. (Orig./CB) [de

  2. System 80+ instrumentation and controls - certification of a reliable design

    International Nuclear Information System (INIS)

    Matzie, R.A.; Scarola, K.; Turk, R.S.

    1993-01-01

    ABB Combustion Engineering's (ABB) System 80+ advanced light water plant design includes a modern, fully digitized instrumentation and controls complex, Nuplex 80+. This complex incorporates an evolutionary advanced control room, replacing conventional analog instruments with more capable computer driven components. As a result, Nuplex 80+ results in significant improvements in operator information handling and control to enhance plant safety and availability. The design implements features which the U.S. NRC has determined to be acceptable for addressing the potential for common mode failure in software implemented for protective functions. (author)

  3. 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.

  4. 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)

  5. Instrumentation and control strategies for an integral pressurized water reactor

    Directory of Open Access Journals (Sweden)

    Belle R. Upadhyaya

    2015-03-01

    Full Text Available Several vendors have recently been actively pursuing the development of integral pressurized water reactors (iPWRs that range in power levels from small to large reactors. Integral reactors have the features of minimum vessel penetrations, passive heat removal after reactor shutdown, and modular construction that allow fast plant integration and a secure fuel cycle. The features of an integral reactor limit the options for placing control and safety system instruments. The development of instrumentation and control (I&C strategies for a large 1,000 MWe iPWR is described. Reactor system modeling—which includes reactor core dynamics, primary heat exchanger, and the steam flashing drum—is an important part of I&C development and validation, and thereby consolidates the overall implementation for a large iPWR. The results of simulation models, control development, and instrumentation features illustrate the systematic approach that is applicable to integral light water reactors.

  6. New technology for BWR power plant control and instrumentation

    International Nuclear Information System (INIS)

    Takano, Yoshiyuki; Nakamura, Makoto; Murata, Fumio.

    1992-01-01

    Nuclear power plants are facing strong demands for higher reliability and cost-performance in their control and instrumentation systems. To meet these needs, Hitachi is developing advanced control and instrumentation technology by rationalizing the conventional technology in that field. The rationalization is done through the utilization of reliable digital technology and optical transmission technology, and others, which are now commonly used in computer applications. The goal of the development work is to ensure safe, stable operation of the plant facilities and to secure harmony between man and machine. To alleviate the burdens of the operators, the latest electronic devices are being employed to create an advanced man-machine interface, and to promote automatic operation of the plant based upon the automatic operation of individual systems. In addition, the control and instrumentation system, including the safety system, incorporates more and more digital components in order to further enhance the reliability and maintainability of the plant. (author)

  7. CAMAC-controlled calibration system for nuclear reactor instruments

    International Nuclear Information System (INIS)

    McDowell, W.P.; Cornella, R.J.

    1977-01-01

    The hardware and the software which have been developed to implement a nuclear instrument calibration system for the Argonne National Laboratory ZPR-VI and ZPR-IX reactor complex are described. The system is implemented using an SEL-840 computer with its associated CAMAC crates and a hardware interface to generate input parameters and measure the required outputs on the instrument under test. Both linear and logarithmic instruments can be calibrated by the system and output parameters can be measured at various automatically selected values of ac line voltage. A complete report on each instrument is printed as a result of the calibration and out-of-tolerance readings are flagged. Operator interface is provided by a CAMAC-controlled Hazeltine terminal. The terminal display leads the operator through the complete calibration procedure. This computer-controlled system is a significant improvement over previously used methods of calibrating nuclear instruments since it reduces reactor downtime and allows rapid detection of long-term changes in instrument calibration

  8. Criminal sanctions for legal enties: An instrument of crime control

    Directory of Open Access Journals (Sweden)

    Jovašević Dragan

    2016-01-01

    's own conduct embodied either in the commission of a criminal offence or in the omission to act. Therefore, contemporary criminal laws have determined special types of criminal sanctions, such as: punishment, security measures, conditional (suspended sentence and confiscation of material gain obtained by comitting the criminal offence, as well as the instruments, proceedings and conditions under which they may be imposed. Within the framework of the forthcoming reform of the entire penal legislation in the Republic of Serbia, the Serbian legislator may use the legal solutions envisaged in the analyzed documents and criminal legislations as a solid model for implementing the international standards in the field of criminal liability of legal entities. Hence, this paper discusses the particularities governing the application of criminal sanctions for legal entities in the Republic of Serbia, particularly as an instrument of crime control.

  9. Realizing Controllable Quantum States

    Science.gov (United States)

    Takayanagi, Hideaki; Nitta, Junsaku

    -- 4. Mesoscopic superconductivity with unconventional superconductor or ferromagnet. Ultraefficient microrefrigerators realized with ferromagnet-superconductor junctions / F. Giazotto et al. Anomalous charge transport in triplet superconductor junctions by the synergy effect of the proximity effect and the mid gap Andreev resonant states / Y. Tanaka and S. Kashiwaya. Paramagnetic and glass states in superconductive YBa[symbol]Cu[symbol]O[symbol] ceramics of sub-micron scale grains / H. Deguchi et al. Quantum properties of single-domain triplet superconductors / A. M. Gulian and K. S. Wood. A numerical study of Josephson current in p wave superconducting junctions / Y. Asano et al. Tilted bi-crystal sapphire substrates improve properties of grain boundary YBa[symbol]Cu[symbol]O[symbol] junctions and extend their Josephson response to THZ frequencies / E. Stepantsov et al. Circuit theory analysis of AB-plane tunnel junctions of unconventional superconductor Bi[symbol]Sr[symbol]Ca[symbol]Cu[symbol]O[symbol] / I. Shigeta et al. Transport properties of normal metal/anisotropic superconductor junctions in the eutectic system Sr[symbol]RuO[symbol]Ru / M. Kawamura et al. Macroscopic quantum tunneling in d-wave superconductor Josephson / S. Kawabata et al. Quasiparticle states of high-T[symbol] oxides observed by a Zeeman magnetic field response / S. Kashiwaya et al. Experimentally realizable devices for controlling the motion of magnetic flux quanta in anisotropic superconductors: vortex lenses, vortex diodes and vortex pumps / S. Savel'ev and F. Nori. Stability of vortex-antivortex "molecules" in mesoscopic superconducting triangles / V. R. Misko et al. Superconducting network with magnetic decoration - Hofstadter butterfly in spatially modulated magnetic field / Y. Iye et al. Observation of paramagnetic supercurrent in mesoscopic superconducting rings and disks using multiple-small-tunnel-junction method / A. Kanda et al. Guidance of vortices in high

  10. NPP Temelin instrumentation and control system upgrade and verification

    International Nuclear Information System (INIS)

    Ubra, O.; Petrlik, J.

    1998-01-01

    Two units of Ver 1000 type of the Czech nuclear power plant Temelin, which are under construction are being upgraded with the latest instrumentation and control system delivered by WEC. To confirm that the functional design of the new Reactor Control and Limitation System, Turbine Control System and Plant Control System are in compliance with the Czech customer requirements and that these requirements are compatible with NPP Temelin upgraded technology, the verification of the control systems has been performed. The method of transient analysis has been applied. Some details of the NPP Temelin Reactor Control and Limitation System verification are presented.(author)

  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. Safety regulations concerning instrumentation and control systems for research reactors

    International Nuclear Information System (INIS)

    El-Shanshoury, A.I.

    2009-01-01

    A brief study on the safety and reliability issues related to instrumentation and control systems in nuclear reactor plants is performed. In response, technical and strategic issues are used to accomplish instrumentation and control systems safety. For technical issues there are ; systems aspects of digital I and C technology, software quality assurance, common-mode software, failure potential, safety and reliability assessment methods, and human factors and human machine interfaces. The strategic issues are the case-by-case licensing process and the adequacy of the technical infrastructure. The purpose of this work was to review the reliability of the safety systems related to these technical issues for research reactors

  13. Conceptual design for the NSTX Central Instrumentation and Control System

    International Nuclear Information System (INIS)

    Bashore, D.; Oliaro, G.; Roney, P.; Sichta, P.; Tindall, K.

    1997-01-01

    The design and construction phase for the National Spherical Torus Experiment (NSTX) is under way at the Princeton Plasma Physics Laboratory (PPPL). Operation is scheduled to begin on April 30, 1999. This paper describes the conceptual design for the NSTX Central Instrumentation and Control (I and C) System. Major elements of the Central I and C System include the Process Control System, Plasma Control System, Network System, Data Acquisition System, and Synchronization System to support the NSTX experimental device

  14. Ageing of instrumentation and control cables in NPPs

    International Nuclear Information System (INIS)

    Santhosh; Ghosh, A.K.; Fernandes, B.G.

    2011-01-01

    Cables are vital components of instrumentation and control (I and C) systems in nuclear power plants (NPPs). The polymer materials used for insulation and jacket materials for electric cables are susceptible to ageing and degradation mechanisms caused by exposure to many of the stressors encountered in NPP service conditions. Ageing of components in NPP is an important concern since the degradation caused by ageing can impact the performance of susceptible equipment. This is of particular concern for safety-related equipment since the failure due to ageing can compromise the continued safe operation of the plant. The state-of-the art for incorporating cable ageing effects into probabilistic safety assessment (PSA) is still evolving and in the reliability assessment of NPP systems, the ageing effect of electrical cable is generally not considered and also, there is no standard method exists for incorporating such ageing effects into the system reliability. Therefore, identification and quantification of ageing of electrical cables is very much essential for an accurate prediction of system reliability for PSA applications. The objective of this study is to develop a methodology to assess the susceptibility of polymeric cable insulation to various ageing mechanisms; and the state of the insulation at any chosen time in order to evaluate the remaining life-time of operating cables in NPPs. This paper presents the state-of-the-art tools and techniques for insulation condition assessment, insulation life prediction methodologies, equipment qualification guidelines, and ageing management programs relating to I and C cables in NPPs. An approach to calculate the insulation resistance subjecting to different stressors has also been presented in this paper. (author)

  15. Quality control procedures applied to nuclear instruments. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2008-11-01

    Quality Control (QC), test procedures for Nuclear Instrumentation are important for assurance of proper and safe operation of the instruments, especially with regard to equipment related to radiological safety, human health and national safety. Correct measurements of radiation parameters must be ensured, i.e., accurate measurement of the number of radioactive events, counting times and in some cases accurate measurements of the radiation energy and occurring time of the nuclear events. There are several kinds of testing on nuclear instruments, for example, type-testing done by suppliers, acceptance testing made by the end users, Quality Control tests after repair and Quality Assurance/Quality Controls tests made by end-users. All of these tests are based in many cases on practical guidelines or on the experience of the own specialist, the available standards on this topic also need to be adapted to specific instruments. The IAEA has provided nuclear instruments and supported the operational maintenance efforts of the Member States. Although Nuclear Instrumentation is continuously upgraded, some older or aged instruments are still in use and in good working condition. Some of these instruments may not, however, meet modern requirements for the end-user therefore, Member States, mostly those with emerging economies, modernize/refurbish such instruments to meet the end-user demands. As a result, new instrumentation which is not commercially available, or modernized/refurbished instruments, need to be tested or verified with QC procedures to meet national or international certification requirements. A technical meeting on QC procedures applied to nuclear instruments was organized in Vienna from 23 to 24 August 2007. Existing and required QC test procedures necessary for the verification of operation and measurement of the main characteristics of nuclear instruments was the focus of discussion at this meeting. Presentations made at the technical meeting provided

  16. Licensing of digital Instrumentation and Control in Radioisotope Production Facility

    International Nuclear Information System (INIS)

    Abdel-Aziz, L.Kh.; Lashin, R.; Mostafa, W.

    2012-01-01

    In spite of the rapid development of digital I and C systems in all major industries, it has for several reasons been slower in nuclear power plants. The most important reason is that only a few new plants have been ordered worldwide during the last ten years. A second reason is connected to the efforts needed in providing adequate evidence that the digital I and C system can be used in safety and safety related applications. This issue is connected to the effort needed in obtaining adequate assurance that the digital I and C will fulfill its intended function and contain no unintended function in all possible operational states during its entire life cycle. This paper presents an acceptance criteria for licensing a digital instrumentation and control system in a Radioisotope Production Facility(1), which is under commissioning. The acceptance criteria ensure that the I and C systems are designed to reach the highest degree of reliability with respect to the function they perform, operators will have clear and accessible availability to data on every plant parameter, and also ensure that the safety objectives have been covered

  17. A basic design of SR4 instrumentation and control system for research reactor

    International Nuclear Information System (INIS)

    Syahrudin Yusuf; M Subhan; Ikhsan Shobari; Sutomo Budihardjo

    2010-01-01

    An SR4 instrumentation and control systems of research reactor is the equipment of nuclear research reactors as power protection devices and control systems. The equipment is to monitor safety parameters and process parameters in the state of reactor shut down, start-up, and in operation at fixed power. In the engineering of Instrumentation and control systems SR4 research reactor, its basic design consists of technical specifications of the reactor protection system devices, technical specifications of the reactor power control system devices, technical specifications information system devices, and systems process termination cabling as a support system. This basic design is used as the basis for the preparation of detailed design and subsequent engineering development of instrumentation systems and control system integrated. (author)

  18. Predicting Falls in Parkinson Disease: What Is the Value of Instrumented Testing in OFF Medication State?

    Directory of Open Access Journals (Sweden)

    Martina Hoskovcová

    Full Text Available Falls are a common complication of advancing Parkinson's disease (PD. Although numerous risk factors are known, reliable predictors of future falls are still lacking. The objective of this prospective study was to investigate clinical and instrumented tests of balance and gait in both OFF and ON medication states and to verify their utility in the prediction of future falls in PD patients.Forty-five patients with idiopathic PD were examined in defined OFF and ON medication states within one examination day including PD-specific clinical tests, instrumented Timed Up and Go test (iTUG and computerized dynamic posturography. The same gait and balance tests were performed in 22 control subjects of comparable age and sex. Participants were then followed-up for 6 months using monthly fall diaries and phone calls.During the follow-up period, 27/45 PD patients and 4/22 control subjects fell one or more times. Previous falls, fear of falling, more severe motor impairment in the OFF state, higher PD stage, more pronounced depressive symptoms, higher daily levodopa dose and stride time variability in the OFF state were significant risk factors for future falls in PD patients. Increased stride time variability in the OFF state in combination with faster walking cadence appears to be the most significant predictor of future falls, superior to clinical predictors.Incorporating instrumented gait measures into the baseline assessment battery as well as accounting for both OFF and ON medication states might improve future fall prediction in PD patients. However, instrumented testing in the OFF state is not routinely performed in clinical practice and has not been used in the development of fall prevention programs in PD. New assessment methods for daylong monitoring of gait, balance and falls are thus required to more effectively address the risk of falling in PD patients.

  19. Measuring Instruments Control Methodology Performance for Analog Electronics Remote Labs

    Directory of Open Access Journals (Sweden)

    Unai Hernandez-Jayo

    2012-12-01

    Full Text Available This paper presents the work that has been developed in parallel to the VISIR project. The objective of this paper is to present the results of the validations processes that have been carried out to check the control methodology. This method has been developed with the aim of being independent of the instruments of the labs.

  20. Acceptance for Beneficial Use Pumping Instrumentation and Control Skid ''M''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This document is a Final Acceptance for Beneficial Use (ABU) for the readiness of Pumping Instrumentation and Control (PIC) skid ''M''. All the testing and documentation for PIC skid ''M'' is completed and the skid is ready for use in the field for pumping of tank U-102

  1. The strategy for intelligent integrated instrumentation and control system development

    International Nuclear Information System (INIS)

    Kwon, Kee Choon; Ham, Chang Shik

    1995-01-01

    All of the nuclear power plants in Korea are operating with analog instrumentation and control ( I and C) equipment which are increasingly faced with frequent troubles, obsolescence and high maintenance expenses. Electrical and computer technology has improved rapidly in recent years and has been applied to other industries. So it is strongly recommended we adopt modern digital and computer technology to improve plant safety and availability. The advanced I and C system, namely, Integrated Intelligent Instrumentation and Control System (I 3 Cs) will be developed for beyond the next generation nuclear power plant. I 3 CS consists of three major parts, the advanced compact workstation, distributed digital control and protection system including Automatic Start-up/Shutdown Intelligent Control System (ASICS) and the computer-based alarm processing and operator support system, namely, Diagnosis, Response, and operator Aid Management System (DREAMS)

  2. Instrumentation, controls and automation in the power industry

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    The year 1991 will be remembered as the year EPRI joined with the ISA Power Division to present an outstanding group to technical papers at the First Annual ISA/EPRI Joint Controls and Automation Conference. All papers met the theme for the conference namely Innovative Instrumentation, Controls, and Automation Techniques for the Power Generation Industry and cover a myriad of application ranging from nuclear to conventional fossil to co-generation plants involving nuclear, conventional BTG, and combined cycle equipment applications

  3. 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)

  4. Instrumentation

    International Nuclear Information System (INIS)

    Decreton, M.

    2000-01-01

    SCK-CEN's research and development programme on instrumentation aims at evaluating the potentials of new instrumentation technologies under the severe constraints of a nuclear application. It focuses on the tolerance of sensors to high radiation doses, including optical fibre sensors, and on the related intelligent data processing needed to cope with the nuclear constraints. Main achievements in these domains in 1999 are summarised

  5. Design of virtual three-dimensional instruments for sound control

    Science.gov (United States)

    Mulder, Axel Gezienus Elith

    An environment for designing virtual instruments with 3D geometry has been prototyped and applied to real-time sound control and design. It enables a sound artist, musical performer or composer to design an instrument according to preferred or required gestural and musical constraints instead of constraints based only on physical laws as they apply to an instrument with a particular geometry. Sounds can be created, edited or performed in real-time by changing parameters like position, orientation and shape of a virtual 3D input device. The virtual instrument can only be perceived through a visualization and acoustic representation, or sonification, of the control surface. No haptic representation is available. This environment was implemented using CyberGloves, Polhemus sensors, an SGI Onyx and by extending a real- time, visual programming language called Max/FTS, which was originally designed for sound synthesis. The extension involves software objects that interface the sensors and software objects that compute human movement and virtual object features. Two pilot studies have been performed, involving virtual input devices with the behaviours of a rubber balloon and a rubber sheet for the control of sound spatialization and timbre parameters. Both manipulation and sonification methods affect the naturalness of the interaction. Informal evaluation showed that a sonification inspired by the physical world appears natural and effective. More research is required for a natural sonification of virtual input device features such as shape, taking into account possible co- articulation of these features. While both hands can be used for manipulation, left-hand-only interaction with a virtual instrument may be a useful replacement for and extension of the standard keyboard modulation wheel. More research is needed to identify and apply manipulation pragmatics and movement features, and to investigate how they are co-articulated, in the mapping of virtual object

  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. Acceptance for Beneficial Use Pumping Instrumentation and Control Skid L

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This is a final Acceptance for Beneficial Use (ABU) for Pumping and Instrumentation Control (PIC) skid ''L''. PIC skid ''L'' is ready for pumping tank U-105. All the testing and documentation has been completed as required on the ABU checklist. This ABU covers only the readiness of the PIC skid ''L''. Other U-farm preparations including dilution tank fabrication, portable exhauster readiness, leak detection, valve pit preparation, and the Operation Control Station readiness are not part of this ABU. PIC skid ''L'' is a new skid fabricated and tested at Site Fabrication Services. The skid controls the jet pump and monitors various instruments associated with the pumping operation. This monitoring includes leak detection along the waste transfer route and flammable gases in the pump pit

  8. WTEC panel report on European nuclear instrumentation and controls

    International Nuclear Information System (INIS)

    White, J.D.; Lanning, D.D.; Johnson, P.M.H.

    1991-12-01

    A study of instrumentation and controls (I and C) technology used in nuclear power plants in Europe was conducted by a panel of US specialists. This study plants in Europe was conducted by a panel of US specialists. This study included a review of the literature on the subject, followed by a visit to some of the leading organizations in Europe in the field nuclear I and C. Areas covered are: (1) role of the operator and control room design; (2) transition from analog to digital technology; (3) computerized operator support systems for fault management; (4) control strategies and techniques; (5) Nuclear power plant I and C architecture; (6) instrumentation and (7) computer standards and tools. The finding relate to poor reactions

  9. Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2001-04-01

    SCK-CEN's research and development programme on instrumentation involves the assessment and the development of sensitive measurement systems used within a radiation environment. Particular emphasis is on the assessment of optical fibre components and their adaptability to radiation environments. The evaluation of ageing processes of instrumentation in fission plants, the development of specific data evaluation strategies to compensate for ageing induced degradation of sensors and cable performance form part of these activities. In 2000, particular emphasis was on in-core reactor instrumentation applied to fusion, accelerator driven and water-cooled fission reactors. This involved the development of high performance instrumentation for irradiation experiments in the BR2 reactor in support of new instrumentation needs for MYRRHA, and for diagnostic systems for the ITER reactor.

  10. Instrumentation

    International Nuclear Information System (INIS)

    Decreton, M.

    2001-01-01

    SCK-CEN's research and development programme on instrumentation involves the assessment and the development of sensitive measurement systems used within a radiation environment. Particular emphasis is on the assessment of optical fibre components and their adaptability to radiation environments. The evaluation of ageing processes of instrumentation in fission plants, the development of specific data evaluation strategies to compensate for ageing induced degradation of sensors and cable performance form part of these activities. In 2000, particular emphasis was on in-core reactor instrumentation applied to fusion, accelerator driven and water-cooled fission reactors. This involved the development of high performance instrumentation for irradiation experiments in the BR2 reactor in support of new instrumentation needs for MYRRHA, and for diagnostic systems for the ITER reactor

  11. The contribution of instrumentation and control software to system reliability

    International Nuclear Information System (INIS)

    Fryer, M.O.

    1984-01-01

    Advanced instrumentation and control systems are usually implemented using computers that monitor the instrumentation and issue commands to control elements. The control commands are based on instrument readings and software control logic. The reliability of the total system will be affected by the software design. When comparing software designs, an evaluation of how each design can contribute to the reliability of the system is desirable. Unfortunately, the science of reliability assessment of combined hardware and software systems is in its infancy. Reliability assessment of combined hardware/software systems is often based on over-simplified assumptions about software behavior. A new method of reliability assessment of combined software/hardware systems is presented. The method is based on a procedure called fault tree analysis which determines how component failures can contribute to system failure. Fault tree analysis is a well developed method for reliability assessment of hardware systems and produces quantitative estimates of failure probability based on component failure rates. It is shown how software control logic can be mapped into a fault tree that depicts both software and hardware contributions to system failure. The new method is important because it provides a way for quantitatively evaluating the reliability contribution of software designs. In many applications, this can help guide designers in producing safer and more reliable systems. An application to the nuclear power research industry is discussed

  12. 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)

  13. Backfitting in Rossendorf research reactor control and instrumentation system

    International Nuclear Information System (INIS)

    Klebau, J.; Seidler, S.

    1985-01-01

    The paper generally describes a decentralized Hierarchical Information System (HIS) which has been developed for backfitting in Rossendorf Research Reactor (RFR) control and instrumentation system. The RFR was put into operation in 1957 and reconstructed from 2 MW up to a thermal power of 10 MW at the end of the sixties. Backfitting is planned by use of an advanced computerized control system for the next years. Main tasks of HIS are: Processmonitoring, online-disturbance analysis, technical diagnosis, direct digital control and use of a special industrial robot for discharging of irradiated materials out of the reactor. Experiences obtained by HIS during a testperiod will be presented. (author)

  14. Hardware design for new instrumentation and control system of RTP

    International Nuclear Information System (INIS)

    Mohd Idris Taib; Izhar Abu Hussin; Zareen Khan Abdul Jalil Khan; Mohd Dzul Aiman Aslan; Mohd Khairulezwan Abdul Manan; Nurfarhana Ayuni Joha; Mohd Sabri Minhat

    2010-01-01

    The design for New Instrumentation and Control system of RTP are proposed. Physical system is modular-based, comprise of several cabinets such as Reactor Protection System 1 and 2, Control Console, Information Console 1 and 2 as well as Communication Console. Reactor Protection System automatically will shut-down reactor whenever safety limit setting was approach. Control console is where the reactor operator actually controls the reactor with control the movement of control rods. Information Consoles using Liquid Crystal Display to monitor the reactor parameters. Communication Console is where the communication tools such as telephone and intercom are located. This new system will incorporated analog, digital and computer-based. Reactor Protection System will use all analog system. Reactor Control System and Reactor Monitoring System will use analog as well as computer-based system. Wide-range channel will use digital signal processor as a main component. Controlling control rod movement is using control rod button via microprocessor-based control rod controller. Automatic Flux Controller is using embedded computer for flexibility of programming. Data Acquisition System is using Programmable Logic Controller and Industrial Computer. The main software for this system will be developed using WinCC software. (author)

  15. Instrumentation

    International Nuclear Information System (INIS)

    Decreton, M.

    2002-01-01

    SCK-CEN's R and D programme on instrumentation involves the development of advanced instrumentation systems for nuclear applications as well as the assessment of the performance of these instruments in a radiation environment. Particular emphasis is on the use of optical fibres as umbilincal links of a remote handling unit for use during maintanance of a fusion reacor, studies on the radiation hardening of plasma diagnostic systems; investigations on new instrumentation for the future MYRRHA accelerator driven system; space applications related to radiation-hardened lenses; the development of new approaches for dose, temperature and strain measurements; the assessment of radiation-hardened sensors and motors for remote handling tasks and studies of dose measurement systems including the use of optical fibres. Progress and achievements in these areas for 2001 are described

  16. Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2002-04-01

    SCK-CEN's R and D programme on instrumentation involves the development of advanced instrumentation systems for nuclear applications as well as the assessment of the performance of these instruments in a radiation environment. Particular emphasis is on the use of optical fibres as umbilincal links of a remote handling unit for use during maintanance of a fusion reacor, studies on the radiation hardening of plasma diagnostic systems; investigations on new instrumentation for the future MYRRHA accelerator driven system; space applications related to radiation-hardened lenses; the development of new approaches for dose, temperature and strain measurements; the assessment of radiation-hardened sensors and motors for remote handling tasks and studies of dose measurement systems including the use of optical fibres. Progress and achievements in these areas for 2001 are described.

  17. Virtual Instrumentation Corrosion Controller for Natural Gas Pipelines

    Science.gov (United States)

    Gopalakrishnan, J.; Agnihotri, G.; Deshpande, D. M.

    2012-12-01

    Corrosion is an electrochemical process. Corrosion in natural gas (methane) pipelines leads to leakages. Corrosion occurs when anode and cathode are connected through electrolyte. Rate of corrosion in metallic pipeline can be controlled by impressing current to it and thereby making it to act as cathode of corrosion cell. Technologically advanced and energy efficient corrosion controller is required to protect natural gas pipelines. Proposed virtual instrumentation (VI) based corrosion controller precisely controls the external corrosion in underground metallic pipelines, enhances its life and ensures safety. Designing and development of proportional-integral-differential (PID) corrosion controller using VI (LabVIEW) is carried out. When the designed controller is deployed at field, it maintains the pipe to soil potential (PSP) within safe operating limit and not entering into over/under protection zone. Horizontal deployment of this technique can be done to protect all metallic structure, oil pipelines, which need corrosion protection.

  18. 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

  19. Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2000-07-01

    SCK-CEN's research and development programme on instrumentation aims at evaluating the potentials of new instrumentation technologies under the severe constraints of a nuclear application. It focuses on the tolerance of sensors to high radiation doses, including optical fibre sensors, and on the related intelligent data processing needed to cope with the nuclear constraints. Main achievements in these domains in 1999 are summarised.

  20. A new instrument for statistical process control of thermoset molding

    International Nuclear Information System (INIS)

    Day, D.R.; Lee, H.L.; Shepard, D.D.; Sheppard, N.F.

    1991-01-01

    The recent development of a rugged ceramic mold mounted dielectric sensor and high speed dielectric instrumentation now enables monitoring and statistical process control of production molding over thousands of runs. In this work special instrumentation and software (ICAM-1000) was utilized that automatically extracts critical point during the molding process including flow point, viscosity minimum gel inflection, and reaction endpoint. In addition, other sensors were incorporated to measure temperature and pressure. The critical point as well as temperature and pressure were then recorded during normal production and then plotted in the form of statistical process control (SPC) charts. Experiments have been carried out in RIM, SMC, and RTM type molding operations. The influence of temperature, pressure chemistry, and other variables has been investigated. In this paper examples of both RIM and SMC are discussed

  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. Instrumentation and Controls evaluation for space nuclear power systems

    International Nuclear Information System (INIS)

    Anderson, J.L.; Oakes, L.C.

    1984-01-01

    Design of control and protection systems should be coordinated with the design of the neutronic, thermal-hydraulic, and mechanical aspects of the core and plant at the earliest possible stage of concept development. An integrated systematic design approach is necessary to prevent uncoordinated choices in one technology area from imposing impractical or impossible requirements in another. Significant development and qualification will be required for virtually every aspect of reactor control and instrumentation. In-core instrumentation widely used in commercial light water reactors will not likely be usable in the higher temperatures of a space power plant. Thermocouples for temperature measurement and gamma thermometers for flux measurement appear to be the only viable candidates. Recent developments in ex-core neutron detectors may provide achievable alternatives to in-core measurements. Reliable electronic equipment and high-temperature actuators will require major development efforts

  3. Computer Security of NPP Instrumentation and Control Systems: Cyber Threats

    International Nuclear Information System (INIS)

    Klevtsov, A.L.; Trubchaninov, S.A.

    2015-01-01

    The paper is devoted to cyber threats, as one of the aspects in computer security of instrumentation and control systems for nuclear power plants (NPP). The basic concepts, terms and definitions are shortly addressed. The paper presents a detailed analysis of potential cyber threats during the design and operation of NPP instrumentation and control systems. Eleven major types of threats are considered, including: the malicious software and hardware Trojans (in particular, in commercial-off-the-shelf software and hardware), computer attacks through data networks and intrusion of malicious software from an external storage media and portable devices. Particular attention is paid to the potential use of lower safety class software as a way of harmful effects (including the intrusion of malicious fragments of code) on higher safety class software. The examples of actual incidents at various nuclear facilities caused by intentional cyber attacks or unintentional computer errors during the operation of software of systems important to NPP safety.

  4. Future independent power generation and implications for instruments and controls

    International Nuclear Information System (INIS)

    Williams, J.H.

    1991-01-01

    This paper reports that the independent power producers market is comprised of cogeneration, small power generation, and independent power production (IPP) segments. Shortfalls in future electric supply are expected to lead to significant growth in this market. The opportunities for instruments and controls will shift from traditional electric utility applications to the independent power market with a more diverse set of needs. Importance will be placed on system reliability, quality of power and increased demand for clean kWh

  5. 21 CFR 111.117 - What quality control operations are required for equipment, instruments, and controls?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 2 2010-04-01 2010-04-01 false What quality control operations are required for equipment, instruments, and controls? 111.117 Section 111.117 Food and Drugs FOOD AND DRUG ADMINISTRATION... and Process Control System: Requirements for Quality Control § 111.117 What quality control operations...

  6. State of work on Main Task 3.1.3 of Complex Programme of Scientific and Technical Progress and precondition for ensuring Czechoslovak automatic control system instrumentation and electrical parts for new-generation power plant project

    International Nuclear Information System (INIS)

    Hrebik, V.

    1990-01-01

    A brief account is given of the state of negotiations with the Soviet partner concerning the preparation, creation and implementation of prospective automated technological equipment control systems at WWER type nuclear power plants. The organization is very clumsy in some fields and their conceptions are not clear. (Z.S.)

  7. Safeguarding the functions and performance of instrumentation and control systems

    International Nuclear Information System (INIS)

    Koehler, M.; Schoerner, O.

    1996-01-01

    Based on an analysis of the existing nuclear power plant control technology, the necessity of providing in the medium-term advanced and future-oriented, digital control system, both for normal operation and for safety-relevant tasks of the reactor and safety control systems. Siemens KWU has been promoting the development, review and marketing of the digital instrumentation and control systems called TELEPERM XS and TELEPERM XP in addition to the measures taken for safeguarding the functions of existing, wired systems. The paper briefly explains the performance and advantages of digital systems and the progress in approval and pioneering of the TELEPERM XS safety control system. Many examples discussed show the diversity of applications of the systems both in new reactor plants and as retrofitting measures, for KWU power plants and those of other manufacturers. (orig.) [de

  8. 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

  9. 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

  10. Challenges for maintaining the modernization of instrumentation and control systems

    International Nuclear Information System (INIS)

    Rojas, V.

    2014-01-01

    Instrumentation and control system upgrades in nuclear power plants come with some challenges for their maintenance staff. It is important to have a long term modernization plant that derives from specific studies for each system. Training, spares, configuration control and cybersecurity are critical topics to take into account from the beginning of these projects. New system maintenance plans can require a new approach in accordance with the technology. FPGAs (Field Programmable Gate Array) appear as the alternative for the future, mainly in safety systems. (Author)

  11. Control and instrumentation: micros, minis and making them manage

    International Nuclear Information System (INIS)

    Mitchie, R.E.; Neal, R.

    1989-01-01

    The control and instrumentation systems on Heysham 2 and Torness Power Stations are more extensive and complex than on previous power stations. In particular computer based equipment has been used extensively for both control and monitoring functions. The design and implementation of the computer based systems introduced many complex technical and project management problems. In many areas the project management arrangements were adapted to cope with these problems and to seek to standardise on the types of equipment being used on the stations. Considerable success has been achieved in this latter respect and is expected to lead to benefits in maintenance costs over the station life. (author)

  12. Temperature control system for optical elements in astronomical instrumentation

    Science.gov (United States)

    Verducci, Orlando; de Oliveira, Antonio C.; Ribeiro, Flávio F.; Vital de Arruda, Márcio; Gneiding, Clemens D.; Fraga, Luciano

    2014-07-01

    Extremely low temperatures may damage the optical components assembled inside of an astronomical instrument due to the crack in the resin or glue used to attach lenses and mirrors. The environment, very cold and dry, in most of the astronomical observatories contributes to this problem. This paper describes the solution implemented at SOAR for remotely monitoring and controlling temperatures inside of a spectrograph, in order to prevent a possible damage of the optical parts. The system automatically switches on and off some heat dissipation elements, located near the optics, as the measured temperature reaches a trigger value. This value is set to a temperature at which the instrument is not operational to prevent malfunction and only to protect the optics. The software was developed with LabVIEWTM and based on an object-oriented design that offers flexibility and ease of maintenance. As result, the system is able to keep the internal temperature of the instrument above a chosen limit, except perhaps during the response time, due to inertia of the temperature. This inertia can be controlled and even avoided by choosing the correct amount of heat dissipation and location of the thermal elements. A log file records the measured temperature values by the system for operation analysis.

  13. Simultaneous control of multiple instruments at the Advanced Technology Solar Telescope

    Science.gov (United States)

    Johansson, Erik M.; Goodrich, Bret

    2012-09-01

    The Advanced Technology Solar Telescope (ATST) is a 4-meter solar observatory under construction at Haleakala, Hawaii. The simultaneous use of multiple instruments is one of the unique capabilities that makes the ATST a premier ground based solar observatory. Control of the instrument suite is accomplished by the Instrument Control System (ICS), a layer of software between the Observatory Control System (OCS) and the instruments. The ICS presents a single narrow interface to the OCS and provides a standard interface for the instruments to be controlled. It is built upon the ATST Common Services Framework (CSF), an infrastructure for the implementation of a distributed control system. The ICS responds to OCS commands and events, coordinating and distributing them to the various instruments while monitoring their progress and reporting the status back to the OCS. The ICS requires no specific knowledge about the instruments. All information about the instruments used in an experiment is passed by the OCS to the ICS, which extracts and forwards the parameters to the appropriate instrument controllers. The instruments participating in an experiment define the active instrument set. A subset of those instruments must complete their observing activities in order for the experiment to be considered complete and are referred to as the must-complete instrument set. In addition, instruments may participate in eavesdrop mode, outside of the control of the ICS. All instrument controllers use the same standard narrow interface, which allows new instruments to be added without having to modify the interface or any existing instrument controllers.

