University Reactor Instrumentation Program

International Nuclear Information System (INIS)

Vernetson, W.G.

1992-11-01

Recognizing that the University Reactor Instrumentation Program was developed in response to widespread needs in the academic community for modernization and improvement of research and training reactors at institutions such as the University of Florida, the items proposed to be supported by this grant over its two year period have been selected as those most likely to reduce foreed outages, to meet regulatory concerns that had been expressed in recent years by Nuclear Regulatory Commission inspectors or to correct other facility problems and limitations. Department of Energy Grant Number DE-FG07-90ER129969 was provided to the University of Florida Training Reactor(UFTR) facility through the US Department of Energy's University Reactor Instrumentation Program. The original proposal submitted in February, 1990 requested support for UFTR facility instrumentation and equipment upgrades for seven items in the amount of $107,530 with $13,800 of this amount to be the subject of cost sharing by the University of Florida and $93,730 requested as support from the Department of Energy. A breakdown of the items requested and total cost for the proposed UFTR facility instrumentation and equipment improvements is presented

Instrumentation for Power System Disturbance Monitoring, Data ...

African Journals Online (AJOL)

In this paper, the level of instrumentation for power system disturbance monitoring, data acquisition and control in Nigerian Electric Power System; National Electric Power Authority (NEPA) is presented. The need for accurate power system disturbance monitoring is highlighted. A feature of an adequate monitoring, data ...

Instrumentation and electrical program at the Three Mile Island Unit 2, Technical Integration Office

International Nuclear Information System (INIS)

Hecker, L.A.

1982-01-01

The Three Mile Island Unit 2 accident of March 28, 1979 presents unique research opportunities that can provide valuable information on nuclear power plant safety philosophy and safety systems performance. The Technical Integration Office at Three Mile Island was established by the Department of Energy to manage a broad-based research and development program. One significant part of this effort is the Instrumentation and Electrical Program, which operates: (1) to identify instruments and electrical components that failed during or since the accident; (2) to test and analyze them in order to identify the causes of failure; and (3) to assess the survivability of those that did not fail. The basis for selection of equipment is discussed, and the testing methodology is described. Also, some results of Instrumentation and Electrical Program work to date are presented

Preventive maintenance instrumentation results in Spanish nuclear power plants

International Nuclear Information System (INIS)

Palomo Anaya, M. Jose; Verdu Martin, Gumersindo; Arnaldos Gonzalvez, Adoracion; Nieva, Marcelino Curiel

2011-01-01

This paper is a recompilation of the most significant results in relation to the researching in Preventive and Predictive Maintenance in critical nuclear instrumentation for power plant operation, which it is being developed by Logistica y Acondicionamientos Industriales and The Isirym Institute of the Polytechnic University of Valencia. Instrumentation verification and test, it is a priority of the Power Plants Control and Instrumentation Department technicians. These procedures are necessary information for the daily power plant work. It is performed according to different procedures and in different moments of the fuel cycle depending on the instrumentation critical state and the monitoring process. Normally, this study is developed taking into account the instantaneous values of the instrumentation measures and, after their conversion to physical magnitude, they are analyzed according to the power plant operation point. Moreover, redundant sensors measurements are taken into consideration to the equipment and/or power plant monitoring. This work goes forward and it is in advanced to the instrument analysis as it is, independently of the operation point, using specific signal analysis techniques for preventive and predictive maintenance, with the aim to obtain not only information about possible malfunctions, but the degradation scale presented in the instrument or in the system measured. We present seven real case studies of Spanish Nuclear Power Plants each of them shall give a significant contribution to problem resolution and power plant performance: Fluctuations in sensor lines (case 1), Air presence in feed water lines (case 2), Root valve partially closed (case 3), Sensor malfunctions (case 4), Electrical source malfunctions (case 5), RTD malfunctions (case 6) and LPRM malfunctions (case 7). (author)

Preventive maintenance instrumentation results in Spanish nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Palomo Anaya, M. Jose; Verdu Martin, Gumersindo, E-mail: mpalomo@iqn.upv.es, E-mail: gverdu@iqn.upv.es [ISIRYM Universidad Politecnica de Valencia, Valencia (Spain); Arnaldos Gonzalvez, Adoracion, E-mail: a.arnaldos@titaniast.com [TITANIA Servicios Tecnologicos SL, Valencia (Spain); Nieva, Marcelino Curiel, E-mail: m.curiel@lainsa.com [Logistica y Acondicionamientos Industriales SAU (LAINSA), Valencia (Spain)

2011-07-01

This paper is a recompilation of the most significant results in relation to the researching in Preventive and Predictive Maintenance in critical nuclear instrumentation for power plant operation, which it is being developed by Logistica y Acondicionamientos Industriales and The Isirym Institute of the Polytechnic University of Valencia. Instrumentation verification and test, it is a priority of the Power Plants Control and Instrumentation Department technicians. These procedures are necessary information for the daily power plant work. It is performed according to different procedures and in different moments of the fuel cycle depending on the instrumentation critical state and the monitoring process. Normally, this study is developed taking into account the instantaneous values of the instrumentation measures and, after their conversion to physical magnitude, they are analyzed according to the power plant operation point. Moreover, redundant sensors measurements are taken into consideration to the equipment and/or power plant monitoring. This work goes forward and it is in advanced to the instrument analysis as it is, independently of the operation point, using specific signal analysis techniques for preventive and predictive maintenance, with the aim to obtain not only information about possible malfunctions, but the degradation scale presented in the instrument or in the system measured. We present seven real case studies of Spanish Nuclear Power Plants each of them shall give a significant contribution to problem resolution and power plant performance: Fluctuations in sensor lines (case 1), Air presence in feed water lines (case 2), Root valve partially closed (case 3), Sensor malfunctions (case 4), Electrical source malfunctions (case 5), RTD malfunctions (case 6) and LPRM malfunctions (case 7). (author)

Seismic instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Senne Junior, M.

1983-01-01

A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those Plants, against the action of earthquakes is described. The instrumentation described is based on the nuclear standards in force. The minimum amount of sensors and other components used, as well as their general localization, is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The various devices used are not covered in detail, except for the accelerometer, which is the seismic instrumentation basic component. (Author) [pt

Seismic instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Senne Junior, M.

1983-07-01

A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those plants, against the action of earth quarks is described. The instrumentation is based on the nuclear standards and other components used, as well as their general localization is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The accelerometer is described in detail. (Author) [pt

HPS instrument calibration laboratory accreditation program

Energy Technology Data Exchange (ETDEWEB)

Masse, F.X; Eisenhower, E.H.; Swinth, K.L.

1993-12-31

The purpose of this paper is to provide an accurate overview of the development and structure of the program established by the Health Physics Society (HPS) for accrediting instrument calibration laboratories relative to their ability to accurately calibrate portable health physics instrumentation. The purpose of the program is to provide radiation protection professionals more meaningful direct and indirect access to the National Institute of Standards and Technology (NIST) national standards, thus introducing a means for improving the uniformity, accuracy, and quality of ionizing radiation field measurements. The process is designed to