  14. Information needs and instrumentation for hydrogen control and management

    International Nuclear Information System (INIS)

    Park, Gun Chul; Suh, Kune Y.; Lee, Seung Dong; Lee, Jin Yong; Jae, Moo Sung

    2000-03-01

    In this study we examined instrument information, which is related to the severe accident management, guidance. We also examined the hydrogen control and management strategy. Hydrogen control occupies and important part in severe accident management and adequate hydrogen control strategy i needed to maintain the plant integrity. Reducing containment hydrogen during a severe accident will mitigate a potential containment failure mechanism. One of the hydrogen control strategies os intentional burning by the hydrogen igniter. Though intentional hydrogen burn strategy may cause pressure and temperature spikes, which are adverse effects, it si the fastest way of reducing the containment hydrogen concentration. From the Ulchin 3 and 4 plant information we developed a simple hydrogen ignition decision tree. And from the information of decision tree, hydrogen ignition decision can be determined in Containment Event Tree (CET). The end branch values in the CET are hydrogen concentrations, which will be used to assess the accident management measure

  15. Information needs and instrumentation for hydrogen control and management

    Energy Technology Data Exchange (ETDEWEB)

    Park, Gun Chul; Suh, Kune Y.; Lee, Seung Dong; Lee, Jin Yong [Seoul National Univ., Seoul (Korea, Republic of); Jae, Moo Sung [Hanyang Univ., Seoul (Korea, Republic of)

    2000-03-15

    In this study we examined instrument information, which is related to the severe accident management, guidance. We also examined the hydrogen control and management strategy. Hydrogen control occupies and important part in severe accident management and adequate hydrogen control strategy i needed to maintain the plant integrity. Reducing containment hydrogen during a severe accident will mitigate a potential containment failure mechanism. One of the hydrogen control strategies os intentional burning by the hydrogen igniter. Though intentional hydrogen burn strategy may cause pressure and temperature spikes, which are adverse effects, it si the fastest way of reducing the containment hydrogen concentration. From the Ulchin 3 and 4 plant information we developed a simple hydrogen ignition decision tree. And from the information of decision tree, hydrogen ignition decision can be determined in Containment Event Tree (CET). The end branch values in the CET are hydrogen concentrations, which will be used to assess the accident management measure.

  16. Instruments

    International Nuclear Information System (INIS)

    Buehrer, W.

    1996-01-01

    The present paper mediates a basic knowledge of the most commonly used experimental techniques. We discuss the principles and concepts necessary to understand what one is doing if one performs an experiment on a certain instrument. (author) 29 figs., 1 tab., refs

  17. A set of portable radioisotopic control and measuring instruments

    International Nuclear Information System (INIS)

    Pospeev, V.V.; Sidorov, V.N.; Tesnavs, Eh.R.; Uleksin, V.I.

    1979-01-01

    The problems and perspectives are examined of the portable radioisotope instruments application in agriculture, building industry, engeeniring and geological survay and in melioration. Principles are given of creation a series of radioisotopic instruments based on the principle of ganging. The series described consists of radioisotopic densimeters and moisture gages of the portable type, based on the ganging principle. The instruments differ in the measuring converters and have unified information processing and power supply devices. Criteria are stated for the ganging principle estimation, in particular, estimation of the technical means' compatibility. Four different types of compatibility are distinguished: an information compatibility; a metrological compatibility; structural and operational compatibility. Description is given of the unified information processing device - the unified pulse counter of the SIP-1M type and description of a row of radioisotopic measuring converters, which provides a possibility for completing the portable radioisotope densimeter of the RPP-2 type, intended for measuring densities of concrets and soils in the surface layer up to 30 cm and the density range from 1000 to 2500 kg/m 3 ; portable radioisotope densimeter of the RPP-1 type having measuring range from 600 to 1500 kg/m 3 ; surface-depth radioisotopic densimeter of the PPGR-1 type and surface-depth radioisotopic moisture gage of the VPGR-1 type [ru

  18. Vehicle electrical system state controller

    Science.gov (United States)

    Bissontz, Jay E.

    2017-10-17

    A motor vehicle electrical power distribution system includes a plurality of distribution sub-systems, an electrical power storage sub-system and a plurality of switching devices for selective connection of elements of and loads on the power distribution system to the electrical power storage sub-system. A state transition initiator provides inputs to control system operation of switching devices to change the states of the power distribution system. The state transition initiator has a plurality of positions selection of which can initiate a state transition. The state transition initiator can emulate a four position rotary ignition switch. Fail safe power cutoff switches provide high voltage switching device protection.

  19. Cryogenic instrumentation needs in the controlled thermonuclear research program

    International Nuclear Information System (INIS)

    Walstrom, P.L.

    1976-01-01

    The magnet development effort for the controlled thermonuclear research program will require extensive testing of superconducting coils at various sizes from small-scale models to full-size prototypes. Extensive use of diagnostic instrumentation will be required and to make detailed comparisons of predicted and actual performance in magnet tests and to monitor the test facility for incipient failure modes. At later stages of the program, cryogenic instrumentation will be required to monitor magnet system performance in fusion power reactors. Measured quantities may include temperature, strain, deflection, coil resistance, helium coolant pressure and flow, current, voltages, etc. The test environment, which includes high magnetic fields (up to 8-10 T) and low temperature, makes many commercial measuring devices inoperative or at least inaccurate. In order to ensure reliable measurements, careful screening of commercial devices for performance in the test environment will be required. A survey of potentially applicable instrumentation is presented along with available information on operation in the test environment based on experimental data or on analysis of the physical characteristics of the device. Areas where further development work is needed are delineated

  20. Simple Instrumental and Visual Tests for Nonlaboratory Environmental Control

    Directory of Open Access Journals (Sweden)

    L. P. Eksperiandova

    2016-01-01

    Full Text Available Proposed are simple and available techniques that can be used for rapid and reliable environmental control specifically of natural water by means of instrumental and visual tests in outdoor conditions. Developed are the chemical colorimetric modes for fast detection of socially dangerous trace impurities in water such as Co(II, Pd(II, and Rh(III as well as NO2--ions and Fe(III serving as model impurities. Application of portable digital devices and scanner allows estimating the color coordinates and increasing the accuracy and sensitivity of the tests. The combination of complex formation with preconcentration of colored complexes replaces the sensitive but time-consuming and capricious kinetic method that is usually used for this purpose at the more convenient and reliable colorimetric method. As the test tools, the following ones are worked out: polyurethane foam tablets with sorbed colored complexes, the two-layer paper sandwich packaged in slide adapter and saturated by reagents, and polyethylene terephthalate blister with dried reagents. Fast analysis of polyurethane foam tablets is realized using a pocket digital RGB-colorimeter or portable photometer. Express analysis of two-layer paper sandwich or polyethylene terephthalate blister is realized by visual and instrumental tests. The metrological characteristics of the developed visual and instrumental express analysis techniques are estimated.

  1. Software for the Local Control and Instrumentation System for MFTF

    International Nuclear Information System (INIS)

    Labiak, W.G.

    1979-01-01

    There are nine different systems requiring over fifty computers in the Local Control and Instrumentation System for the Mirror Fusion Test Facility. Each computer system consists of an LSI-11/2 processor with 32,000 words of memory, a serial driver that implements the CAMAC serial highway protocol. With this large number of systems it is important that as much software as possible be common to all systems. A serial communications system has been developed for data transfers between the LSI-11/2's and the supervisory computers. This system is based on the RS 232 C interface with modem control lines. Six modem control lines are used for hardware handshaking, which allows totally independent full duplex communications to occur. Odd parity on each byte and a 16-bit checksum are used to detect errors in transmission

  2. Instrumentation and control of the fast breeder reactors

    International Nuclear Information System (INIS)

    Juengst, U.

    1982-01-01

    Generally the Liquid Metal Fast Breeder Reactor (LMFBR) in comparison to the Leight Water Reactors hasn't exceptionally different requirements to the instrumentation and control systems. There fore the paper restricts itself to outline the peculiarities of LMFBR's exemplified at the design of the German Breeder SNR-300 beeing under construction. The special sodium instrumentation for temperature level, flow and pressure in the main systems is described. The automatic control system enabled the plant to follow the bad demand of the grid immidiately. The nuclear power production itself is stabilized by inherent coefficients of the core. An exceptional high reliability of the shut down systems is necessary; there fore all LMFBR's have two completely independant and diverse shut down systems. In the SNR-300 also the control of decay heat removal and the active safety systems for enclosure of radioactivity are distributed to two independent and diverse plant protection systems (PPS) so that the first system covered the accidents due to internal events and the second systems managed the external events such as earthquake and aircraft crash. (orig.)

  3. VIMOS Instrument Control Software Design: an Object Oriented Approach

    Science.gov (United States)

    Brau-Nogué, Sylvie; Lucuix, Christian

    2002-12-01

    The Franco-Italian VIMOS instrument is a VIsible imaging Multi-Object Spectrograph with outstanding multiplex capabilities, allowing to take spectra of more than 800 objects simultaneously, or integral field spectroscopy mode in a 54x54 arcsec area. VIMOS is being installed at the Nasmyth focus of the third Unit Telescope of the European Southern Observatory Very Large Telescope (VLT) at Mount Paranal in Chile. This paper will describe the analysis, the design and the implementation of the VIMOS Instrument Control System, using UML notation. Our Control group followed an Object Oriented software process while keeping in mind the ESO VLT standard control concepts. At ESO VLT a complete software library is available. Rather than applying waterfall lifecycle, ICS project used iterative development, a lifecycle consisting of several iterations. Each iteration consisted in : capture and evaluate the requirements, visual modeling for analysis and design, implementation, test, and deployment. Depending of the project phases, iterations focused more or less on specific activity. The result is an object model (the design model), including use-case realizations. An implementation view and a deployment view complement this product. An extract of VIMOS ICS UML model will be presented and some implementation, integration and test issues will be discussed.

  4. Role of maintenance of analytical instruments in the proceedings of quality control laboratory

    International Nuclear Information System (INIS)

    Haribabu, A.; Sailoo, C.C.; Balaji Rao, Y.; Subba Rao, Y.

    2015-01-01

    Control Laboratory being a centralized analytical facility of Nuclear Fuel Complex (NFC) is engaged in chemical qualification of all nuclear materials processed/produced at NFC. The primary responsibility of control laboratory is to provide timely analytical results of raw materials, intermediates and final products to all the production plants of NFC for downstream processing. Annual analytical load of nearly five lakhs of estimations are being carried out at laboratory. For this purpose a gamut of analytical facilities ranging from classical methods like gravimetry, volumetry etc. to fully automated state-of-art analytical instruments like ICP-AES, Gas Analysers, Flame and Graphite Furnace-AAS, Direct Reading Emission Spectrometer (DRES), RF GD-OES, TIMS, WD-XRFS, ED-XRFS, Laser based PSD Analyser, Laser Fluorimeter, UV-Vis Spectrophotometer, Gamma Ray Spectrometer, Ion-Chromatography, Gas Chromatography are used to acquire analytical data to see the suitability of products for their intended use. Depending on the applications, analysts validate their procedures, calibrate their instruments, and perform additional instrument checks, such as system suitability tests and analysis of in-process quality control check samples. With the increasing sophistication and automation of analytical instruments, an increasing demand has been placed on maintenance engineers to qualify these instruments for the purpose

  5. Instrumentation

    International Nuclear Information System (INIS)

    Muehllehner, G.; Colsher, J.G.

    1982-01-01

    This chapter reviews the parameters which are important to positron-imaging instruments. It summarizes the options which various groups have explored in designing tomographs and the methods which have been developed to overcome some of the limitations inherent in the technique as well as in present instruments. The chapter is not presented as a defense of positron imaging versus single-photon or other imaging modality, neither does it contain a description of various existing instruments, but rather stresses their common properties and problems. Design parameters which are considered are resolution, sampling requirements, sensitivity, methods of eliminating scattered radiation, random coincidences and attenuation. The implementation of these parameters is considered, with special reference to sampling, choice of detector material, detector ring diameter and shielding and variations in point spread function. Quantitation problems discussed are normalization, and attenuation and random corrections. Present developments mentioned are noise reduction through time-of-flight-assisted tomography and signal to noise improvements through high intrinsic resolution. Extensive bibliography. (U.K.)

  6. Instrumentation and control improvements at Experimental Breeder Reactor II

    International Nuclear Information System (INIS)

    Christensen, L.J.; Planchon, H.P.

    1993-01-01

    The purpose of this paper is to describe instrumentation and control (I ampersand C) system improvements at Experimental Breeder Reactor 11 (EBR-11). The improvements are focused on three objectives; to keep the reactor and balance of plant (BOP) I ampersand C systems at a high level of reliability, to provide diagnostic systems that can provide accurate information needed for analysis of fuel performance, and to provide systems that will be prototypic of I ampersand C systems of the next generation of liquid metal reactor (LMR) plants

  7. Feedback control of acoustic musical instruments: collocated control using physical analogs.

    Science.gov (United States)

    Berdahl, Edgar; Smith, Julius O; Niemeyer, Günter

    2012-01-01

    Traditionally, the average professional musician has owned numerous acoustic musical instruments, many of them having distinctive acoustic qualities. However, a modern musician could prefer to have a single musical instrument whose acoustics are programmable by feedback control, where acoustic variables are estimated from sensor measurements in real time and then fed back in order to influence the controlled variables. In this paper, theory is presented that describes stable feedback control of an acoustic musical instrument. The presentation should be accessible to members of the musical acoustics community who may have limited or no experience with feedback control. First, the only control strategy guaranteed to be stable subject to any musical instrument mobility is described: the sensors and actuators must be collocated, and the controller must emulate a physical analog system. Next, the most fundamental feedback controllers and the corresponding physical analog systems are presented. The effects that these controllers have on acoustic musical instruments are described. Finally, practical design challenges are discussed. A proof explains why changing the resonance frequency of a musical resonance requires much more control power than changing the decay time of the resonance. © 2012 Acoustical Society of America.

  8. Halden Reactor Project Workshop: Understanding Advanced Instrumentation and Controls Issues

    International Nuclear Information System (INIS)

    Beltracchi, L.

    1991-01-01

    A Halden Reactor Project Workshop on 'Understanding Advanced Instrumentation and Controls Issues' was held in Halden, Norway, during June 17-18, 1991. The objectives of the workshop were to (1) identify and prioritize the types of technical information that the Halden Project can produce to facilitate the development of man-machine interface guidelines and (2) to identify methods to effectively integrate and disseminate this information to signatory organizations. As a member of the Halden Reactor Project, the Nuclear Regulatory Commission (NRC) requested the workshop. This request resulted from the NRC's need for human factors guidelines for the evaluation of advanced instrumentation and controls. The Halden Reactor Project is a cooperative agreement among several countries belonging to the Organization for Economic Cooperation and Development (OECD). The US began its association with the Halden Project in 1958 through the Atomic Energy Commission. The project's activities are centered at the Halden heavy-water reactor and its associated man-machine laboratory in Halden, Norway. The research program conducted at Halden consists of studies on fuel performance and computer-based man-machine interfaces

  9. Upgrading instrumentation and control systems for plant safety and operation

    International Nuclear Information System (INIS)

    Martin, M.; Prehler, H.J.; Schramm, W.

    1997-01-01

    Upgrading the electrical systems and instrumentation and control systems has become increasingly more important in the past few years for nuclear power plants currently in operation. As the requirements to be met in terms of plant safety and availability have become more stringent in the past few years, Western plants built in the sixties and seventies have been the subject of manifold backfitting and upgrading measures in the past. In the meantime, however, various nuclear power plants are facing much more thorough upgrading phases because of the difficulties in obtaining spare parts for older equipment systems. As digital technology has become widespread in many areas because of its advantages, and as applications are continuously expanding, conventional equipment and systems are losing more and more ground as a consequence of decreasing demand. Merely because of the pronounced decline in demand for conventional electronic components it is possible for equipment manufacturers to guarantee spare parts deliveries for older systems only for specific future periods of time. In addition, one-off manufacture entails high costs in purchases of spare parts. As a consequence of current thinking more and more focusing on availability and economy, upgrading of electrical systems and instrumentation and control systems is becoming a more and more topical question, for older plants even to ensure completion of full service life. (orig.) [de

  10. 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

  11. 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

  12. Safety Research Experiment Facility Project. Conceptual design report. Volume VIII. Instrumentation and control

    International Nuclear Information System (INIS)

    1975-01-01

    Included are sections dealing with the following: nuclear instrumentation system, reactor control system, plant protection system, plant annunciator system, data acquisition system, and reactor cooling system instrumentation and control

  13. A Calculation of hydrodynamic noise of control valve on instrumentation and control system using smart plant

    International Nuclear Information System (INIS)

    Demon Handoyo; Djoko H Nugroho

    2012-01-01

    It has been calculated characteristics of the control valve Instrumentation and Control Systems using Smart Plant software. This calculation is done in order to control the valve that will be installed as part of the instrumentation and control systems to provide the performance according to the design. The characteristics that have been calculated are Reynolds number factors which are related to the flow regime in the valve. Critical pressure factor, Valve Hydrodynamic cavitation and noise index. In this paper the discussion will be limited to matters relating to Hydrodynamic noise generation process using model of the instrumentation and control system in the plant design in yellow cake PIPKPP activities in 2012. The results of the calculation of the noise on the valves design are in the range between 9.58~70.1 dBA. (author)

  14. Alternative approaches to pollution control and waste management: Regulatory and economic instruments

    International Nuclear Information System (INIS)

    Bernstein, J.D.

    1993-01-01

    The purpose of the paper is to present an overview of the most common strategies and policy instruments (that is, regulatory and economic) used in developed and developing countries to achieve pollution control and waste management objectives. Although this topic has been at the center of theoretical controversy both within and outside the World Bank, the paper is not intended to contribute to this debate. Rather, its purpose is to explore how regulatory and economic instruments are used to control air and water pollution, protect ground water, and manage solid and hazardous wastes. The paper is directed to policy makers at the national, state, and local levels of government, as well as to other parties responsible for pollution control and waste management programs

  15. The Gas Turbine Modular Helium Reactor Optimum Design for Instrumentation and Control

    International Nuclear Information System (INIS)

    Quinn, Edward 'Ted'; Rodriguez, Carmelo

    2002-01-01

    Nuclear power plants rely on instrumentation and control (I and C) systems for monitoring, control and protection. While the earlier generations of nuclear plants were built with largely analog instrumentation systems, the industrial base has moved to digital based system. The reason for this transition to digital I and C systems lies in their important advantage over existing analog systems. In essence, the challenge is to prove that the new digital guidelines included in NUREG 0800, Standard Review Plan Chapter 7 and all associated documents provided adequate direction and safety review for an advanced control design for a new nuclear plant in the United States. This paper focuses on how one of the new designs incorporates the latest technology and meets the new NRC requirements. (authors)

  16. ITER instrumentation and control-Status and plans

    International Nuclear Information System (INIS)

    Wallander, Anders; Abadie, Lana; Dave, Haresh; Di Maio, Franck; Gulati, Hitesh Kumar; Hansalia, Chandresh; Joonekindt, Didier; Journeaux, Jean-Yves; Klotz, Wolf-Dieter; Mahajan, Kirti; Makijarvi, Petri; Scibile, Luigi; Stepanov, Denis; Utzel, Nadine; Yonekawa, Izuru

    2010-01-01

    The ITER instrumentation and control (I and C) system is the term encompassing all hardware and software required to operate ITER. It has two levels of hierarchy: the central I and C systems and the plant systems I and C. The central I and C systems comprise CODAC (Control, Data Access and Communication), the central interlock system (CIS) and the central safety systems (CSS). The central I and C systems are 'in-fund', i.e. procured by ITER Organization (IO), while plant systems I and C are 'in-kind', i.e. procured by the seven ITER domestic agencies. This procurement model, together with the current estimate of 161 plant systems I and C, poses a major challenge for the realization and integration of the ITER I and C system. To address this challenge a main strategic focus of the CODAC group, formed in 2008, has been to establish good relations with the domestic agencies. By distributing the required R and D tasks and contracts fairly between the domestic agencies we build collaborations for the future at the same time as technical work proceed. The primary goal of ITER I and C system is to provide a fully integrated and automated control system for ITER. Standardization of plant systems I and C is of primary importance and has been the highest priority task during the last year. The target of associated R and D activities is to survey, benchmark and prototype main stream technologies, in order to choose the best and most widely used technology standards for plant systems I and C. In this paper we elaborate on our approach, both from a technical and a non-technical perspective, explain technology evaluation and decisions and finally present the way forward to ensure ITER I and C system will contribute and be instrumental in making ITER a success.

  17. A low cost modular control and instrumentation system for accelerators

    International Nuclear Information System (INIS)

    Shubaly, M.R.; Plato, J.G.; Davis, R.W.

    1984-01-01

    A modular control and instrumentation system, being developed for the RFQ1 accelerator and for ion beam test facilities, is based on an intelligent crate and interchangeable plug-in modules for specific applications. The 8085-based microcomputer used in the system can access up to 256 K of memory, has up to 64 levels of vectored interrupts and time of day, and supports terminals, printers, floppy discs and digital cassette drives. This computer is linked to a bus in the front of the crate which carries not only the usual address, data, and control signals, but also interrupt lines and interrupt chip control lines. This bus is designed for easy interfacing. Plug-in modules connect to the bus, and to monitored equipment via a separate connector leading to a terminal strip on the rear of the crate. These modules monitor absolute and differential temperature, flow-rate, voltages and currents and switch settings. A permanently installed module provides ac power switching, an RS232 serial link and full duplex fibre optic serial links for connection to a central computer. Software for the crate provides for task scheduling, data storage and limit tests, communication to higher levels of the control system and field configuration of the crate. (orig.)

  18. Remote diagnosis system for control and instrumentation systems

    International Nuclear Information System (INIS)

    Ito, Tetsuo; Suzuki, Satoshi; Nagaoka, Yukio.

    1990-01-01

    Control and instrumentation (C and I) systems for nuclear power plants tend to consist of many distributed digital controllers connected with transmission networks. Important parts of the C and I systems are redundantly constructed so that the failure of a component does not readily have a critical effect on the plant operation. It is necessary, however, to localize the faulty component for establishing better availability and maintainability of the plant. To diagnose failure of the C and I systems effectively, a remote diagnosis system is required that diagnoses anomalies of their controllers remotely from a central control room and identifies the fault location. Various fault diagnosis methods that apply artificial intelligence have been proposed for electronic circuits. Their knowledge bases are classified into two categories. One is rule-based knowledge, describing relations between anomaly phenomena and causes. The other is structure-based knowledge, which represents the configuration and functions of diagnosed objects. Though the latter is more suitable for deep inference, it is difficult to use for describing the detailed structure of large-scaled digital C and I systems. Then, a fault diagnosis system was developed that uses both knowledge bases and offers substantial man/machine interface functions for practical use

  19. 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

  20. Proceedings: Electromagnetic interference control in modern digital instrumentation and control upgrades

    International Nuclear Information System (INIS)

    1993-06-01

    A workshop on Electro-Magnetic Interference (EMI) Control in Modern Digital Instrumentation ampersand Control System Upgrade was held in Baltimore on September 10-11, 1992 to provide a forum for technology transfer, technical information exchange, and education. The workshop was attended by more than 70 representatives of electric utilities, equipment manufacturers, engineering consulting organizations, and government agencies. The workshop consists of four sessions: (1) Organizational EMC Perspectives, (2) EMI Environment, Case Histories ampersand Solutions, (3) EMC in Digital Instrumentation ampersand Control Systems, and (4) EMI Utility Needs. A group discussion followed the presentations to identify utility needs. Individual papers have been cataloged separately

  1. Computer security of NPP instrumentation and control systems: categorization

    International Nuclear Information System (INIS)

    Klevtsov, A.L.; Simonov, A.A.; Trubchaninov, S.A.

    2016-01-01

    The paper is devoted to studying categorization of NPP instrumentation and control (I&C) systems from the point of view of computer security and to consideration of the computer security levels and zones used by the International Atomic Energy Agency (IAEA). The paper also describes the computer security degrees and zones regulated by the International Electrotechnical Commission (IEC) standard. The computer security categorization of the systems used by the U.S. Nuclear Regulatory Commission (NRC) is presented. The experts analyzed the main differences in I&C systems computer security categorization accepted by the IAEA, IEC and U.S. NRC. The approaches to categorization that should be advisably used in Ukraine during the development of regulation on NPP I&C systems computer security are proposed in the paper

  2. Information needs and instrumentation availability for hydrogen control and management

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Hong [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Park, Gun Chul; Suh, Kune Y.; Lee, Seung Dong; Lee, Jin Yong [Seoul National Univ., Seoul (Korea, Republic of); Jae, Moo Sung [Hansung Univ., Seoul (Korea, Republic of)

    1999-03-15

    This study is concerned with development of comprehensive hydrogen management strategies based on identification of a severe accident condition and formulation of hydrogen models. Reducing containment hydrogen during a severe accident will mitigate a potential containment failure mechanism. One of the hydrogen control strategies is intentional burning by the hydrogen igniter. Though intentional hydrogen burn strategy will cause pressure and temperature spikes, it is the fastest way of reducing the containment hydrogen concentration. Based on the Westinghouse owners group Severe Accident Management Guidance (SAMG) hydrogen ignition decision tree was developed. From the information of decision tree, hydrogen ignition decision can be determined in Containment Event Tree (CET). We have examined previous hydrogen generation related models in fuel coolant interaction (FCI) and developed transient model for it. Using this model, we have simulated the Argonne National Laboratory (ANL) tests which are single droplet experiments, and Fully Instrumented Test Site (FITS) tests which contain dynamic fragmentation.

  3. Femoral Test Bed for Impedance Controlled Surgical Instrumentation

    Directory of Open Access Journals (Sweden)

    Christian Brendle

    2012-01-01

    Full Text Available The risk for patients during the standard procedure of revision of cemented artificial hip joints is unsatisfactorily highdue to its high level of invasiveness and limited access to the operative field. To reduce this risk we are developing anImpedance Controlled Surgical Instrumentation (ICOS system, which aims to establish real-time control during a BoneCement (BC milling process. For this, the relationship between the thickness of the BC and its frequency-dependentelectrical impedance is used to estimate the residual BC thickness. The aim is to avoid unintended cutting of boneby detecting the passage of the BC/bone boundary layer by the milling head. In a second step, an estimation of theresidual BC thickness will be used to improve process control. As a first step towards demonstrating the feasibility ofour approach, presented here are experimental studies to characterize the BC permittivity and to describe the process indetail. The results show that the permittivity properties of BC are dominated by its polymethyl methacrylate (PMMAfraction. Thus, PMMA can be used as a substitute for future experiments. Furthermore, a Femoral Test Bed (FTB wasdesigned. Using this setup we show it is feasible to accurately distinguish between slightly different thicknesses of BC.

  4. Retrofitting the instrumentation and control system of primary cooling circuit from TRIGA INR 14 MW reactor

    International Nuclear Information System (INIS)

    Preda, M.; Ciocanescu, M.; Ana, E. M.; Cristea, D.

    2008-01-01

    Activities of retrofitting the instrumentation and control system from TRIGA INR primary cooling circuit consists in replacement of actual system for: - parameter measurement; - safety; - reactor external scramming; - protection, command and supply for electrical elements of the system. This retrofitting project is designed to ensure the necessary features of reactor external safety and for technological parameter measurement. The new safety system of main cooling circuit is completely separated from its operating system and is arranged in a panel assembly in reactor control room. The operating system has the following features: - data acquisition; - parameter value and state of command elements displaying; - command elements on hierarchical levels; - operator information through visual and acoustic alarm. (authors)

  5. Integration of analog and digital instrumentation and control systems in hybrid control rooms

    International Nuclear Information System (INIS)

    2010-01-01

    he IAEA's activities in the area of nuclear power plant operating performance and life cycle management are aimed at increasing Member State capabilities in utilizing good engineering and management practices as developed and transferred by the IAEA. In particular, the IAEA supports the improvement of nuclear power plant performance, plant life management, training, power uprating, operational license renewal, and the modernization of instrumentation and control (I and C) systems of plants. The issue of the integration of analog and digital I and C systems in hybrid control rooms was suggested by the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) at its meetings in 2003 and 2005. The subject was then approved by the IAEA and included in its work programmes for 2006-2009. The purpose of this report is to help nuclear utilities in planning control room and other human system interface (HSI) changes, making appropriate use of modern technologies. These technologies would aid in managing ageing and obsolescence, and facilitate improvements in plant performance and safety. This report covers a broad spectrum of potential changes to the control room ranging from the replacement of a few obsolete components with newer digital devices to a fully computerized control room. New digital technologies offer significant opportunities to improve access to and presentation of information to the user, e.g. operators, maintenance staff and management. However, this technology should be used prudently. In some cases, modernization is undertaken to resolve ageing and obsolescence or to meet regulatory requirements for license renewal. The integration of new technologies during main control room (MCR) modernizations should be performed cautiously and all affected aspects of plant maintenance, and operation should be carefully considered, paying particular attention to the human factors elements of these aspects. This report describes a

  6. An Investigation of Digital Instrumentation and Control System Failure Modes

    International Nuclear Information System (INIS)

    Korsah, Kofi; Cetiner, Mustafa Sacit; Muhlheim, Michael David; Poore, Willis P. III

    2010-01-01

    A study sponsored by the Nuclear Regulatory Commission study was conducted to investigate digital instrumentation and control (DI and C) systems and module-level failure modes using a number of databases both in the nuclear and non-nuclear industries. The objectives of the study were to obtain relevant operational experience data to identify generic DI and C system failure modes and failure mechanisms, and to obtain generic insights, with the intent of using results to establish a unified framework for categorizing failure modes and mechanisms. Of the seven databases studied, the Equipment Performance Information Exchange database was found to contain the most useful data relevant to the study. Even so, the general lack of quality relative to the objectives of the study did not allow the development of a unified framework for failure modes and mechanisms of nuclear I and C systems. However, an attempt was made to characterize all the failure modes observed (i.e., without regard to the type of I and C equipment under consideration) into common categories. It was found that all the failure modes identified could be characterized as (a) detectable/preventable before failures, (b) age-related failures, (c) random failures, (d) random/sudden failures, or (e) intermittent failures. The percentage of failure modes characterized as (a) was significant, implying that a significant reduction in system failures could be achieved through improved online monitoring, exhaustive testing prior to installation, adequate configuration control or verification and validation, etc.

  7. Speckle interferometry. Data acquisition and control for the SPID instrument.

    Science.gov (United States)

    Altarac, S.; Tallon, M.; Thiebaut, E.; Foy, R.

    1998-08-01

    SPID (SPeckle Imaging by Deconvolution) is a new speckle camera currently under construction at CRAL-Observatoire de Lyon. Its high spectral resolution and high image restoration capabilities open new astrophysical programs. The instrument SPID is composed of four main optical modules which are fully automated and computer controlled by a software written in Tcl/Tk/Tix and C. This software provides an intelligent assistance to the user by choosing observational parameters as a function of atmospheric parameters, computed in real time, and the desired restored image quality. Data acquisition is made by a photon-counting detector (CP40). A VME-based computer under OS9 controls the detector and stocks the data. The intelligent system runs under Linux on a PC. A slave PC under DOS commands the motors. These 3 computers communicate through an Ethernet network. SPID can be considered as a precursor for VLT's (Very Large Telescope, four 8-meter telescopes currently built in Chile by European Southern Observatory) very high spatial resolution camera.

  8. 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)

  9. FINANCIAL INSTRUMENTS OF THE STATE POLICY FOR THE PREVENTION OF TERRORIST ACTS IN UKRAINE

    Directory of Open Access Journals (Sweden)

    Mykola Bunchuk

    2017-11-01

    Full Text Available The article’s objective is to determine the mechanism for implementing the financial instruments of the state policy to counter terrorist acts in the territory not controlled by Ukrainian authorities in Donetsk and Luhansk regions. Methodology. Within the scientific research, for the most effective approaches at the national level to prevent the threat of international terrorism, under the conditions of the deep internal political crisis and extremely difficult economic situation, in order to improve the efficiency of public administration in developing and implementing the anti-terrorism state policies in Ukraine, the paper analyses international and domestic regulations on preventing the terrorist financing, considers factors that affect the deterioration of the social and economic situation of the temporarily occupied parts of Donbas. Results of the research allow formulating the definition of financial instruments of antiterrorist policies, the paper develops and proposes a series of organizational measures in order to prevent the terrorist financing in Ukraine. Practical implications. Based on the above, we propose an option of classification of main illegal mechanisms that may be used to finance terrorist activities in the territories of Donetsk and Luhansk regions uncontrolled by Ukrainian authorities, dividing them into internal and external. Given the above studied factors and classification of financing of terrorist acts in eastern Ukraine, we can assume that for the purpose of evading duty payable to relevant state bodies of Ukraine, external supplies of inventories in the uncontrolled areas of the Donetsk region, which are later obtained by illegal armed groups, are possibly carried out as follows: on behalf of a commercial entity registered in a foreign country for the Ukrainian commercial entity, registered in settlements located in the uncontrolled territory; crossing of international transit traffic that moves through the

  10. 27 CFR 31.46 - Sales by agencies and instrumentalities of the United States.

    Science.gov (United States)

    2010-04-01

    ... United States, including post exchanges, ship's stores, ship's service stores, and commissaries, or any... instrumentality, that sells, or offers for sale, distilled spirits, wines, or beer must comply with the...

  11. Dissemination of Knowledge about NPP Instrumentation and Control Systems

    International Nuclear Information System (INIS)

    Yastrebenetsky, M.

    2016-01-01

    Full text: Instrumentation and control (I&C) systems are the most variable part in the nuclear power plants (NPP) comparatively with any other NPP systems. This statement is connected with the wide use of computers, rapid changes in information technologies, with the appearance of new computer complex electronic components, e.g., field programmable gate arrays (FPGA) and with appropriate point of their insertion into NPP I&C life cycle. The changes in NPP I&C systems require the dissemination of the knowledge about these systems. Lessons after Fukushima accident increase necessity of these actions. The elaboration and following dissemination of this knowledge took place in different directions: • Writing and issue of three new books about NPP I&C systems for specialists and for students which were issued in Ukrainian and USA public houses (the last book was issued in 2014); • Organization of five international scientific technical conferences, devoted to NPP I&C safety problems; • Elaboration of national (Ukrainian) standards and regulations pertaining to safety important NPP I&C systems (the last standard was issued in 2015) and participation in elaboration of international standards; • Lecturing for university students, NPP specialists and I&C designers. These actions in all directions are added to IAEA activity in the area NPP I&C systems (e.g., IAEA NP-T-3.12 “Core Knowledge on I&C systems in NPP”). (author

  12. Instruments for evalutation of altered states of consciousness

    Directory of Open Access Journals (Sweden)

    Matteo Sozzi

    2011-11-01

    Full Text Available In recent years an increase of interest concerning the altered states of consciousness was observed. In particular literature provided a wide amount of contribution about the scales for measurement of level of responsivity. Our aim is to describe the principale scales used in diagnosis of Disorder of Consciousness (DOC trying to illustrate administation procedures, specifically assessed aspects, modality of stimulation, reliability, and validity. We divided them in four main different groups: the first one in which descriptive scales are included, that is those scales basically used after a clinical observation; the second group which concerns scales requiring defined stimulation sets; in the third group we considered the scale which refer to diagnostic criteria stated by the Aspen Work Group (Giacino et al., 2002; whilst in the fourth group we describe a battery aimed to assess patients with severe cognitive deficits which are not yet evaluable with neuropsychological tests.

  13. Research reactor instrumentation and control technology. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-10-01

    The majority of research reactors operating today were put into operation 20 years ago, and some of them underwent modifications, upgrading and refurbishing since their construction to meet the requirements for higher neutron fluxes. However, a few of these ageing research reactors are still operating with their original instrumentation and control systems (I and C) which are important for reactor safety to guard against abnormal occurrences and reactor control involving startup, shutdown and power regulation. Worn and obsolete I and C systems cause operational problems as well as difficulties in obtaining replacement parts. In addition, satisfying the stringent safety conditions laid out by the nuclear regulatory bodies requires the modernization of research reactors I and C systems and integration of additional instrumentation units to the reactor. In order to clarify these issues and to provide some guidance to reactor operators on state-of-art technology and future trends for the I and C systems for research reactors, a Technical Committee Meeting on Technology and Trends for Research Reactor Instrumentation and Controls was held in Ljubljana, Slovenia, from 4 to 8 December 1995. This publication summarizes the discussions and recommendations resulting from that meeting. This is expected to benefit the research reactor operators planning I and C improvements. Refs, figs, tabs

  14. Micro processor based research reactor instrumentation and control system

    International Nuclear Information System (INIS)

    Hyde, W.K.

    1987-01-01

    The system consists of a Control System Computer (CSC) incorporated into a Reactor Control Console (RCC) and a Data Acquisition and Control Unit (DAC) adjacent to the reactor. The CSC has a high resolution color graphics CRT monitor which provides real-time graphic simulation of the reactor and a number of bar graphs displaying strategic parameters of the reactor system. In addition, abnormal or dangerous conditions are displayed. The CSC is equipped with two printers eliminating manual logging of reactor data. The reactor display and pulse mode display may also be printed. Historical data is saved in the system's large capacity memory and may be replayed and/or printed. Because of the CSC's inherent high speed math capability, raw reactor data will be quickly converted and displayed in real-time. Data can be presented in meaningful engineering units. The DAC provides a high speed data acquisition and control capability adjacent to the reactor. It continuously collects data from the reactor system, concentrates the data into a database and transmits it to the CSC when requested. Data transmission is over one of two data trunks to the CSC. The secondary trunk is used if the primary trunk fails. The data trunks drastically reduce the wiring requirements between the reactor and the Control Console. During steady-state operation of the reactor, operator commands to adjust the rod positions is transmitted from the CSC to the DAC which re-issues the commands to the drive mechanisms. In the automatic mode, the DAC will control the position of the rods via a PID algorithm. The system is independently monitored by two or more safety computers. Their function is to monitor the power level, the rate of change of power and fuel temperature of the reactor and to independently shut the reactor down in the event of a potentially dangerous (scram) condition. (author)

  15. Impact of Smoke Exposure on Digital Instrumentation and Control

    International Nuclear Information System (INIS)

    Tanaka, Tina J.; Nowlen, Steven P.; Korsah, Kofi; Wood, Richard T.; Antonescu, Christina E.

    2003-01-01

    Smoke can cause interruptions and upsets in active electronics. Because nuclear power plants are replacing analog with digital instrumentation and control systems, qualification guidelines for new systems are being reviewed for severe environments such as smoke and electromagnetic interference. Active digital systems, individual components, and active circuits have been exposed to smoke in a program sponsored by the U.S. Nuclear Regulatory Commission. The circuits and systems were all monitored during the smoke exposure, indicating any immediate effects of the smoke. The results of previous smoke exposure studies have been reported in various publications. The major immediate effect of smoke has been to increase leakage currents and to cause momentary upsets and failures in digital systems. This paper presents new results from conformal coatings, memory chips, and hard drive tests.The best conformal coatings were found to be polyurethane, parylene, and acrylic (when applied by dipping). Conformal coatings can reduce smoke-induced leakage currents and protect against metal loss through corrosion. However conformal coatings are typically flammable, so they do increase material flammability. Some of the low-voltage biased memory chips failed during a combination of high smoke and high humidity. Typically, smoke along with heat and humidity is expected during fire, rather than smoke alone. Thus, due to high sensitivity of digital circuits to heat and humidity, it is hypothesized that the impact of smoke may be secondary.Low-voltage (3.3-V) static random-access memory (SRAMs) were found to be the most vulnerable to smoke. Higher bias voltages decrease the likelihood of failure. Erasable programmable read-only memory (EPROMs) and nonvolatile SRAMs were very smoke tolerant. Failures of the SRAMs occurred when two conditions were present: high density of smoke and high humidity. As the high humidity was present for only part of the test, the failures were intermittent. All

  16. Instrumentation and Controls Division biennial progress report, September 1, 1976--September 1, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, G.S. (ed.)

    1978-11-01

    Progress is summarized in the following research and development areas: electronic circuits;instruments; radiation monitoring; process systems and instrumentation; thermometry; instrumentation for engineering experiments and test loops; HTGR fuel recycle development; reactor measurements and analysis; automatic control and data acquisition; electronic engineering support for research facilities; miscellaneous engineering services, studies, and developments; maintenance; and environmental science studies.

  17. Instrumentation and Controls Division biennial progress report, September 1, 1976--September 1, 1978

    International Nuclear Information System (INIS)

    Sadowski, G.S.

    1978-11-01

    Progress is summarized in the following research and development areas: electronic circuits;instruments; radiation monitoring; process systems and instrumentation; thermometry; instrumentation for engineering experiments and test loops; HTGR fuel recycle development; reactor measurements and analysis; automatic control and data acquisition; electronic engineering support for research facilities; miscellaneous engineering services, studies, and developments; maintenance; and environmental science studies

  18. Instrumentation and control balancing the risks and benefits of modernization

    International Nuclear Information System (INIS)

    Doshi, P.K.; Rawlins, D.H.; Falascino, J.A.

    1996-01-01

    This paper examines the benefits and risks of modernization of instrumentation and control (I and C) systems for nuclear power plants. It will draw conclusions on how to proceed with such modernization across the spectrum from operating reactors to new plant designs. Lessons learned from Westinghouse's application of digital systems to the Temelin Nuclear Power Plant in the Czech Republic, and other nuclear plant upgrades will be used to support principles and conclusions drawn in the paper. A long term view of the modernization program is essential, even if piecemeal or individual upgrades are envisioned. A framework for considering these risks and goals into a long range strategic plan will be presented. The framework will be presented in the form of I and C architectures which permit long term growth, planning ahead for technological obsolescence, selectron of suppliers for term relationships, and effective integration of individual upgrades. Potential upgrade areas will be summarized for functional improvements, I and C hardware upgrades, and man-machine interface improvements. Examples from Westinghouse's I and C experience will be presented to clarify the principles and framework described in the paper. Lessons learned from the application of the Eagle product line to operating reactors and the emergence of distributed computer information systems as an integration vehicle for I and C upgrades will be discussed. Westinghouse is currently modernizing the Temelin Nuclear Power Plant I and C system in the Czech Republic. An overview of this program will be included as it relates to the modernization framework presented in the paper. (authors)

  19. Future Vision for Instrumentation, Information, and Control Modernization

    International Nuclear Information System (INIS)

    Thomas, Ken D.

    2012-01-01

    A Future Vision of a transformed nuclear plant operating model based on an integrated digital environment has been developed as part of the Advanced Instrumentation, Information, and Control (II and C) research pathway, under the Light Water Reactor (LWR) Sustainability Program. This is a research and development program sponsored by the U.S. Department of Energy (DOE), performed in close collaboration with the nuclear utility industry, to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. II and C has been identified as a potential life-limiting issue for the domestic LWR fleet in addressing the reliability and aging concerns of the legacy systems in service today. The Future Vision is based on a digital architecture that encompasses all aspects of plant operations and support, integrating plant systems, plant work processes, and plant workers in a seamless digital environment to enhance nuclear safety, increase productivity, and improve overall plant performance. Pilot projects are being conducted as the means for industry to gain confidence in these new technologies for use in nuclear plant work activities. The pilot projects introduce new digital technologies into the nuclear plant operating environment at host operating plants to demonstrate and validate them for production usage. In turn, the pilot project technologies serve as the stepping stones to the eventual seamless digital environment as described in the Future Vision. Initial project results confirm that the technologies can provide substantial efficiency and human performance benefits while resolving the reliability and aging concerns of the legacy systems. (author)

  20. Instrumentation and Controls Division annual progress report for period ending September 1, 1973

    International Nuclear Information System (INIS)

    Sadowski, G.S.

    1976-08-01

    Research progress is described under the following topics: (1) pulse counting and analysis; (2) support for the thermonuclear division ORMAK project; (3) miscellaneous electronics development; (4) detectors of ionizing particles and radiation; (5) radiation monitoring; (6) support for the Oak Ridge Electron Linear Accelerator; (7) automatic control and data acquisition; (8) process instrumentation and control; (9) reactor instrumentation and controls; (10) instrumentation for reactor division experiments and test loops; (11) maintenance and service; and (12) ecological science studies

  1. Remote Instrument Control with CIMA Web Services and Web 2.0 Technology

    Directory of Open Access Journals (Sweden)

    Douglas John du Boulay

    2008-02-01

    Full Text Available The Common Instrument Middleware Architecture (CIMA model for Web services based monitoring of remote scientific instruments is being extended and enhanced to provide a capability for remote instrument control. X-ray diffraction has been selected as an ideal domain for prototype development, with the goal being a comprehensive and feature rich portal system for access to remote instruments and their data. The system has two principle components, one of which serves the instrument and data, and the second serves the client user. Plugin modules are used to provide flexibility and re-use, and the notion of plugin control is being developed. The architecture supports remote access to multiple instruments from a single portal. The use of Web 2.0 Pushlet and AJAX technologies has been introduced for push based portlet refresh and updating. An X3D based 3D virtual representation of the instrument provides data collection simulation and (pseudo real time instrument representation.

  2. State-of-the-Art Report on the Piping and Instrumentation Design of RHRS in the Commercial NPPs

    International Nuclear Information System (INIS)

    Lee, Jun; Park, C. T.; Kim, Y. I.; Kim, S. H.; Choi, B. S.; Yoon, Ju Hyeon

    2004-12-01

    The objective of the study is for system designers to understand the technical state of the piping and instrumentation design of RHRS (or SCS) in the commercial nuclear power plants, thus to design more uncomplicated and advanced system. In this study, we have reviewed the design requirements and the technical state of piping and instrumentation design. Firstly we have reviewed the design requirements, including functional, isolation, pressure relief, pump protection, test requirements, etc.. Especially we have separately reviewed the design requirements of the low temperature overpressure, including ASME code requirements. Also we have reviewed the technical state of piping and instrumentation design, including piping design, PAMS design, ESFAS design, relief valve design, and instrument/valve/pump control design. In the piping design, the technical state of design has been investigated classified by the five regions, which have a little different design features, from the RCS suction line to the LPSI header line. Commonly, the P and ID is the design output which the related design requirements of the system have been all applied, also the operations for in-service inspection, heat-up/normal/cool-down, and emergency have been all considered. If we can understand well the design bases and its meanings of the P and ID, it would be helpful for us to design more uncomplicated and advanced system

  3. Instrumentation and Controls Division biennial progress report, September 1, 1978-September 1, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, G.S. (comp.)

    1981-06-01

    Brief summaries of research work are presented in the following section: overview of the ORNL Instrumentation and Controls Division activities; new developments and methods; reactor instrumentation and controls; measurement and control engineering; electronic engineering; maintenance; studies; services; and development; and division achievements.

  4. Instrumentation and Controls Division biennial progress report, September 1, 1978-September 1, 1980

    International Nuclear Information System (INIS)

    Sadowski, G.S.

    1981-06-01

    Brief summaries of research work are presented in the following section: overview of the ORNL Instrumentation and Controls Division activities; new developments and methods; reactor instrumentation and controls; measurement and control engineering; electronic engineering; maintenance; studies; services; and development; and division achievements

  5. The Los Alamos accelerator control system data base: A generic instrumentation interface

    International Nuclear Information System (INIS)

    Dalesio, L.R.

    1990-01-01

    Controlling experimental-physics applications requires a control system that can be quickly integrated and easily modified. One aspect of the control system is the interface to the instrumentation. An instrumentation set has been chosen to implement the basic functions needed to monitor and control these applications. A data-driven interface to this instrumentation set provides the required quick integration of the control system. This type of interface is limited by its built-in capabilities. Therefore, these capabilities must provide an adequate range of functions to be of any use. The data-driven interface must support the instrumentation range requird, the events on which to read or control the instrumentation and a method for manipulating the data to calculate terms or close control loops. The database for the Los Alamos Accelerator Control System addresses these requirements. (orig.)

  6. Artificial intelligence programming with LabVIEW: genetic algorithms for instrumentation control and optimization.

    Science.gov (United States)

    Moore, J H

    1995-06-01

    A genetic algorithm for instrumentation control and optimization was developed using the LabVIEW graphical programming environment. The usefulness of this methodology for the optimization of a closed loop control instrument is demonstrated with minimal complexity and the programming is presented in detail to facilitate its adaptation to other LabVIEW applications. Closed loop control instruments have variety of applications in the biomedical sciences including the regulation of physiological processes such as blood pressure. The program presented here should provide a useful starting point for those wishing to incorporate genetic algorithm approaches to LabVIEW mediated optimization of closed loop control instruments.

  7. Account of requirements for modernization in VPBER-600 enhanced safety reactor instrumentation and control system development

    International Nuclear Information System (INIS)

    Shashkin, S.L.; Pobedonostsev, A.B.; Drumov, V.V.; Chudin, A.G.

    1993-01-01

    Nuclear power plant (NPP) with VPBER-600 reactor is a station of new generation. The specified term of reactor plant operation is 60 years and taking into account that the proposed term of starting the first power unit is on the turn of centuries one can definitely state that for Russia conditions VPBER-600 is a plant of 21 century. Such far removed term for NPP now in the stage of development as it can seem does not put the problems of modernization as first order tasks. But open-quotes...who does not think about future lives in the past.close quotes It is that the NPP instrumentation and control (I ampersand C) systems are in the most degree subjected to the influence of factors which favor their modifications. These factors can be arbitrarily divided into two groups: (1) inner factors, i.e. changes (failures, aging, etc) in I ampersand C components as well as changes dictated by technological reasons (change of equipment composition, control algorithms, operation modes); (2) outer factors, i.e. intensive development of information technologies and rapid improvement of electronic components. This presentation addresses the problem of modernization of the safety instrumentation for this next generation facility, and the research effort it will entail. The system is designed to allow for modernization, and the relatively easy adoption of new instrumentation and technology as it becomes available

  8. Geodetic Control Points - Multi-State Control Point Database

    Data.gov (United States)

    NSGIC State | GIS Inventory — The Multi-State Control Point Database (MCPD) is a database of geodetic and mapping control covering Idaho and Montana. The control were submitted by registered land...

  9. Developing and testing a positive theory of instrument choice: Renewable energy policy in the fifty American states

    Science.gov (United States)

    Ciocirlan, Cristina E.

    The environmental economics literature consistently suggests that properly designed and implemented economic incentives are superior to command-and-control regulation in reducing pollution. Economic incentives, such as green taxes, cap-and-trade programs, tax incentives, are able to reduce pollution in a cost-effective manner, provide flexibility to industry and stimulate innovation in cleaner technologies. In the past few decades, both federal and state governments have shown increased use of economic incentives in environmental policy. Some states have embraced them in an active manner, while others have failed to do so. This research uses a three-step analysis. First, it asks why some states employ more economic incentives than others to stimulate consumption of renewable energy by the residential, commercial and industrial sectors. Second, it asks why some states employ stronger incentives than others. And third, it asks why certain states employ certain instruments, such as electricity surcharges, cap-and-trade programs, tax incentives or grants, while others do not. The first two analyses were conducted using factor analysis and multiple regression analysis, while the third analysis employed logistic regression models to analyze the data. Data for all three analyses were obtained from a combination of primary and secondary sources. To address these questions, a theory of instrument choice at the state level, which includes both internal and external determinants of policy-making, was developed and tested. The state level of analysis was chosen. States have proven to be pioneers in designing policies to address greenhouse gases (see, for instance, the recent cap-and-trade legislation passed in California). The theory was operationalized with the help of four models: needs/responsiveness, interest group influence, professionalism/capacity and innovation-and-diffusion. The needs/responsiveness model suggests that states tend to choose more and stronger economic

  10. 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

  11. 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

  12. CRDIAC: Coupled Reactor Depletion Instrument with Automated Control

    International Nuclear Information System (INIS)

    Logan, Steven K.

    2012-01-01

    When modeling the behavior of a nuclear reactor over time, it is important to understand how the isotopes in the reactor will change, or transmute, over that time. This is especially important in the reactor fuel itself. Many nuclear physics modeling codes model how particles interact in the system, but do not model this over time. Thus, another code is used in conjunction with the nuclear physics code to accomplish this. In our code, Monte Carlo N-Particle (MCNP) codes and the Multi Reactor Transmutation Analysis Utility (MRTAU) were chosen as the codes to use. In this way, MCNP would produce the reaction rates in the different isotopes present and MRTAU would use cross sections generated from these reaction rates to determine how the mass of each isotope is lost or gained. Between these two codes, the information must be altered and edited for use. For this, a Python 2.7 script was developed to aid the user in getting the information in the correct forms. This newly developed methodology was called the Coupled Reactor Depletion Instrument with Automated Controls (CRDIAC). As is the case in any newly developed methodology for modeling of physical phenomena, CRDIAC needed to be verified against similar methodology and validated against data taken from an experiment, in our case AFIP-3. AFIP-3 was a reduced enrichment plate type fuel tested in the ATR. We verified our methodology against the MCNP Coupled with ORIGEN2 (MCWO) method and validated our work against the Post Irradiation Examination (PIE) data. When compared to MCWO, the difference in concentration of U-235 throughout Cycle 144A was about 1%. When compared to the PIE data, the average bias for end of life U-235 concentration was about 2%. These results from CRDIAC therefore agree with the MCWO and PIE data, validating and verifying CRDIAC. CRDIAC provides an alternative to using ORIGEN-based methodology, which is useful because CRDIAC's depletion code, MRTAU, uses every available isotope in its depletion

  13. Optimal design of tweezer control for chimera states

    Science.gov (United States)

    Omelchenko, Iryna; Omel'chenko, Oleh E.; Zakharova, Anna; Schöll, Eckehard

    2018-01-01

    Chimera states are complex spatio-temporal patterns which consist of coexisting domains of spatially coherent and incoherent dynamics in systems of coupled oscillators. In small networks, chimera states usually exhibit short lifetimes and erratic drifting of the spatial position of the incoherent domain. A tweezer feedback control scheme can stabilize and fix the position of chimera states. We analyze the action of the tweezer control in small nonlocally coupled networks of Van der Pol and FitzHugh-Nagumo oscillators, and determine the ranges of optimal control parameters. We demonstrate that the tweezer control scheme allows for stabilization of chimera states with different shapes, and can be used as an instrument for controlling the coherent domains size, as well as the maximum average frequency difference of the oscillators.

  14. A Wearable Foot-mounted / Instrument-mounted Effect Controller

    DEFF Research Database (Denmark)

    Konovalovs, Kristians; Zovnercuka, Jelizaveta; Adjorlu, Ali

    2017-01-01

    . The classic foot activated effect pedals that are used to alter the sound of the instrument are stationary, forcing the performer to return to the same location in order to interact with the pedals. This paper presents a new design that enables the performer to interact with the effect pedals anywhere...

  15. Policy instruments for pollution control in developing countries.

    Science.gov (United States)

    Eskeland, G S; Jimenez, E

    1992-07-01

    Economic development in developing countries must be accomplished in a manner that does not harm the environment with pollution. Pollution harms human health and productivity. Thus appropriate strategies must be developed that promote growth, reduce poverty, and protect the environment. A review of the current literature is performed with attention paid to cost-effective interventions i.e., comparisons of regulatory and fiscal instruments that can reduce pollution. Both direct instruments (like effluent charges, tradable permits, deposit refund systems, emission regulations and regulatory agency funding for purification, cleanup, waste disposal, and enforcement) and indirect instruments (like input/output taxes and subsidies, substitution subsidies, abatement inputs, regulation of equipment and processes, and development of clean technologies) are examined. Examples are used to show how indirect instruments can be successful when monitoring and enforcement is too costly. A careful examination of distributive concerns illustrate how the effect on the poor may need particular consideration and how groups with vested interests can help evaluate the probable success of such interventions.

  16. Manual Control for Medical Instruments in Minimally Invasive Surgery

    NARCIS (Netherlands)

    Fan, C.

    2014-01-01

    With the introduction of new technologies, surgical procedures have been varying from free access in open surgery towards limited access in minimal invasive surgery. During such procedures, surgeons have to manoeuver the instruments from outside the patient while looking at the monitor. Long and

  17. New generation in process-control colorimetric instrumentation

    Science.gov (United States)

    Ladson, Jack A.

    1992-08-01

    Colorimetric performance parameters (repeatability and reproducibility) of a new spectrophotometer/colorimeter manufactured by BYK-Gardner, Inc. are reported. The color- viewTM spectrophotometer (CVS) uses forty-five degree illumination and zero degree viewing geometry relative to the plane of the test specimen. The CVS is designed for the measurement of diffuse reflectance factor. It is designed to conform to national and international recommendations for Spectrophotometry and Colorimetry. Colorimetric performance was evaluated by measuring colored tiles manufactured by the British Ceramic Research Association (BCRA). Instrument repeatability was recorded after an hour, eight hours, and thirty days. Routine performance of the CVS shows that color difference repeatability over short and medium time periods is within 0.15 CIELAB color difference unit. The long term repeatability is within 0.4 unit. Reproducibility was evaluated by making color measurements on BCRA tiles with 54 instruments. Measurements made on CVS instruments indicate that its reproducibility is better than the reproducibility of product standards. Reproducibility is well within the requirement for industrial applications. Actually, the repeatability and reproducibility is comparable to that of reference instruments in national standardizing laboratories.

  18. Instrumentation utilisation for risk control in safety operations. [balloons and rockets

    Science.gov (United States)

    Swayer, F. R.

    1987-01-01

    Ways in which instrumentation is utilized for risk control for inherently safe (no control or guidance) and flight programmed launch vehicles is presented. Instrumentation and how it is utilized in the launching and recovery of balloons and payloads is also presented. Wind sensing, computer systems, tracking, and telemetry are discussed.

  19. 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

  20. Project W-314 DST and DCRT instrument and control systems, initial assessment

    International Nuclear Information System (INIS)

    Acree, C.D.

    1996-01-01

    This report contains an assessment of the instrument and control systems in the Double Shell Tank Farms and the 244-A DCRT. The assessment report contains data from physical inspection activities and an overall engineering assessment of the instruments and control systems in use in the Double Shell Tanks

  1. Implementation of a communication and control network for the instruments of a nuclear analytical laboratory

    International Nuclear Information System (INIS)

    Cunya, Eduardo; Baltuano, Oscar; Bedregal, Patricia

    2013-01-01

    This paper describes the implementation of a communication network and control for a conventional laboratory instruments and nuclear analytical processes based on CAN open field bus to control devices and machines. Hardware components and software developed as well as installation and configuration tools for incorporating new instruments to the network re presented. (authors).

  2. Operating experience with LAMPF main beam lines instrumentation and control system

    International Nuclear Information System (INIS)

    van Dyck, O.B.; Harvey, A.; Howard, H.H.; Roeder, D.L.

    1975-01-01

    Instrumentation and control (I and C) for the Los Alamos Clinton P. Anderson Meson Physics Facility (LAMPF) main beam line is based upon central computer control through remote stations which provide input and output to most devices. Operating experience shows that the ability of the computer to give high-quality graphical presentation of the measurements enhances operator performance and instrument usefulness. Experience also shows that operator efficiency degrades rapidly with increasing instrument response time, that is, with increasing delay between the time a control is changed and the result can be observed. For this reason, instrumentation upgrade includes speeding up data acquisition and display times to under 10 s. Similarly, television-viewed phosphors are being retained where possible since their instantaneous response is very useful. Other upgrading of the instrumentation system is planned to improve data accuracy, reliability, redundancy, and instrument radiation tolerance. Past experience is being applied in adding or relocating devices to simplify tuning procedures. (U.S.)

  3. PLC and DTAM Software Programs for Pumping Instrumentation and Control Skid ''M''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This document describes the software programs for the Programmable Logic Controller and the Data Table Access Module for Pumping Instrumentation and Control skid ''M''. The Appendices contains copies of the printouts of these software programs

  4. PLC and DTAM Software Programs for Pumping Instrumentation and Control Skid P

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This document describe the software programs for the Programmable Logic Controller and the Datable Access Module for Pumping Instrumentation and Control skid ''P''. The Appendices contains copies of the printouts of these software programs

  5. PLC and DTAM Software Programs for Pumping Instrumentation and Control Skid M

    Energy Technology Data Exchange (ETDEWEB)

    KOCH, M.R.

    2000-02-14

    This document describes the software programs for the Programmable Logic Controller and the Data Table Access Module for Pumping Instrumentation and Control skid ''M''. The Appendices contains copies of the printouts of these software programs.

  6. PLC/DTAM Software Programs for Pumping Instrumentation and Control Skid L

    Energy Technology Data Exchange (ETDEWEB)

    KOCH, M.R.

    2000-01-03

    This document describes the software programs for the Programmable Logic Controller and the Data Table Access Module for Pumping Instrumentation and Control skid ''L''. The Appendices contains copies of the printouts of these software programs.

  7. PLC/DTAM Software Programs for Pumping Instrumentation and Control Skid ''L''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This document describes the software programs for the Programmable Logic Controller and the Data Table Access Module for Pumping Instrumentation and Control skid ''L''. The Appendices contains copies of the printouts of these software programs

  8. An instrument control and data analysis program for imaging and in vivo spectroscopy

    International Nuclear Information System (INIS)

    Roos, M.S.; Mushlin, R.A.; Veklerov, E.; Port, J.D.; Ladd, C.; Harrison, C.G.

    1987-01-01

    The spectrometer control data processing environment and the libraries of macros designed are used to support imaging and in vivo spectroscopy at the Lawrence Berkeley Laboratory, the Massachusetts Institute of Technology, and the Brigham and Women's Hospital in systems ranging from a 2-T animal spectrometer to a 0.5-T whole body imager. Experiments that have been successfully implemented include multi-slice, multi-echo imaging fast steady state free precession imaging and 31 P spectroscopy. The flexibility of the macro programming structure allowed very rapid development of these macro libraries. We have demonstrated that instrumentation developed around standard hosts, buses, and operating systems can yield research tools with performance comparable to highly specialized systems. The combination of low macro instruction overhead, provision of user access to system internals, and a rich command set controlling basic acquisition and processing functions provides a foundation on which libraries of macros may be built to serve a broad range of users, perhaps more easily than a system with larger sets of less primitive commands and a more limited batch processor. Well defined program interfaces for macros and for installing commands, as well as the ability to modify instrument control code significantly broaden the range of experiments accessible to the researcher

  9. Association between tinnitus retraining therapy and a tinnitus control instrument.

    Science.gov (United States)

    Ito, Mari; Soma, Keiko; Ando, Reiko

    2009-10-01

    Tinnitus retraining therapy (TRT), which is an adaptation therapy for tinnitus based on the neurophysiological model proposed by Jastreboff in 1990,consists of directive counseling and acoustic therapy with a tinnitus control instrument (TCI) or other devices. For the past 5 years, our hospital has administered TRT characterized by the use of a TCI. In this study, we reviewed the clinical course of patients with tinnitus who presented to our outpatient clinic for tinnitus and hearing loss during the 3-year period from April 2004 to March 2007 and underwent TRT with a TCI. Among 188 patients with tinnitus (105 males and 83 females), 88 patients (51 males and 37 females, excluding dropouts) who purchased a TCI and continued therapy were included in the study. Significant improvement in Tinnitus Handicap Inventory (THI) and Visual Analogue Scale (VAS) scores was found as early as 1 month of treatment and later compared with those on initial examination, suggesting that TRT with a TCI may be an effective treatment for tinnitus. Among the noises generated by the TCI, the sound pressure output from the TCI was set at just below tinnitus loudness level both of the first adjustment and the second adjustment. Speech noise and white noise were frequently selected, whereas high-frequency noise and pink noise were infrequently selected. Speech noise was most frequently selected at the first adjustment, and the number of patients selecting white noise increased at the second adjustment. The results that we compared the two also revealed that the mean hearing level and tinnitus loudness levels were higher in the white noise group than in the speech noise group, which suggested that the inner ear disorder was more harder in the white noise group. Both the THI score and VAS grade improved after 1 month of treatment in the speech noise group, whereas improvement in these parameters was observed in the white noise group after 6 months of treatment. These results suggest that it took

  10. Ultrasound Instrumentation for Beam Diagnostics and Accelerating Structures Control

    CERN Document Server

    Moiseev, V I

    2005-01-01

    Sensitive elements and electronics for ultrasound measurements at conducting walls of beam pipes and accelerating structures are described. Noise protected instrumentation provides ultrasound spectra analysis in a wide frequency range up to 5 MHz.In circular accelerators, ultrasound fields in conducting walls of beam pipe represent the space-time characteristics of circulating beams. In accelerating structures, real high power operation modes of structure can be studied by outer ultrasound monitors. The experimental results at KSRS accelerators are discussed.

  11. Control device intended for a gamma radiation measuring instrument

    International Nuclear Information System (INIS)

    1976-01-01

    This invention concerns a monitoring device for a gamma radiation measuring instrument or radiation meter, in which the radiation to be measured brings about, inter alia, the ionisation of a gas and the generation of current pulses. The dial of this meter is generally calibrated in roentgens per hour, i.e. in radiation rate units. This instrument of very simple design is remarkable for its operating reliability. Preferably placed at the inlet to a radioactive area, it enables every user of a ratemeter to check, over the entire measuring range of this instrument, its proper operation prior to entering the area. To this effect, the monitoring device in question has a thick wall lead castle, having an internal cavity in which is mounted a radioactive source delivering a gamma radiation with given constant characteristics, through a measurement window closed by a calibrated plug. Lead doors articulated on the castle can be superimposed on this window to bring about a given attenuation of the radiation coming from the source and delivered to the exterior of the castle [fr

  12. Solid state controller three axes controller

    Science.gov (United States)

    Bailey, C. L., Jr. (Inventor)

    1973-01-01

    The reported flight controller features a handle grip which is mounted on a longitudinally extending control element. The handle grip is pivotally mounted on the control element about a pitch axis which is perpendicular to the longitudinal axis through the control element. The pivotal mounting includes a resilient force mounting mechanism which centers the grip relative to the control element. Rotation of the handle grip produces a direct rotation of a transducer element in a transducer which provides an electrical indication of the rotative movement about three mutually perpendicular axes.

  13. The development of state/region owned goods management’s monitoring instrument design

    Directory of Open Access Journals (Sweden)

    Ikhwanto Yogy

    2017-01-01

    Full Text Available The problems in state/region owned goods in Indonesian state and local governments are suspected to occur because of weak monitoring programs, according to many studies. A tool or instrument in implementing this monitoring program is expected to address this problem. Such tool currently doesn’t exist yet. This research aims to fill that gap by developing a monitoring instrument design for state/region owned goods by using Daerah Istimewa Yogyakarta (DIY Local Government as a research context in order to take valuable inputs for the design. This research is using developmental research method. Government Regulation were used for normative reference and Friedman’s results-based accountability quadrat were used in developing good indicators for the instrument. This research is succeeded in formulating the indicators that made up the instrument. Indicators compiled are divided into compliance-based indicators and results-based indicators. Indicators are formulated based on the validation and inputs from employees of DIY’s Assets Management Agency and experts from academia. This instrument still has some limitations that need improvement through further research.

  14. Evaluation of the Primary Care in leprosy control: proposal of an instrument for users

    Directory of Open Access Journals (Sweden)

    Fernanda Moura Lanza

    2014-12-01

    Full Text Available Objective Developing an instrument to evaluate the performance of primary health care in the leprosy control actions, from the perspective of users and do the face and content validation. Method This is a methodological study carried out in four stages: development of instrument, face and content validation, pre-test, and analysis of test-retest reliability. Results The initial instrument submitted to the judgment of 15 experts was composed of 157 items. The face and content validation and pre-test of instrument were essential for the exclusion of items and adjustment of instrument to evaluate the object under study. In the analysis of test-retest reliability, the instrument proved to be reliable. Conclusion The instrument is considered adequate, but further studies are needed to test the psychometric properties.

  15. Instrumentation and control for reactor power setback in PFBR

    International Nuclear Information System (INIS)

    Upadhyay, Chandra Kant; Vasal, Tanmay; Nagaraj, C.P.; Madhusoodanan, K.

    2013-01-01

    In Prototype Fast Breeder Reactor (PFBR), a 500 MWe plant, Reactor Power Setback is a special operation envisaged for bulk power reduction on occurrence of certain events in Balance of Plant. The bulk power reduction requires a large negative reactivity perturbation if reactor is operating on nominal power. This necessitates a reliable monitoring system with fault tolerant I and C architecture in order to inhibit reactor SCRAM on negative reactivity trip signal. The impact of above events on the process is described. Design of a functional prototype module to carry out RPSB logic operation and its interface with other instruments has been discussed. (author)

  16. Specification of requirements for upgrades using digital instrument and control systems. Report prepared within the framework of the international working group on nuclear power plant control and instrumentation

    International Nuclear Information System (INIS)

    1999-01-01

    The need to develop good specifications of requirements for instrument and control (I and C) systems applies throughout the world and is becoming more and more important as more upgrades are planned. Better guidance on how to develop good requirements specifications would support safer, more effective and more economical refits and upgrades. The need for this was pointed out by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). This report is the result of a series of advisory and consultants meetings held by the IAEA in 1997 and 1998 in Vienna. The scope of the activities described covers a methodology for the determination of requirements and the development of the necessary specifications and plans needed through the life-cycle of digital instrumentation and control systems. It is restricted to technical aspects and indicates subjects which should be included in specifications and plans at different phases

  17. Instrumentation Standard Architectures for Future High Availability Control Systems

    International Nuclear Information System (INIS)

    Larsen, R.S.

    2005-01-01

    Architectures for next-generation modular instrumentation standards should aim to meet a requirement of High Availability, or robustness against system failure. This is particularly important for experiments both large and small mounted on production accelerators and light sources. New standards should be based on architectures that (1) are modular in both hardware and software for ease in repair and upgrade; (2) include inherent redundancy at internal module, module assembly and system levels; (3) include modern high speed serial inter-module communications with robust noise-immune protocols; and (4) include highly intelligent diagnostics and board-management subsystems that can predict impending failure and invoke evasive strategies. The simple design principles lead to fail-soft systems that can be applied to any type of electronics system, from modular instruments to large power supplies to pulsed power modulators to entire accelerator systems. The existing standards in use are briefly reviewed and compared against a new commercial standard which suggests a powerful model for future laboratory standard developments. The past successes of undertaking such projects through inter-laboratory engineering-physics collaborations will be briefly summarized

  18. Roadmap for Research, Development, and Demonstration of Instrumentation, Controls, and Human-Machine Interface Technologies

    International Nuclear Information System (INIS)

    Miller, Don W.; Arndt, Steven A.; Bond, Leonard J.; Dudenhoeffer, Donald D.; Hallbert, Bruce P.; Holcomb, David E.; Wood, Richard T.; Naser, Joseph A.; O'Hara, John M.; Quinn, Edward L.

    2008-01-01

    Instrumentation, controls, and human-machine interfaces are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The nuclear power industry is currently engaged in a transition from traditional analog-based instrumentation, controls, and human-machine interface (ICHMI) systems to implementations employing digital technologies. This transition has primarily occurred in an ad hoc fashion through individual system upgrades at existing plants and has been constrained by a number of concerns. Although international implementation of evolutionary nuclear power plants and the progression toward new plants in the United States have spurred design of more fully digital plant-wide ICHMI systems, the experience base in the nuclear power application domain is limited. Additionally, design and development programs by the U.S. Department of Energy (DOE) for advanced reactor concepts, such as the Generation IV Program and Next Generation Nuclear Plant (NGNP), introduce different plant conditions and unique plant configurations that increase the need for enhanced ICHMI capabilities to fully achieve programmatic goals related to economic competitiveness, safety and reliability, sustainability, and proliferation resistance and physical protection. As a result, there are challenges that need to be addressed to enable the nuclear power industry to effectively and efficiently complete the transition to safe and comprehensive use of digital technology

  19. Modernization of the CDTN IPR-R1 TRIGA reactor instrumentation and control

    International Nuclear Information System (INIS)

    Mesquita, A.Z.; Costa, A.C.L.; Souza, R.M.G.P.

    2009-01-01

    The control system of the IPR-R1 was changed in 1995. Although since the year's 80 was generalized the use of microprocessor technology and video monitors for visual interface, in the IPR-R1 control room it was used analogical system by relay-based logic, and were maintained the mechanical strip chart recorders (ink-pen drive) to measure, monitor and store the operational parameters. It was maintained the measure and the control of, practically, the same variables of the original system, although the reactor power already have been upgraded to 100 kW and began the studies to increase it to 250 kW, which is the current core configuration. For 250 kW operations the fuel heat transfer becomes important and new parameters should be used as safety operational limits. A state-of-the-art instrumentation and control system using microprocessor technology is proposed to replace the present analogical systems. The new system can eliminates most manual data logging, provides automatic or manual reactor operation modes, provides complete real-time operator display, replays historical operating data on monitor or printer, eliminates spare parts replacement problems and meets all applicable international standards as NRC and IEE specifications. This paper describes the research project in process in CDTN that has as objective the modernization of the IPR-R1 TRIGA reactor instrumentation and control of the operational variables. The project also will improve the accomplishment of neutronic and thermal-hydraulic experiments, foreseen in the CDTN research program. (author)

  20. Unidirectional Quantum Remote Control:Teleportation of Control-State

    Institute of Scientific and Technical Information of China (English)

    ZHENG Yi-Zhuang; GU Yong-Jian; WU Gui-Chu; GUO Guang-Can

    2003-01-01

    We investigate the problem of teleportation of unitary operations by unidirectional control-state telepor-tation and propose a scheme called unidirectional quantum remote control. The scheme is based on the isomorphismbetween operation and state. It allows us to store a unitary operation in a control state, thereby teleportation of theunitary operation can be implemented by unidirectional teleportation of the control-state. We find that the probabilityof success for implementing an arbitrary unitary operation on arbitrary M-qubit state by unidirectional control-stateteleportation is 4-M, and 2M ebits and 4M cbits are consumed in each teleportation.

  1. Discriminative stimuli that control instrumental tobacco-seeking by human smokers also command selective attention.

    Science.gov (United States)

    Hogarth, Lee; Dickinson, Anthony; Duka, Theodora

    2003-08-01

    Incentive salience theory states that acquired bias in selective attention for stimuli associated with tobacco-smoke reinforcement controls the selective performance of tobacco-seeking and tobacco-taking behaviour. To support this theory, we assessed whether a stimulus that had acquired control of a tobacco-seeking response in a discrimination procedure would command the focus of visual attention in a subsequent test phase. Smokers received discrimination training in which an instrumental key-press response was followed by tobacco-smoke reinforcement when one visual discriminative stimulus (S+) was present, but not when another stimulus (S-) was present. The skin conductance response to the S+ and S- assessed whether Pavlovian conditioning to the S+ had taken place. In a subsequent test phase, the S+ and S- were presented in the dot-probe task and the allocation of the focus of visual attention to these stimuli was measured. Participants learned to perform the instrumental tobacco-seeking response selectively in the presence of the S+ relative to the S-, and showed a greater skin conductance response to the S+ than the S-. In the subsequent test phase, participants allocated the focus of visual attention to the S+ in preference to the S-. Correlation analysis revealed that the visual attentional bias for the S+ was positively associated with the number of times the S+ had been paired with tobacco-smoke in training, the skin conductance response to the S+ and with subjective craving to smoke. Furthermore, increased exposure to tobacco-smoke in the natural environment was associated with reduced discrimination learning. These data demonstrate that discriminative stimuli that signal that tobacco-smoke reinforcement is available acquire the capacity to command selective attentional and elicit instrumental tobacco-seeking behaviour.

  2. Proceedings of the International topical meeting on VVER instrumentation and control

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    The Proceedings contain the full texts of 44 contributions, out of which 42 have been input to INIS. The papers cover various aspects of WWER instrumentation and control including reactor upgrading and modernization, testing and refurbishment of instrumentation, and operational experience and problems. (A.K.).

  3. Proceedings of the 1978 symposium on instrumentation and control for fossil demonstration plants

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The 1978 symposium on instrumentation and control for fossil demonstration plants was held at Newport Beach, California, June 19--21, 1978. It was sponsored by Argonne National Laboratory, the U.S. Department of Energy - Fossil Energy, and the Instrument Society of America - Orange County Section. Thirty-nine papers have been entered individually into the data base. (LTN)

  4. Proceedings of the International topical meeting on VVER instrumentation and control

    International Nuclear Information System (INIS)

    1997-11-01

    The Proceedings contain the full texts of 44 contributions, out of which 42 have been input to INIS. The papers cover various aspects of WWER instrumentation and control including reactor upgrading and modernization, testing and refurbishment of instrumentation, and operational experience and problems. (A.K.)

  5. Mobile source pollution control in the United States and China

    International Nuclear Information System (INIS)

    Menz, Fredric C

    2002-01-01

    This paper reviews policies for the control of mobile source pollution and their potential application in China. The first section of the paper reviews the U.S. experience with mobile source pollution control since regulations were first established in the Clean Air Act of 1970. Highlights in the policy and trends in vehicle emissions over the 1970 to 2000 time period are discussed. The second section of the paper discusses the range of policy instruments that could be used to control vehicle pollution, ranging from traditional direct regulations to market-based instruments. Experiences with the use of economic incentives in the United States and elsewhere are also discussed. The third section of the paper discusses possible implications of the U.S. experience for controlling vehicle pollution in China. While market-based instruments might be particularly appropriate for use in several aspects of China's pollution control policies, important differences between the institutional structures in China and the United States suggest that they should be phased in gradually. The paper closes with concluding remarks. (author)

  6. Mobile source pollution control in the United States and China

    Energy Technology Data Exchange (ETDEWEB)

    Menz, Fredric C

    2002-07-01

    This paper reviews policies for the control of mobile source pollution and their potential application in China. The first section of the paper reviews the U.S. experience with mobile source pollution control since regulations were first established in the Clean Air Act of 1970. Highlights in the policy and trends in vehicle emissions over the 1970 to 2000 time period are discussed. The second section of the paper discusses the range of policy instruments that could be used to control vehicle pollution, ranging from traditional direct regulations to market-based instruments. Experiences with the use of economic incentives in the United States and elsewhere are also discussed. The third section of the paper discusses possible implications of the U.S. experience for controlling vehicle pollution in China. While market-based instruments might be particularly appropriate for use in several aspects of China's pollution control policies, important differences between the institutional structures in China and the United States suggest that they should be phased in gradually. The paper closes with concluding remarks. (author)

  7. 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)

  8. 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

  9. Instrumentation and Controls Division biennial progress report, September 1, 1974--September 1, 1976. Non-LMFBR programs

    International Nuclear Information System (INIS)

    Sadowski, G.S.

    1976-11-01

    Research progress and developments are reported in the areas of basic electronics, instruments, radiation monitoring, pulse counting and analysis, electronic engineering support for research facilities, automatic control and data acquisition, reactor instrumentation and controls, fuel reprocessing and shipping, process systems and instrumentation development, thermometry, instrumentation for reactor division experiments and test loops, environmental science studies, miscellaneous engineering studies, services, and developments, and maintenance

  10. Instrumentation, control and automation in wastewater - from London 1973 to Narbonne 2013

    DEFF Research Database (Denmark)

    Olsson, G.; Carlsson, B.; Comas, J.

    2014-01-01

    , instrumentation, computer systems and control theory. However, many developments have not been addressed here, such as sewer control, drinking water treatment and water distribution control. It is hoped that this review can stimulate new attempts to more effectively apply control and automation in water systems...

  11. The digital reactor protection system for the instrumentation and control of reactor TRIGA PUSPATI (RTP)

    International Nuclear Information System (INIS)

    Nurfarhana Ayuni Joha; Izhar Abu Hussin; Mohd Idris Taib; Zareen Khan Abdul Jalil Khan

    2010-01-01

    Reactor Protection System (RPS) is important for Reactor Instrumentation and Control System. The RPS comprises all redundant electrical devices and circuitry involved in the generation of those initiating signals associated to the trip protective function. The instrumentation system for the RPS provides automatic protection signals against unsafe and improper reactor operation. The physical separation is provided for all of the redundant instrumentation systems to preserve redundancy. The safety protection systems using circuits composed of analog instruments and relays with relay contacts is difficult to realize from various reasons. Therefore, an application of digital technology can be said a logical conclusion also in the light of its functional superiority. (author)

  12. National phantoms bank for the service of nuclear medicine in Cuba. Utility for the quality control of the instrumentation

    International Nuclear Information System (INIS)

    Varela C, C.; Diaz B, M.; Lopez B, G.M.

    2006-01-01

    Although, most of the applications in Nuclear Medicine have diagnostic ends, its going enlarging considerably the therapeutic applications. So that the diagnostic accuracy or the therapy effectiveness have not been affected, it becomes indispensable the quality control of the instrumentation, independently of its technological complexity and/or its exploitation period. Before the real lack of phantoms in the institutions, it was created a bank that puts to disposition of all the institutions, the existent phantoms in the country, and those that are going acquired, centralized by the State Control of Medical Equipment Center (CCEEM) and with Web access in its place www.eqmed.sld.cu. Having like base the elaboration of the National Protocol for the Quality Control of the Instrumentation in Nuclear Medicine that keeps in mind the international normative and the own existent conditions, were dictated and established two national regulations and its are being carried out the first audits to the instrumentation quality. These have evidenced the partial realization of the established quality controls in the services, the necessity to make aware as for the fulfillment of the criteria and quality concepts for the instrumentation, as well as the necessity to increase the phantoms number to the bank to guarantee the fulfillment of the Quality Control Programs. (Author)

  13. 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.)

  14. Meteorological Support Interface Control Working Group (MSICWG) Instrumentation, Data Format, and Networks Document

    Science.gov (United States)

    Brenton, James; Roberts, Barry C.

    2017-01-01

    The purpose of this document is to provide an overview of instrumentation discussed at the Meteorological Interface Control Working Group (MSICWG), a reference for data formats currently used by members of the group, a summary of proposed formats for future use by the group, an overview of the data networks of the group's members. This document will be updated as new systems are introduced, old systems are retired, and when the MSICWG community necessitates a change to the formats. The MSICWG consists of personnel from the National Aeronautics and Space Administration (NASA) Kennedy Space Center (KSC), NASA Marshall Space Flight Center (MSFC), NASA Johnson Space Center (JSC), National Oceanic and Atmospheric Administration National Weather Service Spaceflight Meteorology Group (SMG), and the United States Air Force (USAF) 45th Space Wing and Weather Squadron. The purpose of the group is to coordinate the distribution of weather related data to support NASA space launch related activities.

  15. An integrated approach for integrated intelligent instrumentation and control system (I3CS)

    International Nuclear Information System (INIS)

    Jung, C.H.; Kim, J.T.; Kwon, K.C.

    1997-01-01

    Nuclear power plants to guarantee the safety of public should be designed to reduce the operator intervention resulting in operating human errors, identify the process states in transients, and aid to make a decision of their tasks and guide operator actions. For the sake of this purpose, MMIS(MAN-Machine Interface System) in NPPs should be the integrated top-down approach tightly focused on the function-based task analysis including an advanced digital technology, an operator support function, and so on. The advanced I and C research team in KAERI has embarked on developing an Integrated Intelligent Instrumentation and Control System (I 3 CS) for Korea's next generation nuclear power plants. I 3 CS bases the integrated top-down approach on the function-based task analysis, modern digital technology, standardization and simplification, availability and reliability, and protection of investment. (author). 4 refs, 6 figs

  16. Regulatory issues of digital instrumentation and control system in Lungmen project

    International Nuclear Information System (INIS)

    Chuang, C.F.; Chou, H.P.

    2004-01-01

    The Lungmen Nuclear Power Station (LNPS) is currently under construction in Taiwan, which consists of 2 advanced boiling water reactor (ABWR) units. The instrumentation and control (IC) systems of the LNPS are based on the state-of-the-art modernized fully integrated digital design. These IC systems possess many advantages and distinguished features comparing to traditional analog IC systems, they enjoy set-point stability, self-diagnostic and automatic testing ability, fault tolerance and avoidance, low power requirements, data handling and storage capability, as well as enhanced human-machine interfaces. This paper presents regulatory overviews, regulatory requirements, current major regulatory issues, as well as the areas of regulatory concerns and the lessons learned on the digital IC systems in the Lungmen Project

  17. An integrated approach for integrated intelligent instrumentation and control system (I{sup 3}CS)

    Energy Technology Data Exchange (ETDEWEB)

    Jung, C H; Kim, J T; Kwon, K C [Korea Atomic Energy Research Inst., Yusong, Taejon (Korea, Republic of)

    1997-07-01

    Nuclear power plants to guarantee the safety of public should be designed to reduce the operator intervention resulting in operating human errors, identify the process states in transients, and aid to make a decision of their tasks and guide operator actions. For the sake of this purpose, MMIS(MAN-Machine Interface System) in NPPs should be the integrated top-down approach tightly focused on the function-based task analysis including an advanced digital technology, an operator support function, and so on. The advanced I and C research team in KAERI has embarked on developing an Integrated Intelligent Instrumentation and Control System (I{sup 3}CS) for Korea`s next generation nuclear power plants. I{sup 3}CS bases the integrated top-down approach on the function-based task analysis, modern digital technology, standardization and simplification, availability and reliability, and protection of investment. (author). 4 refs, 6 figs.

  18. State laws on tobacco control--United States, 1998.

    Science.gov (United States)

    Fishman, J A; Allison, H; Knowles, S B; Fishburn, B A; Woollery, T A; Marx, W T; Shelton, D M; Husten, C G; Eriksen, M P

    1999-06-25

    State laws addressing tobacco use, the leading preventable cause of death in the United States, are summarized. Laws address smoke-free indoor air, minors' access to tobacco products, advertising of tobacco products, and excise taxes on tobacco products. Legislation effective through December 31, 1998. CDC identified laws addressing tobacco control by using an on-line legal research database. CDC's findings were verified with the National Cancer Institute's State Cancer Legislative Database. Since a previous surveillance summary on state tobacco-control laws published in November 1995 (covering legislation effective through June 30, 1995), several states have enacted new restrictions or strengthened existing legislation that addresses smoke-free indoor air, minors' access to tobacco, tobacco advertising, and tobacco taxes. Five states strengthened their smoke-free indoor air legislation. All states and Washington, D.C., continued to prohibit the sale and distribution of tobacco products to minors; however, 21 states expanded minors' access laws by designating enforcement authorities, adding license suspension or revocation for sale to minors, or requiring signage. Since the 1995 report, eight additional states (a total of 19 states and Washington, D.C.) now ban vending machines from areas accessible to minors. Thirteen states restrict advertising of tobacco products, an increase of four states since the 1995 report. Although the number of states that tax cigarettes and smokeless tobacco did not change, 13 states increased excise taxes on cigarettes, and five states increased excise taxes on smokeless tobacco products. The average state excise tax on cigarettes is 38.9 cents per pack, an increase of 7.4 cents compared with the average tax in the 1995 report. State laws addressing tobacco control vary in relation to restrictiveness, enforcement and penalties, preemptions, and exceptions. The data summarizing state tobacco-control laws are available through CDC

  19. Data acquisition and instrument control system for neutron ...

    Indian Academy of Sciences (India)

    used for controlling various neutron spectrometers using single end-on detector in step scan mode. ... An interface card and DC motor driver card have been ... ther through computation or user input) the values of the angles for the various.

  20. Control Engineering Embraces Instrumentation and Alarm Systems Of Navy

    Directory of Open Access Journals (Sweden)

    Gheorghe Samoilescu

    2008-10-01

    Full Text Available Control engineering can be applied not only to propelling and auxiliary machinery but also to electrical installations, refrigeration, cargo handling (especially in tankers and deck machinery, e.g. Windlass control. Opinion still vary on such matters as the relative merits of pneumatic versus electronic system and whether the control center should be in the engine room or adjacent to the navigating bridge. Arguments against the exclusion of the engineer officer from close contact with the machinery are countered by the fact that electronic systems are based on changes other than those of human response. Automated ships (UMS operate closer to prescribed standards and therefore operate with greater efficiency. The closer control of machinery operating conditions (cooling water temperatures and pressures, permits machinery to be run at its optimum design conditions, making for fuel economy and reduced maintenance.

  1. An Instrumented Glove for Control Audiovisual Elements in Performing Arts

    Directory of Open Access Journals (Sweden)

    Rafael Tavares

    2018-02-01

    Full Text Available The use of cutting-edge technologies such as wearable devices to control reactive audiovisual systems are rarely applied in more conventional stage performances, such as opera performances. This work reports a cross-disciplinary approach for the research and development of the WMTSensorGlove, a data-glove used in an opera performance to control audiovisual elements on stage through gestural movements. A system architecture of the interaction between the wireless wearable device and the different audiovisual systems is presented, taking advantage of the Open Sound Control (OSC protocol. The developed wearable system was used as audiovisual controller in “As sete mulheres de Jeremias Epicentro”, a portuguese opera by Quarteto Contratempus, which was premiered in September 2017.

  2. 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

  3. 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.

  4. Design concepts for a nuclear digital instrumentation and control system platform

    International Nuclear Information System (INIS)

    Ou, T. C.; Chen, C. K.; Chen, P. J.; Shyu, S. S.; Lee, C. L.; Hsieh, S. F.

    2010-10-01

    The objective of this paper is to present the development results of the nuclear instrumentation and control system in Taiwan. As the Taiwan nuclear power plants age, the need to consider upgrading of both their safety and non-safety-related instrumentation and control systems becomes more urgent. Meanwhile, the digital instrumentation and control system that is based on current fast evolving electronic and information technologies are difficult to maintain effectively. Therefore, Institute of Nuclear Energy Research was made a decision to promote the Taiwan Nuclear Instrumentation and Control System project to collaborate with domestic electronic industry to establish self-reliant capabilities on the design, manufacturing, and application of nuclear instrumentation and control systems with newer technology. In the case of safety-related applications like nuclear instrumentation and control, safety-oriented quality control is required. In order to establish a generic qualified digital platform, the world-wide licensing experience should be considered in the licensing process. This paper describes the qualification and certification tools by IEC 61508 for design and development of safety related equipment and explains the basis for many decisions made while performing the digital upgrade. (Author)

  5. A Scheme of Controlled Quantum State Swapping

    International Nuclear Information System (INIS)

    Zha Xinwei; Zou Zhichun; Qi Jianxia; Song Haiyang

    2012-01-01

    A scheme for controlled quantum state swapping is presented using maximally entangled five-qubit state, i.e., Alice wants to transmit an entangled state of particle a to Bob and at the same time Bob wants to transmit an entangled state of particle b to Alice via the control of the supervisor Charlie. The operations used in this swapping process including C-not operation and a series of single-qubit measurements performed by Alice, Bob, and Charlie.

  6. Acceptance Test Procedure for New Pumping and Instrumentation Control Skid L

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping and Instrumentation Control (PIC) skid designed as ''L''. The ATP will be performed after the construction of the PIC skid in the shop

  7. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''P''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''P''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  8. Acceptance Test Procedure for New Pumping and Instrumentation Control Skid N

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping and Instrumentation Control (PIC) skid designed as ''N''. The ATP will be performed after the construction of the PIC skid in the shop

  9. Utilization of the research reactors for the power reactor control instrumentation development

    International Nuclear Information System (INIS)

    Duchene, J.; Verdant, R.; Gilbert, J.

    1977-01-01

    Studies on characteristics and reliability of control instruments lead to testing with various radiations of various intensities and energy spectra. Osiris and Triton reactors present this great variety of radiations and a flexibility of use better than power reactors [fr

  10. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid W

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''W''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  11. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid V

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control. (PIC) skid designed as ''V''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  12. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''V''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designated as ''V''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  13. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''Q''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''Q''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  14. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''T''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designated as ''T''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  15. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid T

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing Of the new Pumping Instrumentation and Control (PIC) skid designed as ''T''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  16. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid R

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''R''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  17. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''U''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''U''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  18. Instrumentation and Controls Division progress report, July 1, 1990--June 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    This report contains the following information from the Instrumentation and Controls Division of Oak Ridge National Laboratory: supplementary activities; seminars; publications and presentations; scientific and professional activities, achievements, and awards; and division organization charts.

  19. Instrumentation and Controls Division progress report, July 1, 1990--June 30, 1992. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    This report contains the following information from the Instrumentation and Controls Division of Oak Ridge National Laboratory: supplementary activities; seminars; publications and presentations; scientific and professional activities, achievements, and awards; and division organization charts.

  20. Design and quality assurance of control and instrumentation systems, licensing practice in Austria

    International Nuclear Information System (INIS)

    Fasko, Peter.

    1978-01-01

    The practicised way how licensing of control and instrumentation systems is performed in Austria, is related. As there is no national regulations in Austria for licensing nuclear power plants, it tries to adopt international regulations for its own purpose. (author)

  1. Instrumentation and Controls Division progress report, September 1, 1980-July 1, 1982

    Energy Technology Data Exchange (ETDEWEB)

    Klobe, L.E.E. (ed.)

    1982-12-01

    Activities are reported by the Reactor Systems Section, Research Instrument Section, and the Measurement and Controls Engineering Section. Reactor system activities include dynamic analysis, survillanc and diagnostic methods, design and evaluation, detectors, facilities support, process instrumentation development, and special assignments. Activities in the Research Instrument Section include the Navy-ORNL RADIAC development program, advanced ..gamma.. and x ray detector systems, neutron detection and subcriticality measurements, circuit development, position-sensitive detectors, stand-alone computers, environmental monitoring-detectors and systems, plant security, engineering support for fusion energy division, engineering support for accelerator physics, and communications: radio, closed-circuit tv, and computer. Activities in the Measurement and Controls Engineering Section include the AVLIS program; gas centrifuge enrichment technology support; Advanced Instrumentation for Reflood Studies (AIDRS) program; instrumentation development support for fuel reprocessing; in-core experiments and reactor systems; energy, conservation, and electric power systems; computer systems; measurements research; and fossil energy studies Publications are listed. (WHK)

  2. A survey on the VXIbus and validity analyses for instrumentation and control in NPPs

    International Nuclear Information System (INIS)

    Kwon, Kee Choon; Park, Won Man

    1997-06-01

    This document presents the technical status of the VXIbus system and its interface. VMEbus, while developed as a backplane for Motorola processors, can be used for data acquisition, control and other instrumentation applications. The VXIbus and its associated standard for form, fit, and electrical interface have simplified the process of putting together automated instrumentation systems. The VXIplug and play system alliance was founded in 1993, the alliance's charter to improve the effectiveness of VXI-based solutions by increasing ease-of-use and improving the interoperability of mainframes, computers, instrumentations, and software through open, multivendor standards and practices. This technical report surveys surveys the instrumentation and control in NPPs apply to the VXI-based instruments which are studied expendability, interoperability, maintainability and other features. (author). 10 refs., 4 tabs., 25 figs

  3. Instrumentation and Controls Division progress report, September 1, 1980-July 1, 1982

    International Nuclear Information System (INIS)

    Klobe, L.E.E.

    1982-12-01

    Activities are reported by the Reactor Systems Section, Research Instrument Section, and the Measurement and Controls Engineering Section. Reactor system activities include dynamic analysis, survillanc and diagnostic methods, design and evaluation, detectors, facilities support, process instrumentation development, and special assignments. Activities in the Research Instrument Section include the Navy-ORNL RADIAC development program, advanced #betta# and x ray detector systems, neutron detection and subcriticality measurements, circuit development, position-sensitive detectors, stand-alone computers, environmental monitoring-detectors and systems, plant security, engineering support for fusion energy division, engineering support for accelerator physics, and communications: radio, closed-circuit tv, and computer. Activities in the Measurement and Controls Engineering Section include the AVLIS program; gas centrifuge enrichment technology support; Advanced Instrumentation for Reflood Studies (AIDRS) program; instrumentation development support for fuel reprocessing; in-core experiments and reactor systems; energy, conservation, and electric power systems; computer systems; measurements research; and fossil energy studies Publications are listed

  4. Process instrumentation and control for cryogenic system of VECC

    International Nuclear Information System (INIS)

    Pal, Sandip

    2017-01-01

    Superconducting Cyclotron, which comprises of superconducting main magnet and cryopanels operating at 4.3 K, are operational at VECC in three phases starting from 2005; finally without interruption from July, 2010 to November, 2016. Cryogenic loads of the Cyclotron are catered by any of the two helium liquefiers/refrigerators (250W and 415W @ 4.5K) and associated cryogen distribution system with extensive helium gas management system. The system also consists of 31 K liters of liquid Nitrogen (LN_2) storage and delivery system, necessary of radiation shield. EPICS (Experimental Physics and Industrial Control System) architecture is open source, flexible and has unlimited tags as compared to the commercial Supervisory control and data acquisition (SCADA) packages. Hence, it has been adopted to design the SCADA module. The EPICS Input Output Controller (IOC) communicates with four PLCs over Ethernet based control LAN to control/monitor 618 numbers of field Inputs/ Outputs (I/O). The control system is fully automated and does not require any human intervention for routine operation. Since these two liquefiers share the same high pressure (HP) and low pressure (LP) pipelines, any pressure fluctuation due to rapid change in flow sometimes causes trip of the liquefiers. Few modifications are made in the control scheme in HP and LP zones to avoid liquefier trip. The plant is running very reliably round the clock and the historical data of important parameters during plant operation are archived for plant maintenance, easy diagnosis and future modifications. Total pure helium cycle gas inventory is monitored through EPICS for early detection of helium loss from its trend

  5. Modernization of control instrumentation and security of reactor IAN - R1

    International Nuclear Information System (INIS)

    Gonzalez, J. M.

    1993-01-01

    The program to modernize IAN-R1 research reactor control and safety instrumentation has been carried out considering two main aspects: updating safety philosophy requirements and acquiring the newest reactor control instrumentation controlled by computer, following the present criteria internationally recognized, for safety and reliable reactor operations and the latest developments of nuclear electronic technology. The new IAN-R1 reactor instrumentation consist of two wide range neutron monitoring channels, commanded by microprocessor a data acquisition system and reactor control, (controlled by computers). The reactor control desk is providing through two displays; all safety and control signals to the reactor operators; furthermore some signals like reactor power, safety and period signals are also showed on digital bar graphics, which are hard wired directly from the neutron monitoring channels

  6. A pilot's opinion - VTOL control design requirements for the instrument approach task.

    Science.gov (United States)

    Patton, J. M., Jr.

    1972-01-01

    This paper presents pilot opinion supported by test data concerning flight control and display concepts and control system design requirements for VTOL aircraft in the instrument approach task. Material presented is drawn from research flights in the following aircraft: Dornier DO-31, Short SC-1, LTV XC-142A, and Boeing-Vertol CH-46. The control system concepts and mechanizations employed in the above aircraft are discussed, and the effect of control system augmentation is shown on performance. Operational procedures required in the instrument approach task are described, with comments on need for automation and combining of control functions.

  7. Proceedings of the 1981 symposium on instrumentation and control for fossil-energy processes

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    The 1981 symposium on instrumentation and control for fossil-energy processes was held June 8-10, 1981, at the Sheraton-Palace Hotel, San Francisco, California. It was sponsored by the US Department of Energy; Office of Fossil Energy; Argonne National Laboratory; and the Society for Control and Instrumentation of Energy Processes. Sixty-seven articles from the proceedings have been entered individually into EDB and ERA; thirteen articles had been entered previously from other sources. (LTN)

  8. Instrumentation and Controls Division, Technical Support Department Management Plan, FY 1993--FY 1996

    Energy Technology Data Exchange (ETDEWEB)

    Adkisson, B.P.; Kunselman, C.W.; Effler, R.P.; Miller, D.R.; Millet, A.J.; Stansberry, C.T.

    1993-08-01

    This report describes the organization, key functions, and major activities of the Technical Support Department The Department is the programmatic support element of the Instrumentation and Controls Division. The Department`s primary focus is the support of existing equipment and systems at Oak Ridge National Laboratory that are generally characterized as instrumentation and controls. The support takes the form of repair, calibration, fabrication, field engineering, preventive maintenance, software support, and record keeping.

  9. VME-based remote instrument control without ground loops

    CERN Document Server

    Belleman, J; González, J L

    1997-01-01

    New electronics has been developed for the remote control of the pick-up electrodes at the CERN Proton Synchrotron (PS). Communication between VME-based control computers and remote equipment is via full duplex point-to-point digital data links. Data are sent and received in serial format over simple twisted pairs at a rate of 1 Mbit/s, for distances of up to 300 m. Coupling transformers are used to avoid ground loops. The link hardware consists of a general-purpose VME-module, the 'TRX' (transceiver), containing four FIFO-buffered communication channels, and a dedicated control card for each remote station. Remote transceiver electronics is simple enough not to require micro-controllers or processors. Currently, some sixty pick-up stations of various types, all over the PS Complex (accelerators and associated beam transfer lines) are equipped with the new system. Even though the TRX was designed primarily for communication with pick-up electronics, it could also be used for other purposes, for example to for...

  10. Study on the instrumentation and control of the fermentaion process

    Energy Technology Data Exchange (ETDEWEB)

    Nanba, Akira

    1988-03-25

    An attempt was made to create models representing various fermentation processes, and these models were applied to a computer-controlled bread yeast culture plant. First, batch ethanol fermentation processes using yeast were analyzed in the light of reaction rate theory, and various model equations were presented. Using these models, analysis was made at various fermentation temperatures. As a result, it was found that the model equations are applicable to ethanol production and that the reaction rate equation is useful for analyzing high-concentration ethanol fermentation processes. Next, heat involved in ethanol fermentation was measured with a calorimeter. In combination with the above models, automatic montitoring based on microcomputer control, data processing, and display on a screen was attempted, with good results. Using the above findings, the ethanol generation reaction in the bread yeast culture was analyzed qualitatively. Culture control was performed with ethanol growth patterns as signals. The above technique has proved to be applicable to industrial bread yeast production. (17 figs, 3 tabs, 29 refs)

  11. Target Diagnostic Instrument-Based Controls Framework for the National Ignition Facility

    International Nuclear Information System (INIS)

    Shelton, R; O'Brien, D; Nelson, J; Kamperschroer, J

    2007-01-01

    NIF target diagnostics are being developed to observe and measure the extreme physics of targets irradiated by the 192-beam laser. The response time of target materials can be on the order of 100ps--the time it takes light to travel 3 cm--temperatures more than 100 times hotter than the surface of the sun, and pressures that exceed 109 atmospheres. Optical and x-ray diagnostics were developed and fielded to observe and record the results of the first 4-beam experiments at NIF. Hard and soft x-ray spectra were measured, and time-integrated and gated x-ray images of hydrodynamics experiments were recorded. Optical diagnostics recorded backscatter from the target, and VISAR laser velocimetry measurements were taken of laser-shocked target surfaces. Additional diagnostics are being developed and commissioned to observe and diagnose ignition implosions, including various neutron and activation diagnostics. NIF's diagnostics are being developed at LLNL and with collaborators at other sites. To accommodate the growing number of target diagnostics, an Instrument-Based Controls hardware-software framework has been developed to facilitate development and ease integration into the NIF Integrated Computer Control System (ICCS). Individual WindowsXP PC controllers for each digitizer, power supply and camera (i.e., instruments) execute controls software unique to each instrument model. Each hardware-software controller manages a single instrument, in contrast to the complexity of combining all the controls software needed for a diagnostic into a single controller. Because of this simplification, controllers can be more easily tested on the actual hardware, evaluating all normal and off-normal conditions. Each target diagnostic is then supported by a number of instruments, each with its own hardware-software instrument-based controller. Advantages of the instrument-based control architecture and framework include reusability, testability, and improved reliability of the deployed

  12. Target Diagnostic Instrument-Based Controls Framework for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Shelton, R; O' Brien, D; Nelson, J; Kamperschroer, J

    2007-05-07

    NIF target diagnostics are being developed to observe and measure the extreme physics of targets irradiated by the 192-beam laser. The response time of target materials can be on the order of 100ps--the time it takes light to travel 3 cm--temperatures more than 100 times hotter than the surface of the sun, and pressures that exceed 109 atmospheres. Optical and x-ray diagnostics were developed and fielded to observe and record the results of the first 4-beam experiments at NIF. Hard and soft x-ray spectra were measured, and time-integrated and gated x-ray images of hydrodynamics experiments were recorded. Optical diagnostics recorded backscatter from the target, and VISAR laser velocimetry measurements were taken of laser-shocked target surfaces. Additional diagnostics are being developed and commissioned to observe and diagnose ignition implosions, including various neutron and activation diagnostics. NIF's diagnostics are being developed at LLNL and with collaborators at other sites. To accommodate the growing number of target diagnostics, an Instrument-Based Controls hardware-software framework has been developed to facilitate development and ease integration into the NIF Integrated Computer Control System (ICCS). Individual WindowsXP PC controllers for each digitizer, power supply and camera (i.e., instruments) execute controls software unique to each instrument model. Each hardware-software controller manages a single instrument, in contrast to the complexity of combining all the controls software needed for a diagnostic into a single controller. Because of this simplification, controllers can be more easily tested on the actual hardware, evaluating all normal and off-normal conditions. Each target diagnostic is then supported by a number of instruments, each with its own hardware-software instrument-based controller. Advantages of the instrument-based control architecture and framework include reusability, testability, and improved reliability of the

  13. GLOBALIZATION AND THE DECLINE OF THE UNITED STATES ECONOMIC INSTRUMENT OF POWER

    Science.gov (United States)

    2017-06-01

    of global trade relations. Whereas forty years ago, 90 percent of international trade consisted of mercantilist goods; today , 90 percent of... GLOBALIZATION AND THE DECLINE OF THE UNITED STATES ECONOMIC INSTRUMENT OF POWER BY MAJOR JOSH WATKINS A THESIS PRESENTED TO THE...bachelor of business administration degree from Old Dominion University in 2001. He was commissioned through Officer Training School in 2002 and his

  14. Isolation contactor state control system

    Energy Technology Data Exchange (ETDEWEB)

    Bissontz, Jay E.

    2017-05-16

    A controller area network (CAN) installed on a hybrid electric vehicle provides one node with control of high voltage power distribution system isolation contactors and the capacity to energize a secondary electro-mechanical relay device. The output of the secondary relay provides a redundant and persistent backup signal to the output of the node. The secondary relay is relatively immune to CAN message traffic interruptions and, as a result, the high voltage isolation contactor(s) are less likely to transition open in the event that the intelligent output driver should fail.

  15. Application of new technology to SMART instrumentation and control systems

    Energy Technology Data Exchange (ETDEWEB)

    Park, Heui Youn; Lee, C. K.; Kim, D. H.; Suh, Y. S.; Hur, S.; Seong, S. H.; Jang, G. S.; Koo, I. S.; Chang, M. H

    1998-03-01

    It is very important to examine the conformance with licensing requirements and standards when new digital technology and equipment apply to nuclear plants. Key requirements of licensing on digitalisation using new technologies are software and hardware V and V, reliability of communication network, and diversity and defence-in-depth concept against common mode failures of hardware and software. And it should be also evaluated whether the selection and application of new technology comply with the design concept and requirements of SMART MMIS or not. In this report, we reviewed digitalisation materials such as EPRI`s ALWR utility requirements document, I and C upgrade plan, guideline on licensing digital upgrades, and IAEA`s issues and approaches to plant modernization to explore application method on new I and C technologies, and evaluated the state of applicable new technologies for SMART MMIS which are selected from the technologies, methods, and manuals of the industrial area. (author). 36 refs., 15 tabs.

  16. Application of new technology to SMART instrumentation and control systems

    International Nuclear Information System (INIS)

    Park, Heui Youn; Lee, C. K.; Kim, D. H.; Suh, Y. S.; Hur, S.; Seong, S. H.; Jang, G. S.; Koo, I. S.; Chang, M. H.

    1998-03-01

    It is very important to examine the conformance with licensing requirements and standards when new digital technology and equipment apply to nuclear plants. Key requirements of licensing on digitalisation using new technologies are software and hardware V and V, reliability of communication network, and diversity and defence-in-depth concept against common mode failures of hardware and software. And it should be also evaluated whether the selection and application of new technology comply with the design concept and requirements of SMART MMIS or not. In this report, we reviewed digitalisation materials such as EPRI's ALWR utility requirements document, I and C upgrade plan, guideline on licensing digital upgrades, and IAEA's issues and approaches to plant modernization to explore application method on new I and C technologies, and evaluated the state of applicable new technologies for SMART MMIS which are selected from the technologies, methods, and manuals of the industrial area. (author). 36 refs., 15 tabs

  17. REKO - Bohunice V-1. Experience with instrumentation and control system

    International Nuclear Information System (INIS)

    Arbet, L.; Ziska, D.; Golan, P.; Karaba, P.; Krupa, S.; Wiening, K.-H.

    2000-01-01

    In this paper and in presentation some results of upgrading of the NPP Bohunice V-1 are presented. For the first time, extensive upgrades are performed in all safety-related areas of both units with VVER 440/230 reactors. These upgrades focused on: - Expansion and upgrading of the process safety systems; - Replacement of the safety I and C system with a TELEPERM XS-based system; - Spatial separation of safety equipment; - Modernisation of the electrical auxiliary power systems; - Seismic upgrading and fire protection; - Improvement of the man-machine interface. This upgrade is considered exemplary around the world. The most extensive stage of gradual reconstruction of Unit 2 was completed according to the schedule in January 1999. For the first time, a reactor which incorporates state-of-the-art digital I and C in its reactor protection system is on-line. (author)

  18. Long-term preventive maintenance of instrumentation control equipment for PWR plants

    International Nuclear Information System (INIS)

    Sugitani, S.; Nanba, M.

    2006-01-01

    Since the PWR plants in Japan have been operated more than 30 years, main instrumentation control equipment of analog systems has been renewed to digital control systems. Renewal works had to be done in short period within periodical inspection term and for several facilities. The Mitsubishi LTD group had been provided with these market needs by its digital control system (MELTAC-NplusR 3) applicable to main instrumentation control equipment for primary and secondary systems and had already finished the renewal for practical plants. (T. Tanaka)

  19. State Radiation Protection Supervision and Control

    International Nuclear Information System (INIS)

    2003-01-01

    Radiation Protection Centre is carrying state supervision and control of radiation protection. The main objective of state supervision and control of radiation protection is assessing how licensees comply with requirements of the appropriate legislation and enforcement. Summary of inspections conducted in 2002 is presented

  20. Nonlinear H-ininity state feedback controllers:

    DEFF Research Database (Denmark)

    Cromme, Marc; Møller-Pedersen, Jens; Pagh Petersen, Martin

    1997-01-01

    From a general point of view the state feedback H∞ suboptimal control problem is reasonably well understood. Important problems remain with regard to a priori information of the size of the neighbourhood where the local state feedback H∞ problem is solvable. This problem is solved regionally (sem...... (semiglobally) in this paper, and the obtained control laws are implemented in MAPLE...

  1. Federal/State Radiation Control Legislation, 1974

    International Nuclear Information System (INIS)

    Miller, L.A.

    1975-07-01

    A review is presented of Federal and State radiation control legislation for calendar year 1974, in Federal-State, subject, and status order. A brief description of each bill introduced in 1974 is included, plus existing laws or statutes governing radiation control. (auth)

  2. State Radiation Protection Supervision and Control

    CERN Document Server

    2002-01-01

    Radiation Protection Centre is carrying state supervision and control of radiation protection. The main objective of state supervision and control of radiation protection is assessing how licensees comply with requirements of the appropriate legislation and enforcement. Summary of inspections conducted in 2002 is presented.

  3. State Supervision and Control of Radiation Protection

    CERN Document Server

    2001-01-01

    Radiation Protection Centre is carrying state supervision and control of radiation protection. The main objective of state supervision and control of radiation protection is assessing how licensees comply with requirements of the appropriate legislation and enforcement. Summary of inspections conducted in 1999-2001 is presented.

  4. Future Direction of the Instrumentation and Control System for Security of Nuclear Facilities

    International Nuclear Information System (INIS)

    Kim, Woo Jin; Kim, Jae Kwang

    2014-01-01

    Instrumentation and control systems are pervasively used as a vital component in modern industries. Nuclear facilities, such as nuclear power plants (NPPs), originally use I and C systems for plant status monitoring, processes control, and many other purposes. After some events that raised security concerns, application areas of I and C systems have been expanded to physical protection of nuclear material and facilities. As nuclear policies over the world are strengthening security issues, the future direction of roles and technical requirements of security related I and C systems is described: An introduction of I and C systems, especially digitalized I and C systems, to security of nuclear facilities requires many careful considerations, such as system integration, verification and validation (V/V), etc. Institute of Nuclear Nonproliferation and Control (KINAC) established 'International Nuclear Nonproliferation and Security Academy, INSA' in 2014. One of the main achievements of INSA is test-bed implementation for technical criteria development of nuclear facilities' physical protection systems (PPSs) as well as for education and training of those systems. The test bed was modified and improved more suitably from the previous version to modern PPSs including state-of-the-art I and C technologies. KINAC is confident in the new test bed to become a fundamental technical basis of security related I and C systems in near future

  5. An instrumentation and control philosophy for high-level nuclear waste processing facilities

    International Nuclear Information System (INIS)

    Weigle, D.H.

    1990-01-01

    The purpose of this paper is to present an instrumentation and control philosophy which may be applied to high-level nuclear waste processing facilities. This philosophy describes the recommended criteria for automatic/manual control, remote/local control, remote/local display, diagnostic instrumentation, interlocks, alarm levels, and redundancy. Due to the hazardous nature of the process constituents of a high-level nuclear waste processing facility, it is imperative that safety and control features required for accident-free operation and maintenance be incorporated. A well-instrumented and controlled process, while initially more expensive in capital and design costs, is generally safer and less expensive to operate. When the long term cost savings of a well designed process is coupled with the high savings enjoyed by accident avoidance, the benefits far outweigh the initial capital and design costs

  6. 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

  7. Maintenance quality surveillance for nuclear reactor instrument and control systems

    International Nuclear Information System (INIS)

    Clement, T.M.

    1976-01-01

    A description is given of a formal program of mandatory testing and inspection for assurance of reliability at the N-reactor. The techniques and procedures are called Equipment Maintenance Standards (EMS) and cover the nuclear plant systems which affect nuclear safety, environmental control, continuity of operation and reactor life. The scope of the program is such that all electrical, chemical, mechanical, and nuclear devices with interconnecting circuitry, linkages, and piping are functionally checked and/or inspected from sensors through actuating media necessary for carrying out the defined functions under startup, operating, and shutdown conditions and also under any credible accident condition. Records are kept of the AS FOUND results of the tests and inspections along with adjustments and repairs required to correct any out-of-limits conditions found. These records are accumulated and are used as a source for quantitative reliability information and for evaluating wear-out or design problems

  8. Replacement of the instrumentation and control system of Tore Supra

    International Nuclear Information System (INIS)

    Leveque, P.

    1995-02-01

    The control system of the Tore-Supra is a wide and complex system that cannot be interrupted while running without significant consequences on the operating of the machine. Replacing the current system cannot be achieved in a global way without immobilisation and high costs. Therefore partial changes have been decided on. This work presents the detailed analysis of the arrangements and the operating of the system that will be replaced: the pro's and con's that have appeared through experience are related. The possibilities that the new apparatus offers are also examined. A method of step by step replacements had to be set up in order to assess the means, funds, term of achievement, performance and quality of the overall project. (TEC). 15 refs., 29 figs

  9. 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

  10. Metallurgical characterization of controlled memory wire nickel-titanium rotary instruments.

    Science.gov (United States)

    Shen, Ya; Zhou, Hui-Min; Zheng, Yu-Feng; Campbell, Les; Peng, Bin; Haapasalo, Markus

    2011-11-01

    To improve the fracture resistance of nickel-titanium (NiTi) files, manufacturers have introduced new alloys and developed new manufacturing processes for the fabrication of NiTi files. This study aimed to examine the phase transformation behavior and microstructure of NiTi instruments from a novel controlled memory NiTi wire (CM wire). Instruments of EndoSequence (ES), ProFile (PF), ProFile Vortex (Vortex), Twisted Files (TF), Typhoon (TYP), and Typhoon™ CM (TYP CM), all size 25/.04, were examined by differential scanning calorimetry (DSC) and x-ray diffraction (XRD). Microstructures of etched instruments were observed by optical microscopy and scanning electron microscopy with x-ray energy-dispersive spectrometric (EDS) analyses. The DSC analyses showed that each segment of the TYP CM and Vortex instruments had an austenite transformation completion or austenite-finish (A(f)) temperature exceeding 37°C, whereas the NiTi instruments made from conventional superelastic NiTi wire (ES, PF, and TYP) and TF had A(f) temperatures substantially below mouth temperature. The higher A(f) temperature of TYP CM instruments was consistent with a mixture of austenite and martensite structure, which was observed at room temperature with XRD. All NiTi instruments had room temperature martensite microstructures consisting of colonies of lenticular features with substantial twinning. EDS analysis indicated that the precipitates in all NiTi instruments were titanium-rich, with an approximate composition of Ti(2)Ni. The TYP CM and Vortex instruments with heat treatment contribute to increase austenite transformation temperature. The CM instrument has significant changes in the phase transformation behavior, compared with conventional superelastic NiTi instruments. Copyright © 2011 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

  11. The development of advanced instrumentation and control technology -The development of basic technology for instrumentation and control-

    Energy Technology Data Exchange (ETDEWEB)

    Ham, Chang Sik; Kwon, Kee Choon; Park, Jae Chang; Kim, Jung Taek; Jung, Chul Hwan; Lee, Dong Yung; Kim, Chang Hoi; Hwang, In Koo; Kim, Jung Soo; Nah, Nan Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    In this report automatic startup technology and dynamic alarm processing technology are developed. We designed an automatic control system had four modes and six break points. The four modes are heating mode I, heating mode II, heating mode III and critical mode. The six break points are RHR isolation and pressurizer bubble generation, P-6, critical conformation and another three break points for the start point of each mode from heating mode II to critical mode. We defined control variables and components at each mode and developed control algorithms. The conceptual design for automatic startup system configuration and interface with test facility was developed. These results will be used for detail design and software implementation in the project of next year. For development of dynamic alarm processing technology, necessary techniques were selected according to the survey on current development activities and the analysis on design documents. Alarm operating procedures were studied for obtaining casual relationships among alarms and part of a preliminary prototype was implemented in this first year using the results of the analysis including various techniques studied during the survey and analysis stage. 70 figs, 7 tabs, 77 refs. (Author).

  12. Control and acquisition system of a space instrument for cosmic ray measurement

    Science.gov (United States)

    Prieto, M.; Martín, C.; Quesada, M.; Meziat, D.; Medina, J.; Sánchez, S.; Rodríguez-Frías, M. D.

    2000-04-01

    The PESCA Instrument Control and Acquisition System (PICAS) design, building and tests are presented. The purpose of the PESCA instrument is the study of the Solar Energetic Particles and the Anomalous Cosmic Rays. It is, therefore, a satellite on-board instrument. The PICAS is basically a computer, composed of a microprocessor with a memory block and a set of interfaces for the communication with the rest of the instrument and the satellite. The PICAS manages all the comunication processes with the satellite, that comprises the order reception from the ground station, and the telemetry sending, that includes scientific data and housekeeping data. By means of telecommands, the PICAS is completely controllable from the ground. The PICAS is also a reliable data acquisition system that guarantees the correct reception of the Cosmic Rays data collected in the ground.

  13. Study on virtual instrument developing system based on intelligent virtual control

    International Nuclear Information System (INIS)

    Tang Baoping; Cheng Fabin; Qin Shuren

    2005-01-01

    The paper introduces a non-programming developing system of a virtual instrument (VI), i.e., a virtual measurement instrument developing system (VMIDS) based on intelligent virtual control (IVC). The background of the IVC-based VMIDS is described briefly, and the hierarchical message bus (HMB)-based software architecture of VMIDS is discussed in detail. The three parts and functions of VMIDS are introduced, and the process of non-programming developing VI is further described

  14. Study on virtual instrument developing system based on intelligent virtual control

    Energy Technology Data Exchange (ETDEWEB)

    Tang Baoping; Cheng Fabin; Qin Shuren [Test Center, College of Mechanical Engineering, Chongqing University , Chongqing 400030 (China)

    2005-01-01

    The paper introduces a non-programming developing system of a virtual instrument (VI), i.e., a virtual measurement instrument developing system (VMIDS) based on intelligent virtual control (IVC). The background of the IVC-based VMIDS is described briefly, and the hierarchical message bus (HMB)-based software architecture of VMIDS is discussed in detail. The three parts and functions of VMIDS are introduced, and the process of non-programming developing VI is further described.

  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. Controlled quantum teleportation with Bell states

    International Nuclear Information System (INIS)

    Wang Tian-Yin; Wen Qiao-Yan

    2011-01-01

    We propose a new scheme for controlled quantum teleportation with Bell states in which classical keys for controllers' portion are used. We also discuss the security of the proposed scheme and show that it can satisfy the requirements for controlled quantum teleportation. The comparison between this scheme and the previous ones shows that it is more economical and efficient. (general)

  17. State estimation for integrated vehicle dynamics control

    NARCIS (Netherlands)

    Zuurbier, J.; Bremmer, P.

    2002-01-01

    This paper discusses a vehicle controller and a state estimator that was implemented and tested in a vehicle equipped with a combined braking and chassis control system to improve handling. The vehicle dynamics controller consists of a feed forward body roll compensation and a feedback stability

  18. Towards a Generic and Adaptive System-On-Chip Controller for Space Exploration Instrumentation

    Science.gov (United States)

    Iturbe, Xabier; Keymeulen, Didier; Yiu, Patrick; Berisford, Dan; Hand, Kevin; Carlson, Robert; Ozer, Emre

    2015-01-01

    This paper introduces one of the first efforts conducted at NASA’s Jet Propulsion Laboratory (JPL) to develop a generic System-on-Chip (SoC) platform to control science instruments that are proposed for future NASA missions. The SoC platform is named APEX-SoC, where APEX stands for Advanced Processor for space Exploration, and is based on a hybrid Xilinx Zynq that combines an FPGA and an ARM Cortex-A9 dual-core processor on a single chip. The Zynq implements a generic and customizable on-chip infrastructure that can be reused with a variety of instruments, and it has been coupled with a set of off-chip components that are necessary to deal with the different instruments. We have taken JPL’s Compositional InfraRed Imaging Spectrometer (CIRIS), which is proposed for NASA icy moons missions, as a use-case scenario to demonstrate that the entire data processing, control and interface of an instrument can be implemented on a single device using the on-chip infrastructure described in this paper. We show that the performance results achieved in this preliminary version of the instrumentation controller are sufficient to fulfill the science requirements demanded to the CIRIS instrument in future NASA missions, such as Europa.

  19. 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

  20. Cold Vacuum Drying Safety Class Instrumentation and Control System Design Description SYS 93-2

    International Nuclear Information System (INIS)

    WHITEHURST, R.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) Safety Class Instrumentation and Control system (SCIC). The SCIC provides safety functions and features to protect the environment, off-site and on-site personnel and equipment. The function of the SCIC is to provide automatic trip features, valve interlocks, alarms, indication and control for the cold vacuum drying process

  1. Cold Vacuum Drying Safety Class Instrumentation and Control System Design Description

    International Nuclear Information System (INIS)

    WHITEHURST, R.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) Safety Class Instrumentation and Control system (SCIC). The SCIC provides safety functions and features to protect the environment, off-site and on-site personnel and equipment. The function of the SCIC is to provide automatic trip features, valve interlocks, alarms, indication and control for the cold vacuum drying process

  2. Governance and control as mediating instruments in an inter-firm relationship : Towards collaboration or transactions?

    NARCIS (Netherlands)

    Zahir-Ul-Hassan, Muhammad Kaleem; Minnaar, Reinald A.; Vosselman, E.G.J.

    2016-01-01

    This paper explores the mediation of governance and control structures in an inter-firm relationship between a semiconductor producer and its contractor. As mediating instruments the contract and the control structures are not just pre-given results of distanced managerial decision-making, but are

  3. Governance and control as mediating instruments in an inter-firm relationship: towards collaboration or transactions?

    NARCIS (Netherlands)

    Zahir-ul-Hassan, M.K.; Minnaar, R.A.; Vosselman, E.G.J.

    2016-01-01

    This paper explores the mediation of governance and control structures in an inter-firm relationship between a semiconductor producer and its contractor. As mediating instruments the contract and the control structures are not just pre-given results of distanced managerial decision-making, but are

  4. Using GPS instruments and GIS techniques in data management for insect pest control programs

    International Nuclear Information System (INIS)

    2006-01-01

    This interactive tutorial CD entitled 'Using GPS Instruments and GIS Techniques in Data Management for Insect Pest Control Programs' was developed by Micha silver of the Arava Development Co., Sapir, Israel, and includes step-by-step hands on lessons on the use of GPS/GIS in support of area-wide pest control operations

  5. TELICS—A Telescope Instrument Control System for Small/Medium Sized Astronomical Observatories

    Science.gov (United States)

    Srivastava, Mudit K.; Ramaprakash, A. N.; Burse, Mahesh P.; Chordia, Pravin A.; Chillal, Kalpesh S.; Mestry, Vilas B.; Das, Hillol K.; Kohok, Abhay A.

    2009-10-01

    For any modern astronomical observatory, it is essential to have an efficient interface between the telescope and its back-end instruments. However, for small and medium-sized observatories, this requirement is often limited by tight financial constraints. Therefore a simple yet versatile and low-cost control system is required for such observatories to minimize cost and effort. Here we report the development of a modern, multipurpose instrument control system TELICS (Telescope Instrument Control System) to integrate the controls of various instruments and devices mounted on the telescope. TELICS consists of an embedded hardware unit known as a common control unit (CCU) in combination with Linux-based data acquisition and user interface. The hardware of the CCU is built around the ATmega 128 microcontroller (Atmel Corp.) and is designed with a backplane, master-slave architecture. A Qt-based graphical user interface (GUI) has been developed and the back-end application software is based on C/C++. TELICS provides feedback mechanisms that give the operator good visibility and a quick-look display of the status and modes of instruments as well as data. TELICS has been used for regular science observations since 2008 March on the 2 m, f/10 IUCAA Telescope located at Girawali in Pune, India.

  6. Introduction to digital instrumentation and control techniques used in nuclear engineering

    International Nuclear Information System (INIS)

    Kurilla, R.G.; Kenney, E.S.

    1988-01-01

    For the past 8 yr, the nuclear engineering department at Pennsylvania State University has been teaching a digital interfacing class at the undergraduate (senior) level. With the ever-increasing use of computers in the nuclear engineering area (such as in the use of automated data acquisition systems) and the complexity of control instrumentation, more than a cursory introduction into electronics and computer controls is needed. Because of the ever-increasing popularity, and hence importance, of IBM-PC compatible microcomputers in the engineering fields, the program has been adapted to the Intel 8086 microprocessor. Courses such as this one are helpful in ensuring the students have an adequate design and practice base as required by accrediting groups. The course, is composed of three parts: (1) machine code/assembly language, (2) interfacing, and (3) final project. Experience demonstrates that a course of this inherent complexity can successfully be taught within a nuclear engineering curriculum without extensive prerequisites. The important ingredient is to treat nuclear engineering students for exactly what they are, engineers. By having them use their creativity and adaptability, they can successfully integrate the digital interfacing techniques now routinely used in the nuclear industry

  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. Quantum state sharing against the controller's cheating

    Science.gov (United States)

    Shi, Run-hua; Zhong, Hong; Huang, Liu-sheng

    2013-08-01

    Most existing QSTS schemes are equivalent to the controlled teleportation, in which a designated agent (i.e., the recoverer) can recover the teleported state with the help of the controllers. However, the controller may attempt to cheat the recoverer during the phase of recovering the secret state. How can we detect this cheating? In this paper, we considered the problem of detecting the controller's cheating in Quantum State Sharing, and further proposed an effective Quantum State Sharing scheme against the controller's cheating. We cleverly use Quantum Secret Sharing, Multiple Quantum States Sharing and decoy-particle techniques. In our scheme, via a previously shared entanglement state Alice can teleport multiple arbitrary multi-qubit states to Bob with the help of Charlie. Furthermore, by the classical information shared previously, Alice and Bob can check whether there is any cheating of Charlie. In addition, our scheme only needs to perform Bell-state and single-particle measurements, and to apply C-NOT gate and other single-particle unitary operations. With the present techniques, it is feasible to implement these necessary measurements and operations.

  10. 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)

  11. XML for nuclear instrument control and monitoring: an approach towards standardisation

    International Nuclear Information System (INIS)

    Bharade, S.K.; Ananthakrishnan, T.S.; Kataria, S.K.; Singh, S.K.

    2004-01-01

    Communication among heterogeneous system with applications running under different operating systems and applications developed under different platforms has undergone rapid changes due to the adoption of XML standards. These are being developed for different industries like Chemical, Medical, Commercial etc. The High Energy Physics community has already a standard for exchange of data among different applications , under heterogeneous distributed systems like the CMS Data Acquisition System. There are a large number of Nuclear Instruments supplied by different manufactures which are increasingly getting connected. This approach is getting wider acceptance in instruments at reactor sites, accelerator sites and complex nuclear experiments -especially at centres like CERN. In order for these instruments to be able to describe the data which is available from them in a platform independent manner XML approach has been developed. This paper is the first attempt at Electronics Division for proposing an XML standard for control, monitoring, Data Acquisition and Analysis generated by Nuclear Instruments at Accelerator sites, Nuclear Reactor plant and Laboratory. The gamut of Nuclear Instruments include Multichannel Analysers, Health Physics Instruments, Accelerator Control Systems, Reactor Regulating systems, Flux mapping Systems etc. (author)

  12. Nineteenth Century Long-Term Instrumental Records, Examples From the Southeastern United States

    Science.gov (United States)

    Mock, C. J.

    2001-12-01

    Early instrumental records in the United States, defined as those operating before 1892 which is regarded the period prior to the modern climate record, provide a longer perspective of climatic variability at decadal and interannual timescales. Such reconstructions also provide a means of verification for other proxy data. This paper provides a American perspective of historical climatic research, emphasizing the urgent need to properly evaluate data quality and provide necessary corrections to make them compatible with the modern record. Different fixed observation times, different practices of weather instrument exposures, and statistical methods for calibration are the main issues in applying corrections and conducting proper climatic interpretations. I illustrate several examples on methodologies of this historical climatic research, focusing on the following in the Southeastern United States: daily reconstructed temperature time-series centered on Charleston SC and Natchez MS back to the late eighteenth century, and precipitation frequency reconstructions during the antebellum period for the Gulf Coast and coastal Southeast Atlantic states. Results indicate several prominent extremes unprecedented as compared to the modern record, such as the widespread warm winter of 1827-28, and the severe cold winters of 1856 and 1857. The reconstructions also yield important information concerning responses to past ENSO events, the PNA, NAO, and the PDO, particularly when compared with instrumental data from other regions. A high potential also exists for applying the climate reconstructions to assess historical climatic impacts on society in the Southeast, such as to understand climatic linkages to famous case studies of Yellow Fever epidemics and severe drought.

  13. Design and development of control instrumentation for the superconducting Linear Accelerator

    International Nuclear Information System (INIS)

    Joshi, Gopal; Kapatral, R.S.; Jha, K.; Rathod, N.C.; Sujo, C.I.; Ananthakrishnan, T.S.; Narsaiah, A.; Ghodgaonkar, M.D.; Kataria, S.K.; Singh, S.K.

    2001-01-01

    Electronics Division, BARC is developing the required control instrumentation for the Linear Accelerator (LINAC) coming up at TIFR. This consists of RF systems, CAMAC instruments and the Control and Information System. The control system consists of several identical Local Control Stations (LCS) connected over a LAN to a Main Control Station (MCS). Each LCS consists of a PC, CAMAC crates with functional Modules and RF systems. The MCS will contain two PCs running identical software. Each LCS will cater to two LINAC module each consisting of one cryostat and four resonators. This paper discusses different systems developed and under development in the Electronics Division which play an important role in the control of the LINAC. (author)

  14. 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)

  15. The 5th questionnaire report of safety control on instrument in nuclear medicine laboratory

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-08-01

    The questionnaire was done every three years from 1986 for the ultimate purpose of safe medical examinations and this 5th one was performed in May, 1998 for the period of April, 1995-March, 1998. Subjects were 1,258 nuclear medicine facilities and answers were obtained in 81.6%. Questionnaire concerned the personnel involved in nuclear medical examinations, instruments, accidents occurred, matters possibly leading to accident, improvement in safety control, serious trouble and breakage of the instrument, request for the instrument manufacturers and so on. Summaries were: numbers of medical radiology technicians were increased, in vitro tests were decreased, SPECT instruments came into wide use, in accident and improvement cases, examination beds were arousing much interest, concerns to examine were further required, communication with the manufacturers was insufficient, and problems for Y2K were pointed out to be resolved. (K.H.)

  16. Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

    Energy Technology Data Exchange (ETDEWEB)

    Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I. [Research and Production Corporation Radiy, 29 Geroev Stalingrada Str., Kirovograd 25006 (Ukraine); Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A., E-mail: marketing@radiy.co [Center for Safety Infrastructure-Oriented Research and Analysis, 37 Astronomicheskaya Str., Kharkiv 61085 (Ukraine)

    2010-10-15

    The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY{sup TM} platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY{sup TM} platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY{sup TM} platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

  17. Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

    International Nuclear Information System (INIS)

    Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I.; Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A.

    2010-10-01

    The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY TM platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY TM platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY TM platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

  18. Controllable Tamm states in magnetophotonic crystal

    Energy Technology Data Exchange (ETDEWEB)

    Merzlikin, A.M. [Institute for Theoretical and Applied Electromagnetics, Russian Academy of Science, 13/19 Izhorskaya ul., 125412 Moscow (Russian Federation); Vinogradov, A.P. [Institute for Theoretical and Applied Electromagnetics, Russian Academy of Science, 13/19 Izhorskaya ul., 125412 Moscow (Russian Federation)]. E-mail: a-vinogr@yandex.ru; Dorofeenko, A.V. [Institute for Theoretical and Applied Electromagnetics, Russian Academy of Science, 13/19 Izhorskaya ul., 125412 Moscow (Russian Federation); Inoue, M. [Department of Electrical and Electronic Engineering, Toyohashi University of Technology, 1-1 Hibari-Ga-Oka, Tempaku, Toyohashi 441-8580 (Japan); Levy, M. [Department of Physics, Michigan Technological University, 1400 Townsend Drive Houghton, MI 49931-1295 (United States); Granovsky, A.B. [Faculty of Physics, M.V. Lomonosov Moscow State University, Vorob' evy Gory, 119992 Moscow (Russian Federation)

    2007-05-15

    We study the Tamm states existing at the interface of a 1D magnetophotonic crystal made of magneto-optic material and a material with natural anisotropy. It is shown that in such a photonic crystal (PC) Yeh's band gap may exist, which causes a special type of the Tamm state. As this state is due to magneto-optic properties, it is controllable by an external magnetic field.

  19. Controllable Tamm states in magnetophotonic crystal

    International Nuclear Information System (INIS)

    Merzlikin, A.M.; Vinogradov, A.P.; Dorofeenko, A.V.; Inoue, M.; Levy, M.; Granovsky, A.B.

    2007-01-01

    We study the Tamm states existing at the interface of a 1D magnetophotonic crystal made of magneto-optic material and a material with natural anisotropy. It is shown that in such a photonic crystal (PC) Yeh's band gap may exist, which causes a special type of the Tamm state. As this state is due to magneto-optic properties, it is controllable by an external magnetic field

  20. Instrumentation and Controls Division annual progress report for period ending September 1, 1974. Non-LMFBR program

    International Nuclear Information System (INIS)

    Sadowski, G.S.

    1976-09-01

    Research projects are summarized under the following categories: (1) basic electronics development; (2) engineering support for research facilities; (3) pulse counting and analysis; (4) radiation detection and monitoring; (5) instrument development; (6) automatic control and data acquisition; (7) process systems and instrumentation development; (8) reactor instrumentation and controls; (9) fuel reprocessing and shipping; (10) standards laboratory; (11) instrumentation for reactor division experiments and test loops; (12) maintenance and service; (13) ecological science studies; and (14) administration and training

  1. Instrumentation and Controls Division annual progress report for period ending September 1, 1974. Non-LMFBR program

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, G.S. (comp.)

    1976-09-01

    Research projects are summarized under the following categories: (1) basic electronics development; (2) engineering support for research facilities; (3) pulse counting and analysis; (4) radiation detection and monitoring; (5) instrument development; (6) automatic control and data acquisition; (7) process systems and instrumentation development; (8) reactor instrumentation and controls; (9) fuel reprocessing and shipping; (10) standards laboratory; (11) instrumentation for reactor division experiments and test loops; (12) maintenance and service; (13) ecological science studies; and (14) administration and training. (WHK)

  2. Instrumentation and Controls Division progress report for the period July 1, 1988 to June 30, 1990

    International Nuclear Information System (INIS)

    Klobe, L.E.

    1990-12-01

    The format of this Instrumentation and Controls Division progress report is a major departure from previous reports. This report has been published in two volumes instead of one, and the description of individual activities have been shortened considerably to make it easier document to scan and to read. Volume 1 of this report presents brief descriptions of a few highly significant programmatic and technological efforts representative of Instrumentation and Controls Division activities over the past two years. This volume contains information concerning the publications, presentations, and other professional activities and achievements of I ampersand C Division staff members

  3. 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)

  4. Instrumentation and Controls Division progress report for the period July 1, 1988 to June 30, 1990

    Energy Technology Data Exchange (ETDEWEB)

    Klobe, L.E. (ed.)

    1990-12-01

    The format of this Instrumentation and Controls Division progress report is a major departure from previous reports. This report has been published in two volumes instead of one, and the description of individual activities have been shortened considerably to make it easier document to scan and to read. Volume 1 of this report presents brief descriptions of a few highly significant programmatic and technological efforts representative of Instrumentation and Controls Division activities over the past two years. This volume contains information concerning the publications, presentations, and other professional activities and achievements of I C Division staff members.

  5. Power plant instrumentation and control handbook a guide to thermal power plants

    CERN Document Server

    Basu, Swapan

    2014-01-01

    The book discusses instrumentation and control in modern fossil fuel power plants, with an emphasis on selecting the most appropriate systems subject to constraints engineers have for their projects. It provides all the plant process and design details, including specification sheets and standards currently followed in the plant. Among the unique features of the book are the inclusion of control loop strategies and BMS/FSSS step by step logic, coverage of analytical instruments and technologies for pollution and energy savings, and coverage of the trends toward filed bus systems and integratio

  6. 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

  7. Proceedings of the third national symposium on advances in control and instrumentation

    International Nuclear Information System (INIS)

    Tiwari, A.P.; Chauhan, Vikas; Wakankar, Amol; Karnani, Urvashi; Saxena, Nikhil; Haridasan, Remya; Mishra, Elina

    2014-01-01

    Control and Instrumentation systems play a vital role in nuclear energy, defence, aerospace, discovery science and transportation sectors. These systems are deployed in safety-critical and mission critical applications as well. Advances in these fields have profound impact on performance, quality, reliability, safety, security and economics of these systems. While the basic theme of the symposium is control and instrumentation, this time the coverage of the symposium has been extended to defence, aerospace, discovery science and transportation sectors besides nuclear energy. This was been motivated by the need for synergy and sharing of experiences among these vital, high technology sectors. Papers relevant to INIS are indexed separately

  8. 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)

  9. Development and Validation of Mechanical Engineering Trade Skills Assessment Instrument for Sustainable Job Security in Yobe State

    Science.gov (United States)

    Adamu, Gishua Garba; Dawha, Josphine Musa; Kamar, Tiamiyu Salihu

    2015-01-01

    Mechanical Engineering Trade Skills Assessment Instrument (METSAI) is aimed at determining the extent to which students have acquired practical skills before graduation that will enable them get employment for sustainable job security in Yobe state. The study employed instrumentation research design. The populations of the study were 23 mechanical…

  10. A cross-platform GUI to control instruments compliant with SCPI through VISA

    Science.gov (United States)

    Roach, Eric; Liu, Jing

    2015-10-01

    In nuclear physics experiments, it is necessary and important to control instruments from a PC, which automates many tasks that require human operations otherwise. Not only does this make long term measurements possible, but it also makes repetitive operations less error-prone. We created a graphical user interface (GUI) to control instruments connected to a PC through RS232, USB, LAN, etc. The GUI is developed using Qt Creator, a cross-platform integrated development environment, which makes it portable to various operating systems, including those commonly used in mobile devices. NI-VISA library is used in the back end so that the GUI can be used to control instruments connected through various I/O interfaces without any modification. Commonly used SCPI commands can be sent to different instruments using buttons, sliders, knobs, and other various widgets provided by Qt Creator. As an example, we demonstrate how we set and fetch parameters and how to retrieve and display data from an Agilent Digital Storage Oscilloscope X3034A with the GUI. Our GUI can be easily used for other instruments compliant with SCPI and VISA with little or no modification.

  11. Instrumentation and Controls Division progress report for the period July 1, 1986 to June 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Klobe, L.E. (ed.)

    1988-12-01

    The Instrumentation and Controls (IandC) Division of Oak Ridge National Laboratory (ORNL) performs basic and applied instrumentation and controls research, development and design engineering, specialized instrument design and fabrication, and maintenance services for instruments, electronics, and computers. The IandC Division is one of the largest RandD organizations of its type among government laboratories, and it exists as the result of an organizational strategy to integrate ORNL's instrumentation and controls-related disciplines into one dedicated functional organization to increase the Laboratory's expertise and capabilities in these rapidly expanding, innovative areas of technology. The Division participates in the programs and projects of ORNL by applying its expertise and capabilities in concert with other divisions to perform basic research and mission-oriented technology development. Many of the Division's RandD tasks that are a part of a larger ORNL program are of sufficient scope that the IandC effort constitutes a separate program element with direct funding and management responsibility within the Division. The activities of IandC include performance of an RandD task in IandC facilities, the participation of from one of many IandC engineers and scientists in a multidisciplinary team working in a specific research area or development project, design and fabrication of a special instrument or instrumentation system, or a few hours of maintenance service. In its support and maintenance work, the role of the IandC Division is to provide a level of expertise appropriate to complete a job successfully at minimum overall cost and time schedule---a role which involves IandC in almost all ORNL activities.

  12. Instrumentation and Controls Division progress report for the period July 1, 1986 to June 30, 1988

    International Nuclear Information System (INIS)

    Klobe, L.E.

    1988-12-01

    The Instrumentation and Controls (IandC) Division of Oak Ridge National Laboratory (ORNL) performs basic and applied instrumentation and controls research, development and design engineering, specialized instrument design and fabrication, and maintenance services for instruments, electronics, and computers. The IandC Division is one of the largest RandD organizations of its type among government laboratories, and it exists as the result of an organizational strategy to integrate ORNL's instrumentation and controls-related disciplines into one dedicated functional organization to increase the Laboratory's expertise and capabilities in these rapidly expanding, innovative areas of technology. The Division participates in the programs and projects of ORNL by applying its expertise and capabilities in concert with other divisions to perform basic research and mission-oriented technology development. Many of the Division's RandD tasks that are a part of a larger ORNL program are of sufficient scope that the IandC effort constitutes a separate program element with direct funding and management responsibility within the Division. The activities of IandC include performance of an RandD task in IandC facilities, the participation of from one of many IandC engineers and scientists in a multidisciplinary team working in a specific research area or development project, design and fabrication of a special instrument or instrumentation system, or a few hours of maintenance service. In its support and maintenance work, the role of the IandC Division is to provide a level of expertise appropriate to complete a job successfully at minimum overall cost and time schedule---a role which involves IandC in almost all ORNL activities

  13. Semiglobal H-infty state feedback control

    DEFF Research Database (Denmark)

    Cromme, Marc

    1997-01-01

    semi-global set-stabilizing H-infty control is local H-infty control within some given compact set O such that all state trajectories are bounded inside O, and are approaching an open loop invariant set S subset O as t -> infinity. Sufficient conditions for the existance of a continuous statefeed...

  14. Quality control of nuclear medicine instruments, 1991; Control de calidad de los instrumentos de medicina nuclear, 1991

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    This document gives detailed guidance on the quality control of various instruments used in nuclear medicine. A first preliminary document was drawn up in 1979. A revised and extended version, incorporating recommended procedures, test schedules and protocols was prepared in 1982. The first edition of 'Quality Control of Nuclear Medicine Instruments', IAEA-TECDOC-317, was printed in late 1984. Recent advances in the field of nuclear medicine imaging made it necessary to add a chapter on Camera-Computer Systems and another on SPECT Systems.

  15. The law as an instrument of technology control and as a basis for technological development

    International Nuclear Information System (INIS)

    Kloepfer, M.

    1998-01-01

    In public debates about German industry's global competitiveness it becomes evident that environmental law and the technology-related law are almost exclusively perceived as systems of law which - for reasons of environmental protection and protection of public health - are setting restraints to technological development. This is a narrow perspective neglecting the functions of the law as an instrument providing legal security and a reliable framework for developments. In a democratic, constitutional state, the environmental law and the technology-related law are instruments providing for protection of the basic, general rights and requirements of technology, and contribute to ensuring general acceptance of technologic development. (orig./CB) [de

  16. Detecting charging state of ultra-fine particles: instrumental development and ambient measurements

    Directory of Open Access Journals (Sweden)

    L. Laakso

    2007-01-01

    Full Text Available The importance of ion-induced nucleation in the lower atmosphere has been discussed for a long time. In this article we describe a new instrumental setup – Ion-DMPS – which can be used to detect contribution of ion-induced nucleation on atmospheric new particle formation events. The device measures positively and negatively charged particles with and without a bipolar charger. The ratio between "charger off" to "charger on" describes the charging state of aerosol particle population with respect to equilibrium. Values above one represent more charges than in an equilibrium (overcharged state, and values below unity stand for undercharged situation, when there is less charges in the particles than in the equilibrium. We performed several laboratory experiments to test the operation of the instrument. After the laboratory tests, we used the device to observe particle size distributions during atmospheric new particle formation in a boreal forest. We found that some of the events were clearly dominated by neutral nucleation but in some cases also ion-induced nucleation contributed to the new particle formation. We also found that negative and positive ions (charged particles behaved in a different manner, days with negative overcharging were more frequent than days with positive overcharging.

  17. Mass Alarms in Main Control Room Caused Condensate on the Instrumentation and Control Cards in Turbine Building

    International Nuclear Information System (INIS)

    Goo, Cheol-Soo

    2015-01-01

    A bunch of alarms and trouble lights on the main control room simultaneously turned on during inspection and exchange of the coolers of the turbine building at pressurized water reactor of the Hanbit nuclear power plant No. 6. The main cause was condensate on instrumentation cards of plant control system (PCS) installed at enclosures in the turbine building which have MUX cabinets to transmit signals between the main control room and local equipment. To control the temperature and humidity of the MUX cabinets, two coolers of the plant chilled water system supply air to the compact enclosures at turbine building where temperature and humidity is high in the summer. It is an unusual experience that mass alarms abnormally were occurred in the main control room during normal plant operation phases. Spurious signals with unknown cause at control and instrumentation system occasionally may have an unnecessary actuation of monitoring equipment and a plant scram even. One of the main causes is humidity by a rapid temperature change of the control and instrumentation cards. Dew on the instrumentation cards could form an abnormal short circuit in printed circuit board with the compact circuits and make any malfunction of the related system. Instrumentation and control cards with integrated circuits are vulnerable to high humidity and temperature where the system is enclosed in a small housing or enclosure surrounding with hash environment such as a turbine building. It was found that there was no functional degradation of the safety systems and no outsides releases of radioactive materials by this occurrence. (author)

  18. Instrumentation and control activities at the Electric Power Research Institute to support operator support systems

    International Nuclear Information System (INIS)

    Naser, J.

    1995-01-01

    Most nuclear power plants in the United States continue to operate with analog instrumentation and control (I and C) technology designed 20 to 40 years ago. This equipment is approaching or exceeding its life expectancy, resulting in increasing maintenance efforts to sustain system performance. Decreasing availability of replacement parts and the accelerating deterioration of the infrastructure of manufacturers that support analog technology exacerbate obsolescence problems and resultant operation and maintenance (O and M) cost increases. Modern digital technology holds a significant potential to improve the safety, cost-effectiveness, productivity, and, therefore, competitiveness of nuclear power plants. Operator support systems provide the tools to help achieve this potential. Reliable, integrated information is a critical element for protecting the utility's capital investment and increasing availability, reliability, and productivity. Integrated operator support systems with integrated information can perform more effectively to increase productivity, to enhance safety, and to reduce O and M costs. The plant communications and computing architecture is the infrastructure needed to allow the implementation of I and C systems and associated operator support systems in an integrated manner. Current technology for distributed digital systems, plant process computers, and plant communications and computing networks support the integration of systems and information. (author). 16 refs

  19. ATTA-3: a State-of-the-Art Instrument for Radio-Krypton Dating

    Science.gov (United States)

    Jiang, W.; Zappala, J. C.; Bailey, K.; Lu, Z.; Müller, P.; O'Connor, T. P.

    2013-12-01

    The ATTA-3 instrument at Argonne has recently enabled routine Kr-81 dating. The instrument is based on Atom Trap Trace Analysis (ATTA), a novel laser based atom counting technique that allows detection of long lived noble gas radioisotopes (Kr-81, Kr-85 and Ar-39) with extremely low abundance (1E-16 to 1E-10). At the center of the instrument is a magneto-optical trap (MOT), which traps and counts only the atoms of the desired isotope. This unique feature makes ATTA free of interference from any other isotopes or molecular species. For Kr-81 dating in the age range of 150 - 1,500 kyr, the required sample size is 5 - 10 micro-L STP of krypton gas, which can be extracted from approximately 100 - 200 kg of water or 40 - 80 kg of ice. Several recent developments in our lab may lead to further improvements to the current ATTA-3 apparatus: 1) The isotopic abundance ratio between the unknown, rare isotope (either Kr-81 or Kr-85) and the stable, abundant isotope (Kr-83) is measured. Here the stable isotope serves as a control isotope. A new method has been developed that allows more accurate measurements of the control isotope Kr-83. Combined with the ability to measure the rare Kr-81 and Kr-85 isotopes, this scheme allows ATTA-3 to directly determine 81Kr/Kr and 85Kr/Kr ratios without other supplemental measurements, to reduce the overall uncertainties of the measured isotope ratios, and also to improve the long term stability of the system. 2) The current capacity of the ATTA-3 instrument is about 120 samples per year. The throughput is mainly limited by the so called 'memory effect', which is caused by the residual samples trapped in the system after each measurement. These residual samples are gradually released in subsequent measurements, causing cross-sample contaminations. In order to mitigate this problem, we wash the system with a xenon discharge for about 36 hours between measurements. This practice limits the overall sample processing speed. Preliminary

  20. Effect of environment on fatigue failure of controlled memory wire nickel-titanium rotary instruments.

    Science.gov (United States)

    Shen, Ya; Qian, Wei; Abtin, Houman; Gao, Yuan; Haapasalo, Markus

    2012-03-01

    This study examined the fatigue behavior of 2 types of nickel-titanium (NiTi) instruments made from a novel controlled memory NiTi wire (CM wire) under various environment conditions. Three conventional superelastic NiTi instruments of ProFile (Dentsply Maillefer, Ballaigues, Switzerland), Typhoon (Clinician's Choice Dental Products, New Milford, CT), and DS-SS0250425NEYY (Clinician's Choice Dental Products) and 2 new CM wire instruments of Typhoon CM and DS-SS0250425NEYY CM were subjected to rotational bending at the curvature of 35° in air, deionized water, 17% EDTA, or deionized water after immersion in 6% sodium hypochlorite for 25 minutes, and the number of revolutions of fracture (N(f)) was recorded. The fracture surface of all fragments was examined by a scanning electron microscope. The crack-initiation sites and the percentage of dimple area to the whole fracture cross-section were noted. Two new CM Wire instruments yielded an improvement of >4 to 9 times in N(f) than conventional NiTi files with the same design under various environments (P Wire instruments was significantly longer in liquid media than in air (P wire had one crack origin. The values of the area fraction occupied by the dimple region were significantly smaller on CM NiTi instruments than in conventional NiTi instruments under various environments (P < .05). Within the limitations of this study, the type of NiTi metal alloy (CM files vs conventional superelastic NiTi files) influences the cyclic fatigue resistance under various environments. The fatigue life of CM instruments is longer in liquid media than in air. Copyright © 2012 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

  1. Replacement of the control and instrumentation system with the microprocessor based systems in Japanese PWR plants

    International Nuclear Information System (INIS)

    Hayashi, N.

    1998-01-01

    In Ohi Units 3 and 4, Ikata Unit 3, and Genkai Units 3 and 4, the latest of PWR plants now under operation in Japan, the reactor control system and turbine control system employ the microprocessor base digital control systems with a view to improving reliability, operability and maintainability. In the next stage plants, another application of such digital system is also planned for the instrumentation rack for the reactor protection system for further improvement. On the other hand, in Mihama Unit 1, the first of domestic PWR plants, and later plants except for the latest 5 plants, analog control systems are employed for the instrumentation racks. For the analog control systems of these plants, FOXBORO H-Line instruments, equivalent domestic box type instruments or WH7300 Series card type instruments were initially employed, and later replaced with domestic card type control systems after 10-15 year operation. However, 8-12 years have passed since these replacements, so the 15th year generally quoted as an interval for replacing C and I systems is near at hand. This is the time to consider next replacement. This replacement will be based on the latest digital technology. However, it is not practical way for the existing plants to apply the same integrated digital C and I system configuration for the next stage plants, because it requires the drastic change of the C and I system configuration and significant cost-up. Therefore, we must investigate the optimum digital C and I system configuration for the existing system. (author)

  2. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''P''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

  3. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid ''P''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Report (ATR) provides the test results for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''P''. The ATR summaries the results and provides a copy of the ATP and inspections in the Appendix

  4. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid Q

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

  5. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid N

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5489. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''N''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

  6. Acceptance Test Procedure for New Pumping and Instrumentation Control Skid M

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This Acceptance Test Procedure (ATP) verifies proper construction per the design drawings and tests for proper functioning of the Pumping and Instrumentation Control (PIC) skid ''M''. The Scope section lists the systems and functions to be checked. This ATP will be performed at the Site Fabrication Service's (SFS) shop upon completion of construction of the PIC skid

  7. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid M

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5073. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''M''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

  8. Instrument for bone mineral measurement using a microprocessor as the control and arithmetic element

    International Nuclear Information System (INIS)

    Alberi, J.L.; Hardy, W.H. II.

    1975-11-01

    A self-contained instrument for the determination of bone mineral content by photon absorptometry is described. A high-resolution detection system allows measurements to be made at up to 16 photon energies. Control and arithmetic functions are performed by a microprocessor. Analysis capability and limitations are discussed

  9. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid L

    Energy Technology Data Exchange (ETDEWEB)

    KOCH, M.R.

    1999-11-09

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5055. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''L''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document.

  10. Submicronic Particle Measurement Instrumentation Test Bench Data Acquisition and Control System

    International Nuclear Information System (INIS)

    Alberdi, J.; Barcala, J. M.; Sanz, D.; Gomez, F. J.; Molinero, A.; Navarrete, J. J.

    1999-01-01

    This document describes the SAD-100 system characteristics. The unit makes the instrumentation test bench data acquisition and control, SAD-100 was designed and developed by Electronic and Automation Area (CIEMAT) and Aerosol Technology in Energy Generation Project (CIEMAT). (Author) 2 refs

  11. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''V''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) verifies proper construction per the design drawings and tests for proper functioning of the Pumping Instrumentation and Control (PIC) skid ''V''. The scope section lists the systems and functions to be checked. This ATP will be performed at the Site Fabrication Services (SFS) shop upon completion of the construction of the PIC skid

  12. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid Q

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Report (ATR) provides the test results for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''Q''. The ATR summaries the results and provides a copy of the ATP and inspections in the Appendix

  13. On safety classification of instrumentation and control systems and their components

    International Nuclear Information System (INIS)

    Yastrebenetskij, M.A.; Rozen, Yu.V.

    2004-01-01

    Safety classification of instrumentation and control systems (I and C) and their components (hardware, software, software-hardware complexes) is described: - evaluation of classification principles and criteria in Ukrainian standards and rules; comparison between Ukrainian and international principles and criteria; possibility and ways of coordination of Ukrainian and international standards related to (I and C) safety classification

  14. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid L

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5055. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''L''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

  15. Proceedings of the 1980 symposium on instrumentation and control for fossil energy processes

    Energy Technology Data Exchange (ETDEWEB)

    Doering, R.W. (comp.)

    1980-01-01

    The 1980 symposium on Instrumentation and Control for Fossil Energy Processes was held June 9-11, 1980, New Cavalier, Virginia Beach, Virginia. It was sponsored by the Argonne National Laboratory and the US Department of Energy, Office of Fossil Energy. Forty-five papers have been entered individually into EDB and ERA; nine papers had been entered previously from other sources. (LTN)

  16. Control and instrumentation system of the Zero Power Reactor at IEA, Sao Paulo (Brazil)

    International Nuclear Information System (INIS)

    Peluso, M.A.V.; Matsuda, K.; Hukai, R.

    1974-01-01

    The control and instrumentation system of the Zero Power Reactor at the IEA (Institute of Atomic Energy - Sao Paulo, Brazil) is described. Technical specifications of the main items of equipment are presented in a general way. Information is also given on the connection between the system described and the electrical supply system of the IEA reactor physics laboratory [pt

  17. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid M

    Energy Technology Data Exchange (ETDEWEB)

    KOCH, M.R.

    1999-12-13

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5073. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''M''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document.

  18. Construction of control and instrumentation devices of high voltage power supply of double chamber plasma nitrogen

    International Nuclear Information System (INIS)

    Saminto; Eko Priyono; Sugeng Riyanto

    2013-01-01

    A control and instrumentation devices of high voltage power supply of double chamber plasma nitrogen have been made. This device consists of the software and hardware component. Hardware component consists of SCR phase angle controller LPC-50HDA type, T100MD1616+ PLC, high voltage transformer and voltage rectifier system. Software component used a LADDER program and TBasic serves to control of the high voltage output. The components in these devices have been tested in the double chamber plasma nitrogen. Its performance meet with the design criteria that can supply of plasma nitrogen operation voltage in the range 290 Vdc to 851 Vdc with glow discharge current 0.4 A to 1.4 A. In general it can be said that the control and instrumentation devices of high voltage power supply is ready for use at the double chamber plasma nitrogen device. (author)

  19. Maximizing kinetic performance in supercritical fluid chromatography using state-of-the-art instruments.

    Science.gov (United States)

    Grand-Guillaume Perrenoud, Alexandre; Hamman, Chris; Goel, Meenakshi; Veuthey, Jean-Luc; Guillarme, Davy; Fekete, Szabolcs

    2013-11-01

    Recently, there has been a renewed interest in supercritical fluid chromatography (SFC), due to the introduction of state-of-the-art instruments and dedicated columns packed with small particles. However, the achievable kinetic performance and practical possibilities of such modern SFC instruments and columns has not been described in details until now. The goal of the present contribution was to provide some information about the optimal column dimensions (i.e. length, diameter and particle size) suitable for such state-of the-art systems, with respect to extra-column band broadening and system upper pressure limit. In addition, the reliability of the kinetic plot methodology, successfully applied in RPLC, was also evaluated under SFC conditions. Taking into account the system variance, measured at ∼85μL(2), on modern SFC instruments, a column of 3mm I.D. was ideally suited for the current technology, as the loss in efficiency remained reasonable (i.e. less than 10% decrease for k>6). Conversely, these systems struggle with 2.1mm I.D. columns (55% loss in N for k=5). Regarding particle size, columns packed with 5μm particles provided unexpectedly high minimum reduced plate height values (hmin=3.0-3.4), while the 3.5 and 1.7μm packing provided lower reduced plate heights hmin=2.2-2.4 and hmin=2.7-3.2, respectively. Considering the system upper pressure limit, it appears that columns packed with 1.7μm particles give the lowest analysis time for efficiencies up to 40,000-60,000 plates, if the mobile phase composition is in the range of 2-19% MeOH. The 3.5μm particles were attractive for higher efficiencies, particularly when the modifier percentage was above 20%, while 5μm was never kinetically relevant with modern SFC instruments, due to an obvious limitation in terms of upper flow rate value. The present work also confirms that the kinetic plot methodology could be successfully applied to SFC, without the need for isopycnic measurements, as the difference

  20. 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

  1. Robust hydraulic position controller by a fuzzy state controller

    International Nuclear Information System (INIS)

    Zhao, T.; Van der Wal, A.J.

    1994-01-01

    In nuclear industry, one of the most important design considerations of controllers is their robustness. Robustness in this context is defined as the ability of a system to be controlled in a stable way over a wide range of system parameters. Generally the systems to be controlled are linearized, and stability is subsequently proven for this idealized system. By combining classical control theory and fuzzy set theory, a new kind of state controller is proposed and successfully applied to a hydraulic position servo with excellent robustness against variation of system parameters

  2. 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)

  3. Control architecture for an adaptive electronically steerable flash lidar and associated instruments

    Science.gov (United States)

    Ruppert, Lyle; Craner, Jeremy; Harris, Timothy

    2014-09-01

    An Electronically Steerable Flash Lidar (ESFL), developed by Ball Aerospace & Technologies Corporation, allows realtime adaptive control of configuration and data-collection strategy based on recent or concurrent observations and changing situations. This paper reviews, at a high level, some of the algorithms and control architecture built into ESFL. Using ESFL as an example, it also discusses the merits and utility such adaptable instruments in Earth-system studies.

  4. Instrumentation and Controls Division Progress report, July 1, 1992--June 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    McDonald, D.W.

    1995-06-01

    The Instrumentation and Controls (I&C) Division serves a national laboratory, and as such has an expansive domain: science, industry, and national defense. The core mission is to support the scientific apparatus of the Laboratory and all of the systems that protect the safety and health of people and the environment. Progress is reported for the five sections: photonics and measurements systems, electronic systems, signal processing, controls and systems integration, and technical support.

  5. The NERA-PR instrument control software: experience of using the VME-PCI adapter

    International Nuclear Information System (INIS)

    Kirilov, A.S.; Astakhova, N.V.; Murashkevich, S.M.; Petukhova, T.B.; Yudin, V.E.

    2003-01-01

    The intermediate results for modernization of the control system for the NERA-PR instrument on the base of a VME-PCI adapter are considered. The article is mostly devoted to the software of the new system. The structure, the new user interface and the method for remote control are described. A half-year testing showed that the new system is reliable and is attractive for users. (author)

  6. Radioisotope instruments

    CERN Document Server

    Cameron, J F; Silverleaf, D J

    1971-01-01

    International Series of Monographs in Nuclear Energy, Volume 107: Radioisotope Instruments, Part 1 focuses on the design and applications of instruments based on the radiation released by radioactive substances. The book first offers information on the physical basis of radioisotope instruments; technical and economic advantages of radioisotope instruments; and radiation hazard. The manuscript then discusses commercial radioisotope instruments, including radiation sources and detectors, computing and control units, and measuring heads. The text describes the applications of radioisotop

  7. Microprocessor-controlled data-acquisition instrument for neutron-activation measurements

    International Nuclear Information System (INIS)

    Jones, B.A.

    1981-01-01

    This paper describes a microprocessor controlled data acquisition instrument designed at Lawrence Livermore National Laboratory to provide experimenters with a diagnostic tool for measuring the performance of laser imploded fusion targets via neutron activation techniques. This instrument features the ability to count four independent inputs simultaneously while providing a front panel readout of these inputs, plus a time of day clock. A hardcopy printout of the data is also provided by a built-in thermal printer. All running modes and parameters are user selectable via a front panel keypad, and a complete set of internal self-testing diagnostics are available for debug

  8. Data acquisition and control system for the IPNS time-of-flight neutron scattering instruments

    International Nuclear Information System (INIS)

    Daly, R.T.; Haumann, J.R.; Kraimer, M.R.; Lenkszus, F.R.; Lidinsky, W.P.; Morgan, C.B.; Rutledge, L.L.; Rynes, P.E.; Tippie, J.W.

    1979-01-01

    The Argonne Intense Pulsed Neutron System (IPNS-I) presently under construction at Argonne National Laboratory will include a number of neutron scattering instruments. This study investigates the data acquisition requirements of these instruments and proposes three alternative multiprocessor systems which will satisfy these requirements. All proposals are star configurations with a super-mini as the central node or HOST. The first proposal is based on front-ends composed of two or more 16-bit microcomputers, the second proposal is based on front ends consisting of a combination of a mini and microcomputers, and the third is based on a minicomputer with an intelligent CAMAC controller

  9. Use of spreadsheets for interactive control of MFTF-B plasma diagnostic instruments

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Goldner, A.L.; Kobayashi, A.

    1986-01-01

    The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory has a variety of highly individualized plasma diagnostic instruments attached to the experiment. These instruments are controlled through graphics workstations networked to a central computer system. A distributed spreadsheet-like program runs in both the graphics workstations and in the central computer system. An interface very similar to a commercial spreadsheet program is presented to the user at a workstation. In a commercial spreadsheet program, the user may attach mathematical calculation functions to spreadsheet cells. At MFTF-B, hardware control functions, hardware monitoring functions, and communications functions, as well as mathematical functions, may be attached to cells. Both the user and feedback from instrument hardware may make entries in spreadsheet cells; any entry in a spreadsheet cell may cause reevaluation of the cell's associated functions. The spreadsheet approach makes the addition of a new instrument a matter of designing one or more spreadsheet tables with associated meta-language-defined control and communication function strings. This paper describes the details of the spreadsheets and the implementation experience

  10. Use of spreadsheets for interactive control of MFTF-B plasma diagnostic instruments

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Goldner, A.; Kobayashi, A.

    1985-01-01

    The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory has a variety of highly individualized plasma diagnostic instruments attached to the experiment. These instruments are controlled through graphics workstations networked to a central computer system. A distributed spreadsheet-like program runs in both the graphics workstations and in the central computer system. An interface very similar to a commercial spreadsheet program is presented to the user at a workstation. In a commercial spreadsheet program, the user may attach mathematical calculation functions to spreadsheet cells. At MFTF-B, hardware control functions, hardware monitoring functions, and communications functions, as well as mathematical functions, may be attached to cells. Both the user and feedback from instrument hardware may make entries in spreadsheet cells; any entry in a spreadsheet cell may cause reevaluation of the cell's associated functions. The spreadsheet approach makes the addition of a new instrument a matter of designing one or more spreadsheet tables with associated meta-language-defined control and communication function strings. We report here details of our spreadsheets and our implementation experience

  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. Instrumentation and controls training in TVA: a story of large numbers

    International Nuclear Information System (INIS)

    Conner, D.L.

    1981-01-01

    The Tennessee Valley Authority currently has four nuclear units on line with seventeen units planned prior to the year 2000. Providing a permanent instrumentation and controls workforce, projected to be approximately 700 trades and labor craftsmen, is a formidable task requiring the cooperative efforts of many diverse groups: mangement and labor, engineers and craftsmen, students and instructors. In TVA, the primary source of skilled I and C craftsmen is through formal training programs conducted in cooperation with the craft bargaining unit, the International Brotherhood of Electrical Workers. The purpose of this paper is to describe and review the progress of two of these programs: the Instrument Mechanic Training Program and the Senior Instrument Mechanic Training Program

  13. Predator control promotes invasive dominated ecological states.

    Science.gov (United States)

    Wallach, Arian D; Johnson, Christopher N; Ritchie, Euan G; O'Neill, Adam J

    2010-08-01

    Invasive species are regarded as one of the top five drivers of the global extinction crisis. In response, extreme measures have been applied in an attempt to control or eradicate invasives, with little success overall. We tested the idea that state shifts to invasive dominance are symptomatic of losses in ecosystem resilience, due to the suppression of apex predators. This concept was investigated in Australia where the high rate of mammalian extinctions is largely attributed to the destructive influence of invasive species. Intensive pest control is widely applied across the continent, simultaneously eliminating Australia's apex predator, the dingo (Canis lupus dingo). We show that predator management accounts for shifts between two main ecosystem states. Lethal control fractures dingo social structure and leads to bottom-up driven increases in invasive mesopredators and herbivores. Where control is relaxed, dingoes re-establish top-down regulation of ecosystems, allowing for the recovery of biodiversity and productivity.

  14. WTEC panel report on European nuclear instrumentation and controls. Final report

    Energy Technology Data Exchange (ETDEWEB)

    White, J.D.; Lanning, D.D.; Johnson, P.M.H. [eds.] [World Technology Evaluation Center, Baltimore, MD (United States); Shelton, R.D. [World Technology Evaluation Center, Baltimore, MD (United States)

    1991-12-01

    A study of instrumentation and controls (I and C) technology used in nuclear power plants in Europe was conducted by a panel of US specialists. This study plants in Europe was conducted by a panel of US specialists. This study included a review of the literature on the subject, followed by a visit to some of the leading organizations in Europe in the field nuclear I and C. Areas covered are: (1) role of the operator and control room design; (2) transition from analog to digital technology; (3) computerized operator support systems for fault management; (4) control strategies and techniques; (5) Nuclear power plant I and C architecture; (6) instrumentation and (7) computer standards and tools. The finding relate to poor reactions.

  15. 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

  16. WTEC panel report on European nuclear instrumentation and controls. Final report

    International Nuclear Information System (INIS)

    White, J.D.; Lanning, D.D.; Beltracchi, L.; Best, F.R.; Easter, J.R.

    1991-12-01

    A study of instrumentation and controls (I and C) technology used in nuclear power plants in Europe was conducted by a panel of American specialists. The study included a review of the literature on the subject, followed by a visit to some of the leading organizations in Europe in the field of nuclear I and C. The findings of the study are presented in the report. The scope is limited to pressurized water reactors in Czechoslovakia, France, Germany, Norway and Russia. Specific topics include: The role of the operator and control room design; the transition from analog to digital technology; computerized operator support systems for fault management; control strategies and techniques; an investigation of nuclear power plant I and C architecture; instrumentation; computer standards and tools. A companion study is JTEC Panel Report on Nuclear Power in Japan (PB90-215724)

  17. Probabilistic risk assessment modeling of digital instrumentation and control systems using two dynamic methodologies

    Energy Technology Data Exchange (ETDEWEB)

    Aldemir, T., E-mail: aldemir.1@osu.ed [Ohio State University, Nuclear Engineering Program, Columbus, OH 43210 (United States); Guarro, S. [ASCA, Inc., 1720 S. Catalina Avenue, Suite 220, Redondo Beach, CA 90277-5501 (United States); Mandelli, D. [Ohio State University, Nuclear Engineering Program, Columbus, OH 43210 (United States); Kirschenbaum, J. [Ohio State University, Department of Computer Science and Engineering, Columbus, OH 43210 (United States); Mangan, L.A. [Ohio State University, Nuclear Engineering Program, Columbus, OH 43210 (United States); Bucci, P. [Ohio State University, Department of Computer Science and Engineering, Columbus, OH 43210 (United States); Yau, M. [ASCA, Inc., 1720 S. Catalina Avenue, Suite 220, Redondo Beach, CA 90277-5501 (United States); Ekici, E. [Ohio State University, Department of Electrical and Computer Engineering, Columbus, OH 43210 (United States); Miller, D.W.; Sun, X. [Ohio State University, Nuclear Engineering Program, Columbus, OH 43210 (United States); Arndt, S.A. [U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 (United States)

    2010-10-15

    The Markov/cell-to-cell mapping technique (CCMT) and the dynamic flowgraph methodology (DFM) are two system logic modeling methodologies that have been proposed to address the dynamic characteristics of digital instrumentation and control (I and C) systems and provide risk-analytical capabilities that supplement those provided by traditional probabilistic risk assessment (PRA) techniques for nuclear power plants. Both methodologies utilize a discrete state, multi-valued logic representation of the digital I and C system. For probabilistic quantification purposes, both techniques require the estimation of the probabilities of basic system failure modes, including digital I and C software failure modes, that appear in the prime implicants identified as contributors to a given system event of interest. As in any other system modeling process, the accuracy and predictive value of the models produced by the two techniques, depend not only on the intrinsic features of the modeling paradigm, but also and to a considerable extent on information and knowledge available to the analyst, concerning the system behavior and operation rules under normal and off-nominal conditions, and the associated controlled/monitored process dynamics. The application of the two methodologies is illustrated using a digital feedwater control system (DFWCS) similar to that of an operating pressurized water reactor. This application was carried out to demonstrate how the use of either technique, or both, can facilitate the updating of an existing nuclear power plant PRA model following an upgrade of the instrumentation and control system from analog to digital. Because of scope limitations, the focus of the demonstration of the methodologies was intentionally limited to aspects of digital I and C system behavior for which probabilistic data was on hand or could be generated within the existing project bounds of time and resources. The data used in the probabilistic quantification portion of the

  18. LabVIEW-based control software for para-hydrogen induced polarization instrumentation

    International Nuclear Information System (INIS)

    Agraz, Jose; Grunfeld, Alexander; Li, Debiao; Cunningham, Karl; Willey, Cindy; Pozos, Robert; Wagner, Shawn

    2014-01-01

    The elucidation of cell metabolic mechanisms is the modern underpinning of the diagnosis, treatment, and in some cases the prevention of disease. Para-Hydrogen induced polarization (PHIP) enhances magnetic resonance imaging (MRI) signals over 10 000 fold, allowing for the MRI of cell metabolic mechanisms. This signal enhancement is the result of hyperpolarizing endogenous substances used as contrast agents during imaging. PHIP instrumentation hyperpolarizes Carbon-13 ( 13 C) based substances using a process requiring control of a number of factors: chemical reaction timing, gas flow, monitoring of a static magnetic field (B o ), radio frequency (RF) irradiation timing, reaction temperature, and gas pressures. Current PHIP instruments manually control the hyperpolarization process resulting in the lack of the precise control of factors listed above, resulting in non-reproducible results. We discuss the design and implementation of a LabVIEW based computer program that automatically and precisely controls the delivery and manipulation of gases and samples, monitoring gas pressures, environmental temperature, and RF sample irradiation. We show that the automated control over the hyperpolarization process results in the hyperpolarization of hydroxyethylpropionate. The implementation of this software provides the fast prototyping of PHIP instrumentation for the evaluation of a myriad of 13 C based endogenous contrast agents used in molecular imaging

  19. LabVIEW-based control software for para-hydrogen induced polarization instrumentation.

    Science.gov (United States)

    Agraz, Jose; Grunfeld, Alexander; Li, Debiao; Cunningham, Karl; Willey, Cindy; Pozos, Robert; Wagner, Shawn

    2014-04-01

    The elucidation of cell metabolic mechanisms is the modern underpinning of the diagnosis, treatment, and in some cases the prevention of disease. Para-Hydrogen induced polarization (PHIP) enhances magnetic resonance imaging (MRI) signals over 10,000 fold, allowing for the MRI of cell metabolic mechanisms. This signal enhancement is the result of hyperpolarizing endogenous substances used as contrast agents during imaging. PHIP instrumentation hyperpolarizes Carbon-13 ((13)C) based substances using a process requiring control of a number of factors: chemical reaction timing, gas flow, monitoring of a static magnetic field (Bo), radio frequency (RF) irradiation timing, reaction temperature, and gas pressures. Current PHIP instruments manually control the hyperpolarization process resulting in the lack of the precise control of factors listed above, resulting in non-reproducible results. We discuss the design and implementation of a LabVIEW based computer program that automatically and precisely controls the delivery and manipulation of gases and samples, monitoring gas pressures, environmental temperature, and RF sample irradiation. We show that the automated control over the hyperpolarization process results in the hyperpolarization of hydroxyethylpropionate. The implementation of this software provides the fast prototyping of PHIP instrumentation for the evaluation of a myriad of (13)C based endogenous contrast agents used in molecular imaging.

  20. Causes and effects of vital instrumentation and control power supply bus failures

    International Nuclear Information System (INIS)

    Muhlheim, M.D.; Murphy, G.A.

    1987-01-01

    This article presents the results of a study in which the objective was to evaluate nuclear power-plant operating experience to identify the causes and the effects of vital instrumentation and control (I and C) power supply bus failures. Vital I and C power is normally provided to essential instrumentation and controls through either vital d-c or a-c power supply systems. The vital d-c power supply system generally provides control power for starting the diesel generators, for operating electrical circuit breakers, and for controlling various logic circuits. The vital d-c power system also supplies vital a-c power through an inverter. The vital a-c power supply system generally feeds the reactor protection system channels, the engineered safety features actuation system channels, and critical instrumentation in the control room. The leading cause of vital bus failures is inverter failures; other causes are human errors, battery charger failures, and miscellaneous failures. The effects of these failures are that the margin of safety can be degraded by (1) denying key information to the operators, (2) inducing plant transients, (3) causing safety injection actuations, and (4) causing the loss of shutdown cooling flow

  1. Nuclear material control in the United States

    International Nuclear Information System (INIS)

    Jaeger, C.; Waddoups, I.

    1995-01-01

    The Department of Energy has defined a safeguards system to be an integrated system of physical protection, material accounting and material control subsystems designed to deter, prevent, detect, and respond to unauthorized possession, use, or sabotage of SNM. In practice, safeguards involve the development and application of techniques and procedures dealing with the establishment and continued maintenance of a system of activities. The system must also include administrative controls and surveillance to assure that the procedures and techniques of the system are effective and are being carried out. The control of nuclear material is critical to the safeguarding of nuclear materials within the United States. The U.S. Department of Energy includes as part of material control four functional performance areas. They include access controls, material surveillance, material containment and detection/assessment. This paper will address not only these areas but also the relationship between material control and other safeguards and security functions

  2. A comparison of spent fuel assembly control instruments: The Cadarache PYTHON and the Los Alamos Fork

    International Nuclear Information System (INIS)

    Bignan, G.; Capsie, J.; Romeyer-Dherbey, J.

    1991-01-01

    Devices to monitor spent fuel assemblies while stored under water with nondestructive assay methods, have been developed in France and in the United States. Both devices are designed to verify operator's declared values of exposures and cooling-time but the applications and thus the designs of the systems differ. A study, whose results are presented in this paper, has been conducted to compare the features and the performances of the two instruments. 4 refs., 9 figs

  3. Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration

    Energy Technology Data Exchange (ETDEWEB)

    J. Wesley Hines; Belle R. Upadhyaya; J. Michael Doster; Robert M. Edwards; Kenneth D. Lewis; Paul Turinsky; Jamie Coble

    2011-05-31

    on meeting two of the eight needs outlined in the recently published 'Technology Roadmap on Instrumentation, Control, and Human-Machine Interface (ICHMI) to Support DOE Advanced Nuclear Energy Programs' which was created 'to provide a systematic path forward for the integration of new ICHMI technologies in both near-term and future nuclear power plants and the reinvigoration of the U.S. nuclear ICHMI community and capabilities.' The research consortium is led by The University of Tennessee (UT) and is focused on three interrelated topics: Topic 1 (simulator development and measurement sensitivity analysis) is led by Dr. Mike Doster with Dr. Paul Turinsky of North Carolina State University (NCSU). Topic 2 (multivariate autonomous control of modular reactors) is led by Dr. Belle Upadhyaya of the University of Tennessee (UT) and Dr. Robert Edwards of Penn State University (PSU). Topic 3 (monitoring, diagnostics, and prognostics system development) is led by Dr. Wes Hines of UT. Additionally, South Carolina State University (SCSU, Dr. Ken Lewis) participated in this research through summer interns, visiting faculty, and on-campus research projects identified throughout the grant period. Lastly, Westinghouse Science and Technology Center (Dr. Mario Carelli) was a no-cost collaborator and provided design information related to the IRIS demonstration platform and defining needs that may be common to other SMR designs. The results of this research are reported in a six-volume Final Report (including the Executive Summary, Volume 1). Volumes 2 through 6 of the report describe in detail the research and development under the topical areas. This volume serves to introduce the overall NERI-C project and to summarize the key results. Section 2 provides a summary of the significant contributions of this project. A list of all the publications under this project is also given in Section 2. Section 3 provides a brief summary of each of the five volumes (2-6) of

  4. Blackhole State-Controlled Regulated Pushdown Automata

    NARCIS (Netherlands)

    E. Csuhaj-Varju; T. Masopust (Tomas); G. Vaszil (György); H. Bordihn; R. Freund; T. Hinze; M. Holzer; M. Kutrib; F. Otto

    2010-01-01

    textabstractIn this paper, we introduce and study a variant of regulated pushdown automata, called blackhole state-controlled R-PDA where a symbol can always be pushed to the pushdown, but only a given depth of the pushdown contents is remembered; the rest of the pushdown contents is lost. In

  5. The Global View on Port State Control

    NARCIS (Netherlands)

    S. Knapp (Sabine); Ph.H.B.F. Franses (Philip Hans)

    2006-01-01

    textabstractThis report is the second part of a PhD project entitled "The Econometrics of Maritime Safety – Recommendations to Enhance Safety at Sea" which is based on 183,000 port state control inspections and 11,700 casualties from various data sources. Its overall objective is to provide

  6. Ageing management of control and instrumentation systems for Indian Nuclear Power Stations

    International Nuclear Information System (INIS)

    Premchandran, T.; Ghoshal, B.; Shirolkar, K.M.; Ahmad, S.N.

    2006-01-01

    During the time of enmasse coolant channel replacement program, undertaken at Rajasthan Atomic Power Station and Madras Atomic Power Station, upgradation and ageing management activities of these units were also taken up with a view to improve the performance of the station. This paper presents the approach followed for handling the issues, pertaining to the ageing management and obsolesce of various components of Control and Instrumentation systems of these stations. Ageing related issues for field instruments, control room instruments and hardware like cables, terminal blocks and relays will be covered in this paper. It will also cover various aspects of ageing management like assessment of degradation due to ageing, policy followed for identifying the instruments that are to be replaced, selection procedure for items for assessment of residual life, testing method followed for life assessment and problems faced during replacement. From the experience gained, the issues to be addressed during design and construction stages of future plants to minimize the ageing related problems are also discussed in this paper. (author)

  7. Closing plenary summary of working group 4 instrumentation and controls for ERL2011

    Energy Technology Data Exchange (ETDEWEB)

    Gassner, D.; Obina, T.

    2011-10-16

    Working group 4 was charged with presentations and discussions on instrumentation and controls with regards to Energy Recovery Linacs (ERL). There were 4 sessions spanning 3.5 hours in which 7 talks were delivered, the first being an invited plenary presentation. The time allotted for each talk was limited to 20-25 minutes in order to allow 5-10 minutes for discussion. Most of the talks were held in joint session with working group 5 (Unwanted Beam Loss). This format was effective for the purpose of this workshop. A final series of discussion sessions were also held with working group 5. Summary of the working group 4 activities, presented in the closing plenary session. We had a plenary presentation on operational performance, experience, and future plans at the existing ERL injector prototype at Cornell. This included instrumentation data, controls system configurations, as well as description of future needs. This was followed by four talks from KEK and RIKEN/SPring-8 that described electron beam instrumentation already in use or under development that can be applied to ERL facilities. The final talks described the ERLs under construction at KEK and BNL. The format of having joint sessions with working group 5 was beneficial as there were a significant number of common topics and concerns with regards to the causes of beam loss, instrumentation hardware, and techniques used to measure and analyze beam loss.

  8. Technical and instrumental prerequisites for single-port laparoscopic solo surgery: state of art.

    Science.gov (United States)

    Kim, Say-June; Lee, Sang Chul

    2015-04-21

    With the aid of advanced surgical techniques and instruments, single-port laparoscopic surgery (SPLS) can be accomplished with just two surgical members: an operator and a camera assistant. Under these circumstances, the reasonable replacement of a human camera assistant by a mechanical camera holder has resulted in a new surgical procedure termed single-port solo surgery (SPSS). In SPSS, the fixation and coordinated movement of a camera held by mechanical devices provides fixed and stable operative images that are under the control of the operator. Therefore, SPSS primarily benefits from the provision of the operator's eye-to-hand coordination. Because SPSS is an intuitive modification of SPLS, the indications for SPSS are the same as those for SPLS. Though SPSS necessitates more actions than the surgery with a human assistant, these difficulties seem to be easily overcome by the greater provision of static operative images and the need for less lens cleaning and repositioning of the camera. When the operation is expected to be difficult and demanding, the SPSS process could be assisted by the addition of another instrument holder besides the camera holder.

  9. Development, structure and qualification of a new digital instrumentation and control system

    International Nuclear Information System (INIS)

    Hofmann, H.; Sauer, H.J.

    1991-01-01

    Introduction of digital instrumentation and control in nuclear power plants is characterized by the need to meet numerous requirements concerning reliability, ergonomic design of the main control room and comprehensive qualification. The system described here is distinguished by a hierarchical and modular structure, being redundant throughout. Ergonomic considerations dominate the layout of the screen-based main control room. Powerful computer-aided engineering tools are employed for planning of the entire system and for generation of the user software. Qualification is performed in step with the development of the system, based on the applicable national and international rules and regulations and in close cooperation with an independent expert. (orig.) [de

  10. Public policies for managing urban growth and protecting open space: policy instruments and lessons learned in the United States

    Science.gov (United States)

    David N. Bengston; Jennifer O. Fletcher

    2003-01-01

    The public sector in the United States has responded to growing concern about the social and environmental costs of sprawling development patterns by creating a wide range of policy instruments designed to manage urban growth and protect open space. These techniques have been implemented at the local, regional, state and, to a limited extent, national levels. This...

  11. Instrument-free exothermic heating with phase change temperature control for paper microfluidic devices

    Science.gov (United States)

    Singleton, Jered; Zentner, Chris; Buser, Josh; Yager, Paul; LaBarre, Paul; Weigl, Bernhard H.

    2013-03-01

    Many infectious diseases, as well as some cancers, that affect global health are most accurately diagnosed through nucleic acid amplification and detection. There is a great need to simplify nucleic acid-based assay systems for use in global health in low-resource settings as well as in settings that do not have convenient access to laboratory staff and equipment such as doctors' offices and home care settings. In developing countries, unreliable electric power, inadequate supply chains, and lack of maintenance for complex diagnostic instruments are all common infrastructure shortfalls. Many elements of instrument-free, disposable, nucleic acid amplification assays have been demonstrated in recent years. However, the problem of instrument-free,1 low-cost, temperature-controlled chemical heating remains unsolved. In this paper we present the current status and results of work towards developing disposable, low-cost, temperature-controlled heaters designed to support isothermal nucleic acid amplification assays that are integrated with a two-dimensional paper network. Our approach utilizes the heat generated through exothermic chemical reactions and controls the heat through use of engineered phase change materials to enable sustained temperatures required for nucleic acid amplification. By selecting appropriate exothermic and phase change materials, temperatures can be controlled over a wide range, suitable for various isothermal amplification methods, and maintained for over an hour at an accuracy of +/- 1°C.

  12. Instrument control software development process for the multi-star AO system ARGOS

    Science.gov (United States)

    Kulas, M.; Barl, L.; Borelli, J. L.; Gässler, W.; Rabien, S.

    2012-09-01

    The ARGOS project (Advanced Rayleigh guided Ground layer adaptive Optics System) will upgrade the Large Binocular Telescope (LBT) with an AO System consisting of six Rayleigh laser guide stars. This adaptive optics system integrates several control loops and many different components like lasers, calibration swing arms and slope computers that are dispersed throughout the telescope. The purpose of the instrument control software (ICS) is running this AO system and providing convenient client interfaces to the instruments and the control loops. The challenges for the ARGOS ICS are the development of a distributed and safety-critical software system with no defects in a short time, the creation of huge and complex software programs with a maintainable code base, the delivery of software components with the desired functionality and the support of geographically distributed project partners. To tackle these difficult tasks, the ARGOS software engineers reuse existing software like the novel middleware from LINC-NIRVANA, an instrument for the LBT, provide many tests at different functional levels like unit tests and regression tests, agree about code and architecture style and deliver software incrementally while closely collaborating with the project partners. Many ARGOS ICS components are already successfully in use in the laboratories for testing ARGOS control loops.

  13. Automatic tracking of laparoscopic instruments for autonomous control of a cameraman robot.

    Science.gov (United States)

    Khoiy, Keyvan Amini; Mirbagheri, Alireza; Farahmand, Farzam

    2016-01-01

    An automated instrument tracking procedure was designed and developed for autonomous control of a cameraman robot during laparoscopic surgery. The procedure was based on an innovative marker-free segmentation algorithm for detecting the tip of the surgical instruments in laparoscopic images. A compound measure of Saturation and Value components of HSV color space was incorporated that was enhanced further using the Hue component and some essential characteristics of the instrument segment, e.g., crossing the image boundaries. The procedure was then integrated into the controlling system of the RoboLens cameraman robot, within a triple-thread parallel processing scheme, such that the tip is always kept at the center of the image. Assessment of the performance of the system on prerecorded real surgery movies revealed an accuracy rate of 97% for high quality images and about 80% for those suffering from poor lighting and/or blood, water and smoke noises. A reasonably satisfying performance was also observed when employing the system for autonomous control of the robot in a laparoscopic surgery phantom, with a mean time delay of 200ms. It was concluded that with further developments, the proposed procedure can provide a practical solution for autonomous control of cameraman robots during laparoscopic surgery operations.

  14. Metal and trace element sediment assessment from Salto Grande reservoir, Sao Paulo state, Brazil, by instrumental neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Walace A.A., E-mail: walace@usp.br [Setor de Analises Toxicologicas. CETESB, Sao Paulo, SP (Brazil); Favaro, Deborah I.T., E-mail: defavaro@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Lab. de Analise por Ativacao com Neutrons

    2011-07-01

    The Salto Grande Reservoir is used for electric generation, irrigation, fish farming, recreation and water supply for the region's cities. The reservoir belongs to the city of Americana, located in on the eastern region of Sao Paulo State, Brazil. It belongs to the Piracicaba River Hydrographic Basin, the second most important economic and populated region and one of the most polluted areas in the State. This basin is located in a highly industrialized and agricultural region. Due to urban, industrial and agricultural activities as well as sewage wastes the water and sediments of this reservoir and surroundings are extremely contaminated, mainly by metals, according to CETESB (Environmental Control Agency of the Sao Paulo State). In order to obtain better information about its sediment contamination the present study reports results of the concentration of some major (Ca, Fe, K and Na), trace (As, Ba, Br, Co, Cr, Cs, Hf, Rb, Sb, Se, Ta, Th, U, Zn and rare earth (Ce, Eu, La, Lu, Nd, Sc, Sm, Tb and Yb)) elements in sediments and Cd, Cr, Cu, Ni and Pb concentration in sediments and water from the Salto Grande Reservoir. Multielementar analysis was carried out by Instrumental Neutron Activation Analysis (INAA). Multielemental concentrations in the sediment samples were compared to NASC (North American Shale Composite) values. The concentration values for metals As, Cd, Cr, Cu, Pb, Ni and Zn were compared to the Canadian Council of Minister of the Environment (CCME) oriented values (TEL and PEL) and adopted by CETESB, (author)

  15. Metal and trace element sediment assessment from Salto Grande reservoir, Sao Paulo state, Brazil, by instrumental neutron activation analysis

    International Nuclear Information System (INIS)

    Soares, Walace A.A.; Favaro, Deborah I.T.

    2011-01-01

    The Salto Grande Reservoir is used for electric generation, irrigation, fish farming, recreation and water supply for the region's cities. The reservoir belongs to the city of Americana, located in on the eastern region of Sao Paulo State, Brazil. It belongs to the Piracicaba River Hydrographic Basin, the second most important economic and populated region and one of the most polluted areas in the State. This basin is located in a highly industrialized and agricultural region. Due to urban, industrial and agricultural activities as well as sewage wastes the water and sediments of this reservoir and surroundings are extremely contaminated, mainly by metals, according to CETESB (Environmental Control Agency of the Sao Paulo State). In order to obtain better information about its sediment contamination the present study reports results of the concentration of some major (Ca, Fe, K and Na), trace (As, Ba, Br, Co, Cr, Cs, Hf, Rb, Sb, Se, Ta, Th, U, Zn and rare earth (Ce, Eu, La, Lu, Nd, Sc, Sm, Tb and Yb)) elements in sediments and Cd, Cr, Cu, Ni and Pb concentration in sediments and water from the Salto Grande Reservoir. Multielementar analysis was carried out by Instrumental Neutron Activation Analysis (INAA). Multielemental concentrations in the sediment samples were compared to NASC (North American Shale Composite) values. The concentration values for metals As, Cd, Cr, Cu, Pb, Ni and Zn were compared to the Canadian Council of Minister of the Environment (CCME) oriented values (TEL and PEL) and adopted by CETESB, (author)

  16. Digital control for the Penn State Breazeale reactor

    International Nuclear Information System (INIS)

    Raiskums, G.A.

    1991-01-01

    Digital control has been an integral part of Canada deuterium uranium (CANDU) nuclear power reactor technology since the 1960s. Much of the high CANDU production reliability can be attributed to the fault-tolerant and flexible control algorithms achievable with digital control. Atomic Energy of Canada Limited (AECL) has now transported this technology to research reactors, using industrial-grade microcomputers to solve equipment aging and spares obsolescence problems so prevalent at older installations. The open architecture of the Intel 8086-based computers provides for wide availability and reasonably priced, quality hardware from numerous sources. AECL recently supplied the Pennsylvania State University Breazeale Reactor (PSBR) with a new console containing a digital control and monitoring system. The reactor safety system (RSS) was also replaced with hardwired relay logic and truly analog state-of-the-art wide range nuclear instrumentation supplied by AECL's subcontractor, Gamma-Metrics. Retaining analog hardware for the mandated RSS functions was key to minimizing licensing efforts and the extensive verification and validation that would be required for safety system software. This paper elaborates on the digital control and monitoring portion of the PSBR console replacement, with emphasis on the key system objectives

  17. Impact of state-of-the-art instrumentation on safety-related experimental studies proposed in containment studies facility (CSF)

    International Nuclear Information System (INIS)

    Gole, N.V.; Markandeya, S.G.; Subramaniam, K.; Ghosh, A.K.

    2002-01-01

    Full text: Conducting an experimental program for safety related studies for nuclear power plants (NPPs) is an extremely laborious and time-consuming task due to several reasons. Requirement for frequent replacements, testing and recalibration of a large number of instruments is one of them. Off-line analysis leading to identification of errors is another. A particular test may have to be abandoned based on such analysis. Following the rapid advances in instrumentation, a larger number of options are now available, which make experimentation easy. CSF is one of the upcoming facilities wherein deployment of state-of-the art became inevitable. This paper discusses in detail the design intent of instrumentation, the state-of-the-art instrumentation provisions made to fulfill it the overall impact of this on successful experimentation

  18. MDEP Common Position No EPR-01 - Common positions on the EPR instrumentation and controls design

    International Nuclear Information System (INIS)

    2010-01-01

    The purpose of the EPR Working Group (EPRWG) of the Multinational Design Evaluation Program (MDEP) is to identify common positions among the regulators reviewing the EPR Instrumentation and Controls (I and C) Systems in order to: 1. Promote understanding of each country 's regulatory decisions and basis for the decisions, 2. Enhance communication among the members and with external stakeholders, 3. Identify areas where harmonization and convergence of regulations, standards, and guidance can be achieved or improved, and 4. Supports standardization of new reactor designs. Since January 2008, the EPR I and C Technical Expert Subgroup (TESG) members met five times to exchange information regarding their country 's review of the EPR I and C design. The EPR I and C TESG consists of regulators from China, Canada, Finland, France, the United Kingdom, and the United States. The information exchange includes presentation of each country 's review status and technical issues, sharing of guidance documents, and sharing of regulatory decision documents. The TESG focused on the following four core areas of the EPR I and C design: 1. I and C System Independence (particularly for data communications), 2. Level of Defense and Diversity (back-up systems), 3. Qualification/quality of digital platforms, 4. Categorization/classification of systems and functions. As meetings were conducted, some areas were emphasized more depending on the significance of the issues for each country. During the TESG interactions, it became apparent that there were aspects of the EPR design where the countries had common agreement. On November 2, 2009, three of the subgroup countries, France, Finland and the United Kingdom, issued a joint regulatory position on the EPR I and C design as result of the 'Groupe Permanent' meeting in France. This statement of common positions expands upon that joint regulatory position

  19. Instrumentation and control of the Doublet III Neutral Beam Injector System

    Energy Technology Data Exchange (ETDEWEB)

    Kohli, J.C.; Moore, C.D.; Drobnis, D.D.; Elischer, V.P.; Kilgore, R.; Uber, D.

    1980-03-01

    The hardware and software required for the operation of the Doublet III Neutral Beam Injector System (NBIS) are described. Development and implementation of this Instrumentation and Control System was divided between the major participants - General Atomic Company and Lawrence Berkeley Laboratory. The subdivision of responsibilities and the coordination of the participants' activities are described with reference to hardware and software requirements in support of the entire system. Included are a description of the operators' consoles, the interlock system and the CAMAC system. One feature of the control software is source modeling. This feature includes feedback on a shot to shot basis and adaptive control. Adaptive control permits the computer system to automatically adjust parameters after a shot, and to control the system to automatically compensate for time varying NBIS components. The Neutral Beam Power Supply features power supply modeling, fiber optic transmission of analog signals and digital control of power supply power-up/interlocks.

  20. JACoW Safety instrumented systems and the AWAKE plasma control as a use case

    CERN Document Server

    Blanco Viñuela, Enrique; Fernández Adiego, Borja; Speroni, Roberto

    2018-01-01

    Safety is likely the most critical concern in many process industries, yet there is a general uncertainty on the proper engineering to reduce the risks and ensure the safety of persons or material at the same time as providing the process control system. Some of the reasons for this misperception are unclear requirements, lack of functional safety engineering knowledge or incorrect protection functionalities attributed to the BPCS (Basic Process Control System). Occasionally the control engineers are not aware of the hazards inherent to an industrial process and this causes an incorrect design of the overall controls. This paper illustrates the engineering of the SIS (Safety Instrumented System) and the BPCS of the plasma vapour controls of the AWAKE R&D; project, the first proton-driven plasma wakefield acceleration experiment in the world. The controls design and implementation refers to the IEC61511/ISA84 standard, including technological choices, design, operation and maintenance. Finally, the publica...

  1. Instrumentation and control of the Doublet III Neutral Beam Injector System

    International Nuclear Information System (INIS)

    Kohli, J.C.; Moore, C.D.; Drobnis, D.D.; Elischer, V.P.; Kilgore, R.; Uber, D.

    1980-03-01

    The hardware and software required for the operation of the Doublet III Neutral Beam Injector System (NBIS) are described. Development and implementation of this Instrumentation and Control System was divided between the major participants - General Atomic Company and Lawrence Berkeley Laboratory. The subdivision of responsibilities and the coordination of the participants' activities are described with reference to hardware and software requirements in support of the entire system. Included are a description of the operators' consoles, the interlock system and the CAMAC system. One feature of the control software is source modeling. This feature includes feedback on a shot to shot basis and adaptive control. Adaptive control permits the computer system to automatically adjust parameters after a shot, and to control the system to automatically compensate for time varying NBIS components. The Neutral Beam Power Supply features power supply modeling, fiber optic transmission of analog signals and digital control of power supply power-up/interlocks

  2. 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.)

  3. Advanced Instrumentation, Information, and Control Systems Technologies Research in Support of Light Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hallbert, Bruce P.; Kenneth, Thomas [Idaho National Laboratory, Idaho (United States)

    2014-08-15

    The Advanced Instrumentation, Information, and Control (II and C) Systems Technologies Pathway conducts targeted research and development (R and D) to address aging and reliability concerns with the legacy instrumentation and control and related information systems of the U.S. operating light water reactor (LWR) fleet. This work involves two major goals to ensure that legacy analog II and C systems are not life-limiting issues for the LWR fleet, and to implement digital II and C technology in a manner that enables broad innovation and business improvement in the nuclear power plant operating model. Resolving long-term operational concerns with the II and C systems contributes to the long-term sustainability of the LWR fleet, which is vital to the nation's energy and environmental security.

  4. Advanced Instrumentation, Information, and Control Systems Technologies Research in Support of Light Water Reactors

    International Nuclear Information System (INIS)

    Hallbert, Bruce P.; Kenneth, Thomas

    2014-01-01

    The Advanced Instrumentation, Information, and Control (II and C) Systems Technologies Pathway conducts targeted research and development (R and D) to address aging and reliability concerns with the legacy instrumentation and control and related information systems of the U.S. operating light water reactor (LWR) fleet. This work involves two major goals to ensure that legacy analog II and C systems are not life-limiting issues for the LWR fleet, and to implement digital II and C technology in a manner that enables broad innovation and business improvement in the nuclear power plant operating model. Resolving long-term operational concerns with the II and C systems contributes to the long-term sustainability of the LWR fleet, which is vital to the nation's energy and environmental security

  5. Assessment of new instrumentation and control technologies. Remote multiplexing. A case study

    International Nuclear Information System (INIS)

    Long, A.B.

    1978-01-01

    New instrumentation and control technologies must be justified for application in power plants on the basis of improved plant performance and reduced investment costs. This justification requires that capability differences among systems be identified and that implementation schemes be selected which permit meaningful comparisons. A simple evaluation of initial investment costs is frequently inadequate because it does not account for operational expenses or resulting changes in plant performance. As an example of a more comprehensive evaluation methodology, this paper reviews the procedures and results from a recently completed study of remote multiplexing funded by the Electric Power Research Institute (EPRI). In this study it was found that plant-wide multiplexing of non-safety instrumentation and control signals is technically feasible, can be designed to satisfy availability requirements, may save millions of dollars as a hardwire replacer, and can provide other significant intangible benefits. (author)

  6. Grafting Acoustic Instruments and Signal Processing: Creative Control and Augmented Expressivity

    DEFF Research Database (Denmark)

    Overholt, Daniel; Freed, Adrian

    In this study, work is presented on a hybrid acoustic / electric violin. The instrument has embedded processing that provides real-time simulation of acoustic body models using DSP techniques able to gradually transform a given body model into another, including extrapolations beyond the models...... acoustic violins with high fidelity. The opportunity to control a virtually malleable body while playing, i.e., a model that changes reverberant resonances in response to player input, results in interesting audio effects. Other common audio effects can also be employed and simultaneously controlled via...... the musician’s movements. For example, gestural tilting of the instrument is tracked via an embedded Inertial Measurement Unit (IMU), which can be assigned to alter parameters such as the wet/dry mix of a simple octave-doubler or other more advanced audio effect, further augmenting the expressivity...

  7. 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

  8. Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan for 2014

    Energy Technology Data Exchange (ETDEWEB)

    Hallbert, Bruce [Idaho National Lab. (INL), Idaho Falls, ID (United States); Thomas, Ken [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-07-01

    The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies Pathway conducts targeted research and development (R&D) to address aging and reliability concerns with the legacy instrumentation and control and related information systems of the U.S. operating light water reactor (LWR) fleet. This work involves two major goals: (1) to ensure that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) to implement digital II&C technology in a manner that enables broad innovation and business improvement in the nuclear power plant operating model. Resolving long-term operational concerns with the II&C systems contributes to the long-term sustainability of the LWR fleet, which is vital to the nation's energy and environmental security.

  9. Microprocessor- and LSI-based CAMAC RAM controllers in a modular multiparameter instrumentation system

    International Nuclear Information System (INIS)

    Skarda, V.

    1982-01-01

    This contribution deals with the main features and with the hardware modifications of RAM controllers in the dual-port accessed CAMAC memory modules that have been applied in a modular multichannel analyzer instrumentation system. The modules described in this paper are fully compatible with the CAMAC standard EUR 4100 and with the COMPEX draft proposal of the ESONE Study Group, as well. Special attention is paid to the possible application of modern LSI bipolar circuits. (orig.)

  10. The upgraded control and instrumentation system of C5 irradiation device

    International Nuclear Information System (INIS)

    Iordache, A.; Ancuta, M.; Gruia, L.; Pulpa, A.; Salistean, E.; Gusescu, G.

    2013-01-01

    C5 capsule is an irradiation device of TRIGA SSR, which is designed for irradiation of structural materials in an inert environment for mechanical behavior characterization and the material microstructure evolution during irradiation. The paper presents the upgraded control and instrumentation system of the C5 irradiation device which was designed and manufactured to enhance the performance of this system for better surveillance and processing the acquired experimental data. (authors)

  11. Principles relating to the digital instrumentation and control design approach 2017

    International Nuclear Information System (INIS)

    2017-01-01

    The design of the instrumentation and control of nuclear facilities uses digital systems that offer increasing computation and interconnection capabilities. They enable advanced functions to be carried out, such as calculation of the critical heat flux ratio, help to detect hardware failures in real time and provide operators with rich, flexible interfaces. However, these evolved functions may be affected by faults that make their logic systematically inadequate in certain cases, which introduces sources of failure other than random hardware failures and raises questions about the informal concept of the increased 'complexity' of instrumentation and control. Appropriate design principles shall therefore be applied so that this logic is as fault-free as possible and can be assessed by an independent body such as IRSN. This document presents the main problems associated with the design of the digital instrumentation and control of a complex facility, as well as the general principles to follow to demonstrate that a satisfactory safety level has been achieved. The doctrine elements presented in this document are the result of the experience acquired during assessments carried out for the French nuclear power plants, enhanced by exchanges with experts from the nuclear sector, and reflect French practice; they apply in other sectors in which a high level of confidence can be attributed to instrumentation and control. The normative texts cited in this document provide detailed requirements that are open to considerable interpretation, as the nature of the problem posed does not enable relevant and measurable criteria to be defined in all cases. This document aims to explain the principles underlying these detailed requirements and to give the means for interpreting them in each situation. (authors)

  12. Research on conceptual design of simplified nuclear safety instrument and control system

    International Nuclear Information System (INIS)

    Huang Jie

    2015-01-01

    The Nuclear safety instrument and control system is directly related to the safety of the reactor. So redundant and diversity design is used to ensure the system's security and reliability. This make the traditional safety system large, more cabinets and wiring complexity. To solve these problem, we can adopt new technology to make the design more simple. The simplify conceptual design can make the system less cabinets, less wiring, but high security, strong reliability. (author)

  13. Instrumentation and control system for PLS-IM-T 60 MeV LINAC

    International Nuclear Information System (INIS)

    Liu, D.K.; Yei, K.R.; Cheng, H.J.

    1992-01-01

    The PLSIMT is a 60 MeV LINAC as a preinjector for 2 GeV LINAC of PLS project. The instrumentation and control system have been designed under the institutional collaboration between the IHEP (Beijing, China) and POSTECH (Pohang, Korea). So far, the I and C system are being set up nowadays at the POSTECH of Pohang. This paper describes its major characteristics and present status. (author)

  14. The market for process control instrumentation in France. Foreign market survey report

    International Nuclear Information System (INIS)

    1977-04-01

    The market research was undertaken to study the present and potential US share of the market in France for process control instrumentation; to examine growth trends in French end-user industries over the next few years; to identify specific product categories that offer the most promising export potential for US companies; and to provide basic data which will assist US suppliers in determining current and potential sales and marketing opportunities. The trade promotional and marketing techniques were also reviewed

  15. 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

  16. The control-and-instrumentation system of the IEA zero power reactor and its reliability calculation

    International Nuclear Information System (INIS)

    Peluso, M.A.V.

    1978-01-01

    The control-and instrumentation system for the Instituto de Energia Atomica Zero Power Reactor is described and the design criteria are presented and discussed. The reliability analysis for the reactor protection system was performed using the fault tree method. This was done using a computer code based on the Monte Carlo simulation. That code is an adaptation of the SAFTE-I, for the IBM 360/155 IEA Computer. (Author) [pt

  17. Job/task analysis for I ampersand C [Instrumentation and Controls] instrument technicians at the High Flux Isotope Reactor

    International Nuclear Information System (INIS)

    Duke, L.L.

    1989-09-01

    To comply with Department of Energy Order 5480.XX (Draft), a job/task analysis was initiated by the Maintenance Management Department at Oak Ridge National Laboratory (ORNL). The analysis was applicable to instrument technicians working at the ORNL High Flux Isotope Reactor (HFIR). This document presents the procedures and results of that analysis. 2 refs., 2 figs

  18. Virtual instrument for controlling and monitoring digitalized power supply in SSRF

    International Nuclear Information System (INIS)

    Tang Junlong; Chen Huanguang; Chinese Academy of Sciences, Beijing; Xu Ruinian; Shen Tianjian; Li Deming

    2006-01-01

    The Shanghai Synchrotron Radiation Facility (SSRF) needs extremely precise power supplies for their various magnets. A digital controller is being developed for the power converters of the SSRF power supply (PS). In the digital controller, a fully digital pulse-width modulator (PWM) directly controls the power unit insulated gate bipolar transistor (IGBT) of the PS. A program in LabVIEW language has been developed to control and monitor the digital PS via serial communication (RS232) from a PC and to modify its parameters as well. In this article, the software design of the virtual instrument for controlling and monitoring digitalized PS and its associated functions are described, and the essential elements of the program graphical main-VI and sub-VI source code are presented and explained. The communication protocol and the structure of the developed system are also included in this article. (authors)

  19. 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)

  20. Economic policy instruments for the control of air pollution in Poland

    International Nuclear Information System (INIS)

    Bates, R.W.

    1993-01-01

    The World Bank is analyzing the role of economic policy instruments for the control of air pollution in Poland, in cooperation with Polish and international experts. The first stage, covering Poland as a whole, was recently completed, jointly financed with the U.S. E.P.A. and the Government of the Netherlands. The second stage, now under way, will extend the analysis into a specific regional framework. Stage 2 is financed by the World Bank, the Polish Government, and the U.K. Environment Know-How Fund. Air Pollution in Poland is overwhelmingly caused by energy production and uses, due to the fact that the Polish economy depends heavily on coal and lignite. At present, vehicles contribute less to total emissions than do coal burning and industrial processes, although they account for 25-35% of nitrogen oxides, carbon monoxide, hydrocarbons and lead; and the concentrated in areas of high population density. The paper shows how economic, technical and meteorological modelling can be used, to reach conclusions about cost-effective strategies for the control of emissions and the improvement of ambient air quality. A simulation approach is presented, to compare alternative policy instruments, in terms of their impact on emissions and control costs for Poland as a whole. The main instruments considered are open-quotes command-and-controlclose quotes regimes (C ampersand C) and economic incentives, namely fuel taxes, emissions taxes and emissions trading. Next, the paper describes how the analysis is being extended, to link emissions with ambient air quality, using air dispersion modelling, based on a case study for Krakow. Finally, some conclusions are drawn on the importance of sound economic policies for air quality management, the costs of alternative standards, C ampersand C approaches versus economic incentives, a practical strategy to develop an effective role for emissions taxes and trading, and the regional differentiation of policy instruments

  1. Operational test procedure for pumping and instrumentation control skid SALW-6001B monitor and control system

    International Nuclear Information System (INIS)

    Garcia, M.F.

    1995-11-01

    This OTP shall verify and document that the monitor and control system comprised of PICS SALW-6001B PLC, 242S PLC, Operator Control Station, and communication network is functioning per operational requirements

  2. Power supply for control and instrumentation in Fast Breeder Test Reactor

    International Nuclear Information System (INIS)

    Raghavan, K.; Shanmugam, T.K.

    1977-01-01

    The design and operation of the four 'no-break' power supplies for control and instrumentation in the Fast Breeder Test Reactor (FBTR), Kalpakkam, are described. Interruptions in the power supplies are eliminated by redundancy and battery back-up source while voltage dips and transients are taken care by automatic regulation system. The four power supplies are : (1) 24 V D.C. exclusively for neutronic and safety circuits, (2) 48 V D.C. for control logic indication lamps and solenoid valves, (3) 220 V D.C. for switchgear control, control room emergency lighting and D.C. flushing oil pump for the turbine and (4) 220 V A.C. single-phase 50 H/Z for computers and electronics of control and instrumentation. Stationary lead-acid batteries (lead antimony type) in floating mode operation with rectifier/charger are used for emergency back-up. All these power supplies are fed by 415 V, 3-phase, 50 HZ emergency supply buses which are provided with diesel generator back-up. Static energy conversion system (in preference to mechanical rotation system) is used for A.C. to D.C. and also for A.C. to A.C. conversion. (M.G.B.)

  3. The development of advanced instrumentation and control technology. The development of verification and validation technology for instrumentation and control in NPPs

    International Nuclear Information System (INIS)

    Kwon, Kee Choon; Ham, Chang Shik; Lee, Jang Soo; Kim, Jang Yeol; Song, Soon Ja; Kim, Jung Taek; Park, Won Man; Lee, Dong Young; Eom, Heung Seop; Park, Kee Yong.

    1997-07-01

    We found essential problems followed by digitalizing of instrumentation and control. A scheme is divided into hardware and software to resolve these problems. We have analyzed the hardware V and V methodologies about common mode failure, commercial grade dedication process and electromagnetic compatibility. We have developed several guidelines, the software classification guideline, the quality assurance handbook for the software in digital I and C, the software V and V planning guideline, and the software safety guideline. And then, we have established the integrated environment for the safety-critical software based on the Computer Aided Software Engineering (CASE) tools. We have also surveyed a trend and application case of test facility for establishment of functional requirements. Input/output interface which connects among the host computer and developed target and panel are designed and manufactured using UXI bus. The developed functional test facility is used for test and validate the automatic start-up intelligent control system, the dynamic alarm system, the accident identification system using hidden Markov model, and the intelligent logic tracking system. The result of evaluation of the above systems shows the functional test facility performance is sufficient in normal operating and transient conditions. (author). 24 tabs., 59 figs

  4. The development of advanced instrumentation and control technology. The development of verification and validation technology for instrumentation and control in NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Ham, Chang Shik; Lee, Jang Soo; Kim, Jang Yeol; Song, Soon Ja; Kim, Jung Taek; Park, Won Man; Lee, Dong Young; Eom, Heung Seop; Park, Kee Yong

    1997-07-01

    We found essential problems followed by digitalizing of instrumentation and control. A scheme is divided into hardware and software to resolve these problems. We have analyzed the hardware V and V methodologies about common mode failure, commercial grade dedication process and electromagnetic compatibility. We have developed several guidelines, the software classification guideline, the quality assurance handbook for the software in digital I and C, the software V and V planning guideline, and the software safety guideline. And then, we have established the integrated environment for the safety-critical software based on the Computer Aided Software Engineering (CASE) tools. We have also surveyed a trend and application case of test facility for establishment of functional requirements. Input/output interface which connects among the host computer and developed target and panel are designed and manufactured using UXI bus. The developed functional test facility is used for test and validate the automatic start-up intelligent control system, the dynamic alarm system, the accident identification system using hidden Markov model, and the intelligent logic tracking system. The result of evaluation of the above systems shows the functional test facility performance is sufficient in normal operating and transient conditions. (author). 24 tabs., 59 figs.

  5. Instrumented Compliant Wrist with Proximity and Contact Sensing for Close Robot Interaction Control

    Directory of Open Access Journals (Sweden)

    Pascal Laferrière

    2017-06-01

    Full Text Available Compliance has been exploited in various forms in robotic systems to allow rigid mechanisms to come into contact with fragile objects, or with complex shapes that cannot be accurately modeled. Force feedback control has been the classical approach for providing compliance in robotic systems. However, by integrating other forms of instrumentation with compliance into a single device, it is possible to extend close monitoring of nearby objects before and after contact occurs. As a result, safer and smoother robot control can be achieved both while approaching and while touching surfaces. This paper presents the design and extensive experimental evaluation of a versatile, lightweight, and low-cost instrumented compliant wrist mechanism which can be mounted on any rigid robotic manipulator in order to introduce a layer of compliance while providing the controller with extra sensing signals during close interaction with an object’s surface. Arrays of embedded range sensors provide real-time measurements on the position and orientation of surfaces, either located in proximity or in contact with the robot’s end-effector, which permits close guidance of its operation. Calibration procedures are formulated to overcome inter-sensor variability and achieve the highest available resolution. A versatile solution is created by embedding all signal processing, while wireless transmission connects the device to any industrial robot’s controller to support path control. Experimental work demonstrates the device’s physical compliance as well as the stability and accuracy of the device outputs. Primary applications of the proposed instrumented compliant wrist include smooth surface following in manufacturing, inspection, and safe human-robot interaction.

  6. The EyeHarp: A Gaze-Controlled Digital Musical Instrument.

    Science.gov (United States)

    Vamvakousis, Zacharias; Ramirez, Rafael

    2016-01-01

    We present and evaluate the EyeHarp, a new gaze-controlled Digital Musical Instrument, which aims to enable people with severe motor disabilities to learn, perform, and compose music using only their gaze as control mechanism. It consists of (1) a step-sequencer layer, which serves for constructing chords/arpeggios, and (2) a melody layer, for playing melodies and changing the chords/arpeggios. We have conducted a pilot evaluation of the EyeHarp involving 39 participants with no disabilities from both a performer and an audience perspective. In the first case, eight people with normal vision and no motor disability participated in a music-playing session in which both quantitative and qualitative data were collected. In the second case 31 people qualitatively evaluated the EyeHarp in a concert setting consisting of two parts: a solo performance part, and an ensemble (EyeHarp, two guitars, and flute) performance part. The obtained results indicate that, similarly to traditional music instruments, the proposed digital musical instrument has a steep learning curve, and allows to produce expressive performances both from the performer and audience perspective.

  7. INSTRUMENTATION AND AUTOMATIC CONTROL, SUGGESTED TECHNIQUES FOR DETERMINING COURSES OF STUDY IN VOCATIONAL AND TECHNICAL EDUCATION PROGRAMS.

    Science.gov (United States)

    WEINSTEIN, EMANUEL

    THE PURPOSE OF THIS GUIDE IS TO HELP THE STATES ORGANIZE AND OPERATE EDUCATIONAL PROGRAMS FOR OCCUPATIONS IN THE FIELD OF INSTRUMENTATION. CHAPTER TITLES ARE--(1) INSTRUMENTATIONS--PAST, PRESENT, AND FUTURE, (2) THE OCCUPATIONAL FIELD, (3) WORK ACTIVITIES (DESIGN, FABRICATION, MAINTENANCE, REPAIR, AND SERVICE), (4) TRAINING REQUIREMENTS, AND (5)…

  8. Status of the Instrument Control Unit for EPD on-board Solar Orbiter

    Science.gov (United States)

    Sánchez Prieto, Sebastián; Da Silva, Antonio; Rodriguez Polo, Oscar; Parra Espada, Pablo; Gutierrez Molina, Oscar; Fernandez Salgado, Javier

    Solar Orbiter is the next heliospheric mission sponsored by ESA. The launch is planned for 2017 and it will be as close as 0.28 AU from the Sun. One of the instruments for Solar Orbiter is the Energetic Particle Detector (EPD) responsible for measuring energies from 2 keV to 200 MeV/n. EPD consists of four detectors, Electron Proton Telescope (EPT), High Energy Telescope (HET), SupraThermal Electrons, Ions, & Neutrals (STEIN), and Suprathermal Ion Spectrograph (SIS), plus the Instrument Control Unit called ICU. The Space Research Group of the University of Alcalá in Spain is the responsible for developing the ICU. In this work we present the development status of the ICU after the Critical Design Review. We also address the planned activities for the next year including the development of the Engineering and Qualification Model (EQM) and Flight Model (PM). Special focus is paid to the software and verification & validation activities.

  9. Regulatory accessibility and social influences on state self-control.

    Science.gov (United States)

    vanDellen, Michelle R; Hoyle, Rick H

    2010-02-01

    The current work examined how social factors influence self-control. Current conceptions of state self-control treat it largely as a function of regulatory capacity. The authors propose that state self-control might also be influenced by social factors because of regulatory accessibility. Studies 1 through 4 provide evidence that individuals' state self-control is influenced by the trait and state self-control of salient others such that thinking of others with good trait or state self-control leads to increases in state self-control and thinking of others with bad trait or state self-control leads to decreases in state self-control. Study 5 provides evidence that the salience of significant others influences both regulatory accessibility and state self-control. Combined, these studies suggest that the effects of social influences on state self-control occur through multiple mechanisms.

  10. Core-adjacent instrumentation systems for pebble bed reactors for process heat application - state of planning

    International Nuclear Information System (INIS)

    Benninghofen, G.; Serafin, N.; Spillekothen, H.G.; Hecker, R.; Brixy, H.; Serpekian, T.

    1982-06-01

    Planning and theoretical/experimental development work for core surveillance instrumentation systems is being performed to meet requirements of pebble bed reactors for process heat application. Detailed and proved instrumentation concepts are now available for the core-adjacent instrumentation systems. The current work and the results of neutron flux measurements at high temperatures are described. Operation devices for long-term accurate gas outlet temperature measurements up to approximately 1423 deg. K will also be discussed. (author)

  11. PLC and DTAM Software Programs for Pumping Instrumentation and Control Skid N

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This document describe the software programs for the Programmable Logic Controller and the Datable Access Module for Pumping Instrumentation and Control skid ''N''. The Appendices contains copies of the printouts of these software programs. This document describes the software programs for the Allen-Bradley SLC 500 programmable logic controller (PLC) and the Allen-Bradley DTAM PLUS operator interface module used on Pumping Instrumentation and Control (PIC) skid ''N''. The software programs for the SLC 500 and DTAM Plus are based on the core programs provided by Allen-Bradley. The PLC and DTAM software programs on skid ''D'' for SX-104 are the baseline programs. These baselines have been tailored for U-farm skids. The skid ''N'' program for U-109 is similar to the skid ''M'' program for U-102. An Acceptance Test Procedure (ATP) and an Operational Test Procedure (OTP) verify that the software programs meet the specific requirements for U-109 pumping. This document represents the final PLC and DTAM programs for PIC skid ''N'' at U-109. These programs were printed out after the performance of the OTP. The OTP acts as the final qualification test for the software programs. Functional requirements and details of the PLC ladder logic are described in this document. The final programs entered into the PLC and DTAM Plus are included as Appendices to this document

  12. Development of intelligent control system for X-ray streak camera in diagnostic instrument manipulator

    Energy Technology Data Exchange (ETDEWEB)

    Pei, Chengquan [Key Laboratory for Physical Electronics and Devices of the Ministry of Education, Xi' an Jiaotong University, Xi' an 710049 (China); Wu, Shengli, E-mail: slwu@mail.xjtu.edu.cn [Key Laboratory for Physical Electronics and Devices of the Ministry of Education, Xi' an Jiaotong University, Xi' an 710049 (China); Tian, Jinshou [Xi' an Institute of Optics and Precision Mechanics, Chinese Academy of Sciences, Xi' an 710119 (China); Liu, Zhen [Key Laboratory for Physical Electronics and Devices of the Ministry of Education, Xi' an Jiaotong University, Xi' an 710049 (China); Fang, Yuman [Key Laboratory for Physical Electronics and Devices of the Ministry of Education, Xi' an Jiaotong University, Xi' an 710049 (China); University of the Chinese Academy of Sciences, Beijing 100039 (China); Gao, Guilong; Liang, Lingliang [Key Laboratory for Physical Electronics and Devices of the Ministry of Education, Xi' an Jiaotong University, Xi' an 710049 (China); Xi' an Institute of Optics and Precision Mechanics, Chinese Academy of Sciences, Xi' an 710119 (China); University of the Chinese Academy of Sciences, Beijing 100039 (China); Wen, Wenlong [Key Laboratory for Physical Electronics and Devices of the Ministry of Education, Xi' an Jiaotong University, Xi' an 710049 (China)

    2015-11-01

    An intelligent control system for an X ray streak camera in a diagnostic instrument manipulator (DIM) is proposed and implemented, which can control time delay, electric focusing, image gain adjustment, switch of sweep voltage, acquiring environment parameters etc. The system consists of 16 A/D converters and 16 D/A converters, a 32-channel general purpose input/output (GPIO) and two sensors. An isolated DC/DC converter with multi-outputs and a single mode fiber were adopted to reduce the interference generated by the common ground among the A/D, D/A and I/O. The software was designed using graphical programming language and can remotely access the corresponding instrument from a website. The entire intelligent control system can acquire the desirable data at a speed of 30 Mb/s and store it for later analysis. The intelligent system was implemented on a streak camera in a DIM and it shows a temporal resolution of 11.25 ps, spatial distortion of less than 10% and dynamic range of 279:1. The intelligent control system has been successfully used in a streak camera to verify the synchronization of multi-channel laser on the Inertial Confinement Fusion Facility.

  13. Development of intelligent control system for X-ray streak camera in diagnostic instrument manipulator

    International Nuclear Information System (INIS)

    Pei, Chengquan; Wu, Shengli; Tian, Jinshou; Liu, Zhen; Fang, Yuman; Gao, Guilong; Liang, Lingliang; Wen, Wenlong

    2015-01-01

    An intelligent control system for an X ray streak camera in a diagnostic instrument manipulator (DIM) is proposed and implemented, which can control time delay, electric focusing, image gain adjustment, switch of sweep voltage, acquiring environment parameters etc. The system consists of 16 A/D converters and 16 D/A converters, a 32-channel general purpose input/output (GPIO) and two sensors. An isolated DC/DC converter with multi-outputs and a single mode fiber were adopted to reduce the interference generated by the common ground among the A/D, D/A and I/O. The software was designed using graphical programming language and can remotely access the corresponding instrument from a website. The entire intelligent control system can acquire the desirable data at a speed of 30 Mb/s and store it for later analysis. The intelligent system was implemented on a streak camera in a DIM and it shows a temporal resolution of 11.25 ps, spatial distortion of less than 10% and dynamic range of 279:1. The intelligent control system has been successfully used in a streak camera to verify the synchronization of multi-channel laser on the Inertial Confinement Fusion Facility

  14. Micro-controller based air pressure monitoring instrumentation system using optical fibers as sensor

    Science.gov (United States)

    Hazarika, D.; Pegu, D. S.

    2013-03-01

    This paper describes a micro-controller based instrumentation system to monitor air pressure using optical fiber sensors. The principle of macrobending is used to develop the sensor system. The instrumentation system consists of a laser source, a beam splitter, two multi mode optical fibers, two Light Dependent Resistance (LDR) based timer circuits and a AT89S8252 micro-controller. The beam splitter is used to divide the laser beam into two parts and then these two beams are launched into two multi mode fibers. One of the multi mode fibers is used as the sensor fiber and the other one is used as the reference fiber. The use of the reference fiber is to eliminate the environmental effects while measuring the air pressure magnitude. The laser beams from the sensor and reference fibers are applied to two identical LDR based timer circuits. The LDR based timer circuits are interfaced to a micro-controller through its counter pins. The micro-controller samples the frequencies of the timer circuits using its counter-0 and counter-1 and the counter values are then processed to provide the measure of air pressure magnitude.

  15. Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

    International Nuclear Information System (INIS)

    Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

    2005-04-01

    This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility

  16. Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

    2005-04-15

    This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility.

  17. Real-time operation without a real-time operating system for instrument control and data acquisition

    Science.gov (United States)

    Klein, Randolf; Poglitsch, Albrecht; Fumi, Fabio; Geis, Norbert; Hamidouche, Murad; Hoenle, Rainer; Looney, Leslie; Raab, Walfried; Viehhauser, Werner

    2004-09-01

    We are building the Field-Imaging Far-Infrared Line Spectrometer (FIFI LS) for the US-German airborne observatory SOFIA. The detector read-out system is driven by a clock signal at a certain frequency. This signal has to be provided and all other sub-systems have to work synchronously to this clock. The data generated by the instrument has to be received by a computer in a timely manner. Usually these requirements are met with a real-time operating system (RTOS). In this presentation we want to show how we meet these demands differently avoiding the stiffness of an RTOS. Digital I/O-cards with a large buffer separate the asynchronous working computers and the synchronous working instrument. The advantage is that the data processing computers do not need to process the data in real-time. It is sufficient that the computer can process the incoming data stream on average. But since the data is read-in synchronously, problems of relating commands and responses (data) have to be solved: The data is arriving at a fixed rate. The receiving I/O-card buffers the data in its buffer until the computer can access it. To relate the data to commands sent previously, the data is tagged by counters in the read-out electronics. These counters count the system's heartbeat and signals derived from that. The heartbeat and control signals synchronous with the heartbeat are sent by an I/O-card working as pattern generator. Its buffer gets continously programmed with a pattern which is clocked out on the control lines. A counter in the I/O-card keeps track of the amount of pattern words clocked out. By reading this counter, the computer knows the state of the instrument or knows the meaning of the data that will arrive with a certain time-tag.

  18. Translation and cultural adaptation of a specific instrument for measuring asthma control and asthma status: the Asthma Control and Communication Instrument

    Directory of Open Access Journals (Sweden)

    Michelle Gonçalves de Souza Tavares

    Full Text Available ABSTRACT Objective: To translate the Asthma Control and Communication Instrument (ACCI to Portuguese and adapt it for use in Brazil. Methods: The ACCI was translated to Portuguese and adapted for use in Brazil in accordance with internationally accepted guidelines. The protocol included the following steps: permission and rights of use granted by the original author; translation of the ACCI from English to Portuguese; reconciliation; back-translation; review and harmonization of the back-translation; approval from the original author; review of the Portuguese version of the ACCI by an expert panel; cognitive debriefing (the clarity, understandability, and acceptability of the translated version being tested in a sample of the target population; and reconciliation and preparation of the final version. Results: During the cognitive debriefing process, 41 asthma patients meeting the inclusion criteria completed the ACCI and evaluated the clarity of the questions/statements. The clarity index for all ACCI items was > 0.9, meaning that all items were considered to be clear. Conclusions: The ACCI was successfully translated to Portuguese and culturally adapted for use in Brazil, the translated version maintaining the psychometric properties of the original version. The ACCI can be used in clinical practice because it is easy to understand and easily applied.

  19. Translation and cultural adaptation of a specific instrument for measuring asthma control and asthma status: the Asthma Control and Communication Instrument

    Science.gov (United States)

    Tavares, Michelle Gonçalves de Souza; Brümmer, Carolina Finardi; Nicolau, Gabriela Valente; de Melo, José Tavares; Nazário, Nazaré Otilia; Steidle, Leila John Marques; Patino, Cecília Maria; Pizzichini, Marcia Margaret Menezes; Pizzichini, Emílio

    2017-01-01

    ABSTRACT Objective: To translate the Asthma Control and Communication Instrument (ACCI) to Portuguese and adapt it for use in Brazil. Methods: The ACCI was translated to Portuguese and adapted for use in Brazil in accordance with internationally accepted guidelines. The protocol included the following steps: permission and rights of use granted by the original author; translation of the ACCI from English to Portuguese; reconciliation; back-translation; review and harmonization of the back-translation; approval from the original author; review of the Portuguese version of the ACCI by an expert panel; cognitive debriefing (the clarity, understandability, and acceptability of the translated version being tested in a sample of the target population); and reconciliation and preparation of the final version. Results: During the cognitive debriefing process, 41 asthma patients meeting the inclusion criteria completed the ACCI and evaluated the clarity of the questions/statements. The clarity index for all ACCI items was > 0.9, meaning that all items were considered to be clear. Conclusions: The ACCI was successfully translated to Portuguese and culturally adapted for use in Brazil, the translated version maintaining the psychometric properties of the original version. The ACCI can be used in clinical practice because it is easy to understand and easily applied. PMID:29365000

  20. Statistical comparisons of Savannah River anemometer data applied to quality control of instrument networks

    International Nuclear Information System (INIS)

    Porch, W.M.; Dickerson, M.H.

    1976-08-01

    Continuous monitoring of extensive meteorological instrument arrays is a requirement in the study of important mesoscale atmospheric phenomena. The phenomena include pollution transport prediction from continuous area sources, or one time releases of toxic materials and wind energy prospecting in areas of topographic enhancement of the wind. Quality control techniques that can be applied to these data to determine if the instruments are operating within their prescribed tolerances were investigated. Savannah River Plant data were analyzed with both independent and comparative statistical techniques. The independent techniques calculate the mean, standard deviation, moments about the mean, kurtosis, skewness, probability density distribution, cumulative probability and power spectra. The comparative techniques include covariance, cross-spectral analysis and two dimensional probability density. At present the calculating and plotting routines for these statistical techniques do not reside in a single code so it is difficult to ascribe independent memory size and computation time accurately. However, given the flexibility of a data system which includes simple and fast running statistics at the instrument end of the data network (ASF) and more sophisticated techniques at the computational end (ACF) a proper balance will be attained. These techniques are described in detail and preliminary results are presented

  1. Method for controlling a coolant liquid surface of cooling system instruments in an atomic power plant

    International Nuclear Information System (INIS)

    Monta, Kazuo.

    1974-01-01

    Object: To prevent coolant inventory within a cooling system loop in an atomic power plant from being varied depending on loads thereby relieving restriction of varied speed of coolant flow rate to lowering of a liquid surface due to short in coolant. Structure: Instruments such as a superheater, an evaporator, and the like, which constitute a cooling system loop in an atomic power plant, have a plurality of free liquid surface of coolant. Portions whose liquid surface is controlled and portions whose liquid surface is varied are adjusted in cross-sectional area so that the sum total of variation in coolant inventory in an instrument such as a superheater provided with an annulus portion in the center thereof and an inner cylindrical portion and a down-comer in the side thereof comes equal to that of variation in coolant inventory in an instrument such as an evaporator similar to the superheater. which is provided with an overflow pipe in its inner cylindrical portion or down-comer, thereby minimizing variation in coolant inventory of the entire coolant due to loads thus minimizing variation in varied speed of the coolant. (Kamimura, M.)

  2. Improving Student Perceptions of Science through the Use of State-of-the-Art Instrumentation in General Chemistry Laboratory

    Science.gov (United States)

    Aurentz, David J.; Kerns, Stefanie L.; Shibley, Lisa R.

    2011-01-01

    Access to state-of-the-art instrumentation, namely nuclear magnetic resonance (NMR) spectroscopy, early in the college curriculum was provided to undergraduate students in an effort to improve student perceptions of science. Proton NMR spectroscopy was introduced as part of an aspirin synthesis in a guided-inquiry approach to spectral…

  3. The Spatial-Temporal Reasoning States of Children Who Play a Musical Instrument, Regarding the Mathematics Lesson: Teachers' Views

    Science.gov (United States)

    Tezer, Murat; Cumhur, Meryem; Hürsen, Emine

    2016-01-01

    The aim of this study is to try to investigate the spatial-temporal reasoning states of primary school children between the ages 8 and 11 who play an instrument, regarding mathematics lessons from the teachers' views. This current study is both qualitative and quantitative in nature. In other words, the mixed research method was used in the study.…

  4. 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.)

  5. Instrumentation, control and data acquisition system with multiple configurations for test in nuclear environment

    Energy Technology Data Exchange (ETDEWEB)

    Monti, Chiara, E-mail: chiara.monti@enea.it; Neri, Carlo; Pollastrone, Fabio

    2015-10-15

    Highlights: • ENEA developed and characterized a first prototype of the In-Vessel Viewing System (IVVS) probe for ITER. • Piezo motor technology to be used in IVVS probe was tested in neutrons, gamma radiations, high temperature, vacuum and high magnetic fields. • A general architecture of the Data Acquisition and Control System (DACS) was defined and then specialized for each test. • The test campaign has validated instrumentation solutions, which can be effectively used in final IVVS implementation or other ITER diagnostics or applications. - Abstract: The In-Vessel Viewing System is a 3D laser scanning system which will be used to inspect the blanket first wall in ITER. To make the IVVS probe design compatible with the harsh environmental conditions present in ITER, a test campaign was performed in 2012–2013 to verify the adequacy of the main components of the IVVS probe. The IVVS components inspected were an optical encoder, passive components and two customized ultrasonic piezoceramic motors that were instrumented with various sensors. A general architecture of the Data Acquisition and Control System (DACS) was defined and then specialized for each test. To be suitable for this test campaign, the DACS had to host various I/O modules and to properly interface the driver of the customized piezo motors, in order to permit the full control of the test and the acquisition of experimental data. This paper presents the instrumentation solutions designed and implemented for different facilities constraints and the related DACS developed in four specialized versions for the described test campaign.

  6. Development of a nuclear reactor control system simulator using virtual instruments

    International Nuclear Information System (INIS)

    Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares

    2011-01-01

    The International Atomic Energy Agency recommends the use of safety and friendly interfaces for monitoring and controlling the operational parameters of the nuclear reactors. This article describes a digital system being developed to simulate the behavior of the operating parameters using virtual instruments. The control objective is to bring the reactor power from its source level (mW) to a full power (kW). It is intended for education of basic reactor neutronic and thermohydraulic principles such as the multiplication factor, criticality, reactivity, period, delayed neutron, control by rods, fuel and coolant temperatures, power, etc. The 250 kW IPR-R1 TRIGA research reactor at Nuclear Technology Development Centre - CDTN was used as reference. TRIGA reactors, developed by General Atomics (GA), are the most widely used research reactor in the world. The simulator system is being developed using the LabVIEW (Laboratory Virtual Instruments Engineering Workbench) software, considering the modern concept of virtual instruments (VI's) using electronic processor and visual interface in video monitor. The main purpose of the system is to provide training tools for instructors and students, allowing navigating by user-friendly operator interface and monitoring tendencies of the operational variables. It will be an interactive tool for training and teaching and could be used to predict the reactor behavior. Some scenarios are presented to demonstrate that it is possible to know the behavior of some variables from knowledge of input parameters. The TRIGA simulator system will allow the study of parameters, which affect the reactor operation, without the necessity of using the facility. (author)

  7. rhBMP-2 for posterolateral instrumented lumbar fusion: a multicenter prospective randomized controlled trial.

    Science.gov (United States)

    Hurlbert, R John; Alexander, David; Bailey, Stewart; Mahood, James; Abraham, Ed; McBroom, Robert; Jodoin, Alain; Fisher, Charles

    2013-12-01

    Multicenter randomized controlled trial. To evaluate the effect of recombinant human bone morphogenetic protein (rhBMP-2) on radiographical fusion rate and clinical outcome for surgical lumbar arthrodesis compared with iliac crest autograft. In many types of spinal surgery, radiographical fusion is a primary outcome equally important to clinical improvement, ensuring long-term stability and axial support. Biologic induction of bone growth has become a commonly used adjunct in obtaining this objective. We undertook this study to objectify the efficacy of rhBMP-2 compared with traditional iliac crest autograft in instrumented posterolateral lumbar fusion. Patients undergoing 1- or 2-level instrumented posterolateral lumbar fusion were randomized to receive either autograft or rhBMP-2 for their fusion construct. Clinical and radiographical outcome measures were followed for 2 to 4 years postoperatively. One hundred ninety seven patients were successfully randomized among the 8 participating institutions. Adverse events attributable to the study drug were not significantly different compared with controls. However, the control group experienced significantly more graft-site complications as might be expected. 36-Item Short Form Health Survey, Oswestry Disability Index, and leg/back pain scores were comparable between the 2 groups. After 4 years of follow-up, radiographical fusion rates remained significantly higher in patients treated with rhBMP-2 (94%) than those who received autograft (69%) (P = 0.007). The use of rhBMP-2 for instrumented posterolateral lumbar surgery significantly improves the chances of radiographical fusion compared with the use of autograft. However, there is no associated improvement in clinical outcome within a 4-year follow-up period. These results suggest that use of rhBMP-2 should be considered in cases where lumbar arthrodesis is of primary concern.

  8. Development of a nuclear reactor control system simulator using virtual instruments

    Energy Technology Data Exchange (ETDEWEB)

    Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares, E-mail: ajp@cdtn.b, E-mail: amir@cdtn.b, E-mail: fsl@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The International Atomic Energy Agency recommends the use of safety and friendly interfaces for monitoring and controlling the operational parameters of the nuclear reactors. This article describes a digital system being developed to simulate the behavior of the operating parameters using virtual instruments. The control objective is to bring the reactor power from its source level (mW) to a full power (kW). It is intended for education of basic reactor neutronic and thermohydraulic principles such as the multiplication factor, criticality, reactivity, period, delayed neutron, control by rods, fuel and coolant temperatures, power, etc. The 250 kW IPR-R1 TRIGA research reactor at Nuclear Technology Development Centre - CDTN was used as reference. TRIGA reactors, developed by General Atomics (GA), are the most widely used research reactor in the world. The simulator system is being developed using the LabVIEW (Laboratory Virtual Instruments Engineering Workbench) software, considering the modern concept of virtual instruments (VI's) using electronic processor and visual interface in video monitor. The main purpose of the system is to provide training tools for instructors and students, allowing navigating by user-friendly operator interface and monitoring tendencies of the operational variables. It will be an interactive tool for training and teaching and could be used to predict the reactor behavior. Some scenarios are presented to demonstrate that it is possible to know the behavior of some variables from knowledge of input parameters. The TRIGA simulator system will allow the study of parameters, which affect the reactor operation, without the necessity of using the facility. (author)

  9. Regulatory Research of the PWR Severe Accident. Information Needs and Instrumentation for Hydrogen Control and Management

    International Nuclear Information System (INIS)

    Park, Gun Chul; Suh, Kune Y.; Lee, Jin Yong; Lee, Seung Dong

    2001-03-01

    The current research is concerned with generation of basic engineering data needed in the process of developing hydrogen control guidelines as part of accident management strategies for domestic nuclear power plants and formulating pertinent regulatory requirements. Major focus is placed on identification of information needs and instrumentation methods for hydrogen control and management in the primary system and in the containment, development of decision-making trees for hydrogen management and their quantification, the instrument availability under severe accident conditions, critical review of relevant hydrogen generation model and phenomena In relation to hydrogen behavior, we analyzed the severe accident related hydrogen generation in the UCN 3·4 PWR with modified hydrogen generation model. On the basis of the hydrogen mixing experiment and related GASFLOW calculation, the necessity of 3-dimensional analysis of the hydrogen mixing was investigated. We examined the hydrogen control models related to the PAR(Passive Autocatalytic Recombiner) and performed MAAP4 calculation in relation to the decision tree to estimate the capability and the role of the PAR during a severe accident

  10. Development of Temperature Control Solutions for Non-Instrumented Nucleic Acid Amplification Tests (NINAAT

    Directory of Open Access Journals (Sweden)

    Tamás Pardy

    2017-06-01

    Full Text Available Non-instrumented nucleic acid amplification tests (NINAAT are a novel paradigm in portable molecular diagnostics. They offer the high detection accuracy characteristic of nucleic acid amplification tests (NAAT in a self-contained device, without the need for any external instrumentation. These Point-of-Care tests typically employ a Lab-on-a-Chip for liquid handling functionality, and perform isothermal nucleic acid amplification protocols that require low power but high accuracy temperature control in a single well-defined temperature range. We propose temperature control solutions based on commercially available heating elements capable of meeting these challenges, as well as demonstrate the process by which such elements can be fitted to a NINAAT system. Self-regulated and thermostat-controlled resistive heating elements were evaluated through experimental characterization as well as thermal analysis using the finite element method (FEM. We demonstrate that the proposed solutions can support various NAAT protocols, as well as demonstrate an optimal solution for the loop-mediated isothermal amplification (LAMP protocol. Furthermore, we present an Arduino-compatible open-source thermostat developed for NINAAT applications.

  11. A thermal control system for long-term survival of scientific instruments on lunar surface.

    Science.gov (United States)

    Ogawa, K; Iijima, Y; Sakatani, N; Otake, H; Tanaka, S

    2014-03-01

    A thermal control system is being developed for scientific instruments placed on the lunar surface. This thermal control system, Lunar Mission Survival Module (MSM), was designed for scientific instruments that are planned to be operated for over a year in the future Japanese lunar landing mission SELENE-2. For the long-term operations, the lunar surface is a severe environment because the soil (regolith) temperature varies widely from nighttime -200 degC to daytime 100 degC approximately in which space electronics can hardly survive. The MSM has a tent of multi-layered insulators and performs a "regolith mound". Temperature of internal devices is less variable just like in the lunar underground layers. The insulators retain heat in the regolith soil in the daylight, and it can keep the device warm in the night. We conducted the concept design of the lunar survival module, and estimated its potential by a thermal mathematical model on the assumption of using a lunar seismometer designed for SELENE-2. Thermal vacuum tests were also conducted by using a thermal evaluation model in order to estimate the validity of some thermal parameters assumed in the computed thermal model. The numerical and experimental results indicated a sufficient survivability potential of the concept of our thermal control system.

  12. A thermal control system for long-term survival of scientific instruments on lunar surface

    International Nuclear Information System (INIS)

    Ogawa, K.; Iijima, Y.; Tanaka, S.; Sakatani, N.; Otake, H.

    2014-01-01

    A thermal control system is being developed for scientific instruments placed on the lunar surface. This thermal control system, Lunar Mission Survival Module (MSM), was designed for scientific instruments that are planned to be operated for over a year in the future Japanese lunar landing mission SELENE-2. For the long-term operations, the lunar surface is a severe environment because the soil (regolith) temperature varies widely from nighttime −200 degC to daytime 100 degC approximately in which space electronics can hardly survive. The MSM has a tent of multi-layered insulators and performs a “regolith mound”. Temperature of internal devices is less variable just like in the lunar underground layers. The insulators retain heat in the regolith soil in the daylight, and it can keep the device warm in the night. We conducted the concept design of the lunar survival module, and estimated its potential by a thermal mathematical model on the assumption of using a lunar seismometer designed for SELENE-2. Thermal vacuum tests were also conducted by using a thermal evaluation model in order to estimate the validity of some thermal parameters assumed in the computed thermal model. The numerical and experimental results indicated a sufficient survivability potential of the concept of our thermal control system

  13. Regulatory Research of the PWR Severe Accident. Information Needs and Instrumentation for Hydrogen Control and Management

    Energy Technology Data Exchange (ETDEWEB)

    Park, Gun Chul; Suh, Kune Y.; Lee, Jin Yong; Lee, Seung Dong [Seoul Nat' l Univ., Seoul (Korea, Republic of)

    2001-03-15

    The current research is concerned with generation of basic engineering data needed in the process of developing hydrogen control guidelines as part of accident management strategies for domestic nuclear power plants and formulating pertinent regulatory requirements. Major focus is placed on identification of information needs and instrumentation methods for hydrogen control and management in the primary system and in the containment, development of decision-making trees for hydrogen management and their quantification, the instrument availability under severe accident conditions, critical review of relevant hydrogen generation model and phenomena In relation to hydrogen behavior, we analyzed the severe accident related hydrogen generation in the UCN 3{center_dot}4 PWR with modified hydrogen generation model. On the basis of the hydrogen mixing experiment and related GASFLOW calculation, the necessity of 3-dimensional analysis of the hydrogen mixing was investigated. We examined the hydrogen control models related to the PAR(Passive Autocatalytic Recombiner) and performed MAAP4 calculation in relation to the decision tree to estimate the capability and the role of the PAR during a severe accident.

  14. A thermal control system for long-term survival of scientific instruments on lunar surface

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, K., E-mail: ogawa@astrobio.k.u-tokyo.ac.jp [Department of Complexity Science and Engineering, The University of Tokyo, 5-1-5 Kashiwanoha, Kashiwa, Chiba (Japan); Iijima, Y.; Tanaka, S. [Institute of Space and Astronautical Science, Japan Aerospace Exploration Agency, 3-1-1 Yoshinodai, Chuo, Sagamihara, Kanagawa (Japan); Sakatani, N. [The Graduate University for Advanced Studies, Shonan Village, Hayama, Kanagawa (Japan); Otake, H. [JAXA Space Exploration Center, Japan Aerospace Exploration Agency, 3-1-1 Yoshinodai, Chuo, Sagamihara, Kanagawa (Japan)

    2014-03-15

    A thermal control system is being developed for scientific instruments placed on the lunar surface. This thermal control system, Lunar Mission Survival Module (MSM), was designed for scientific instruments that are planned to be operated for over a year in the future Japanese lunar landing mission SELENE-2. For the long-term operations, the lunar surface is a severe environment because the soil (regolith) temperature varies widely from nighttime −200 degC to daytime 100 degC approximately in which space electronics can hardly survive. The MSM has a tent of multi-layered insulators and performs a “regolith mound”. Temperature of internal devices is less variable just like in the lunar underground layers. The insulators retain heat in the regolith soil in the daylight, and it can keep the device warm in the night. We conducted the concept design of the lunar survival module, and estimated its potential by a thermal mathematical model on the assumption of using a lunar seismometer designed for SELENE-2. Thermal vacuum tests were also conducted by using a thermal evaluation model in order to estimate the validity of some thermal parameters assumed in the computed thermal model. The numerical and experimental results indicated a sufficient survivability potential of the concept of our thermal control system.

  15. R and D in control, instrumentation, and electronic systems at CRNL

    International Nuclear Information System (INIS)

    Moeck, E.O.; Stirling, A.J.; Yan, G.

    1980-10-01

    Research and development in control, instrumentation, and electronics is part of the refinement of the CANDU power plant design and of the R and D work at the Chalk River Nuclear Laboratories. The programs presently being carried out in these areas are described in this report. Many of these projects originated in response to a potential for performance improvements in CANDU power plants and are aimed at extending plant capabilities and applying new technology and ideas to achieve better and less expensive systems. Some of these projects such as the development of in-reactor pressure transducers for fuel testing are to be completed in a matter of months. Others, for example heavy water vapor loss instruments, will have gone through the laboratory development phase within a year or two. More sophisicated developments such as multivariable controllers, computer-based safety systems, and advanced neutron detectors will continue over 4 or 5 years. This time scale also applies to the design and implementation of new control and safety systems for the NRU research reactor. Still others will require more than 5 years to be fully operational. New systems for the detection and location of failed fuel and a total information network with distributed intelligence, to be applied to future power stations, fall into that category. (auth)

  16. The Role of Clinical and Instrumented Outcome Measures in Balance Control of Individuals with Multiple Sclerosis

    Directory of Open Access Journals (Sweden)

    Neeta Kanekar

    2013-01-01

    Full Text Available Purpose. The aim of the study was to investigate differences in balance control between individuals with multiple sclerosis (MS and healthy control subjects using clinical scales and instrumented measures of balance and determine relationships between balance measures, fatigue, and disability levels in individuals with MS with and without a history of falls. Method. Twelve individuals with MS and twelve healthy controls were evaluated using the Berg Balance and Activities-specific Balance Confidence Scales, Modified Clinical Test of Sensory Interaction on Balance, and Limits of Stability Tests as well as Fatigue Severity Scale and Barthel Index. Results. Mildly affected individuals with MS had significant balance performance deficits and poor balance confidence levels (P<0.05. MS group had higher sway velocities and diminished stability limits (P<0.05, significant sensory impairments, high fatigue and disability levels (P<0.05. Sway velocity was a significant predictor of balance performance and the ability to move towards stability limits for the MS group. For the MS-fallers group, those with lower disability levels had faster movement velocities and better balance performance. Conclusion. Implementation of both clinical and instrumented tests of balance is important for the planning and evaluation of treatment outcomes in balance rehabilitation of people with MS.

  17. Instrumentation and control aging management: A focus on electronic parts and boards

    International Nuclear Information System (INIS)

    Crocombette, C.; Simon, G.; Favaro, P.; Naser, J.; Guffroy, G.

    2002-01-01

    Full text: The nuclear power industry is currently facing increasing aging and obsolescence issues with original equipment installed for instrumentation, control, and safety system applications. One area that needs attention is the aging of electronic boards and components used in instrumentation and control (I and C) systems in nuclear power plants (NPPs). In this context, EPRI has launched a project dedicated to NPP electronic component and board aging management. The goals of this project are: 1) to better understand the degradation mechanisms of I and C electronic systems; 2) to develop new methods to monitor prevalent mechanisms and forecast generic aging cases; and 3) to give guidelines for the aging management of I and C electronic systems. The ultimate objectives are: 1) to reduce the likelihood of losing plant availability due to a board or component failure; and 2) to reduce the global cost of maintenance by optimizing preventive maintenance tasks and the schedule for refurbishment or renewal. Degradation mechanisms of electronic boards in NPP - Aging mechanisms of electronic parts depend on technologies, manufacturing quality, and conditions of environment and operation. Aging of electronic parts is well documented in harsh environments (e.g., aerospace, military, or automotive industries data). However, only a small amount of data on electronic part failures in NPPs is available because the conditions are benign and the failure rates are supposed to be low. It is thus difficult to identify what will predominantly cause the aging of electronic systems after 20 or 30 years of operation. Usual causes are temperature, corrosion, temperature cycles, or extrinsic aggressions (Electrical Over Stress (EOS), Electro Static Discharges (ESD)). From field data and bibliographic analyses, we found that electrolytic capacitors, relays, potentiometers, power devices (thyristors, power transistors, etc.), optocouplers, on-board connectors, printed boards, integrated

  18. U.S. Department of Energy instrumentation and controls technology research for advanced small modular reactors

    International Nuclear Information System (INIS)

    Wood, Richard Thomas

    2013-01-01

    Instrumentation, controls, and human-machine interfaces (ICHMI) are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The U.S. Department of Energy (DOE) has recognized that ICHMI research, development, and demonstration (RD and D) is needed to resolve the technical challenges that may compromise the effective and efficient utilization of modern ICHMI technology and consequently inhibit realization of the benefits offered by expanded utilization of nuclear power. Consequently, key DOE programs have substantial ICHMI RD and D elements to their respective research portfolio. This article describes current ICHMI research to support the development of advanced small modular reactors. (author)

  19. Assessment and management of ageing of electrical instrumentation and control cables

    International Nuclear Information System (INIS)

    Pachner, J.; Burnay, S.G.

    2001-01-01

    This paper presents a summary of the results of an IAEA Co-ordinated Research Project (CRP) on Management of Ageing of In-containment Instrumentation and Control (I and C) Cables addressing current practices and techniques for assessing and managing ageing degradation of cables in real nuclear power plant (NPP) environments. These practices and techniques include environmental qualification, identification of cables of concern, condition monitoring, and predictive modelling. The paper shows how they should be integrated within a plant-specific ageing management programme utilising a systematic ageing management process, which is an adaptation of Deming Plan-Do-Check-Act cycle to ageing management. (author)

  20. MicroASC instrument onboard Juno spacecraft utilizing inertially controlled imaging

    DEFF Research Database (Denmark)

    Pedersen, David Arge Klevang; Jørgensen, Andreas Härstedt; Benn, Mathias

    2016-01-01

    This contribution describes the post-processing of the raw image data acquired by the microASC instrument during the Earth-fly-by of the Juno spacecraft. The images show a unique view of the Earth and Moon system as seen from afar. The procedure utilizes attitude measurements and inter......-calibration of the Camera Head Units of the microASC system to trigger the image capturing. The triggering is synchronized with the inertial attitude and rotational phase of the sensor acquiring the images. This is essentially works as inertially controlled imaging facilitating image acquisition from unexplored...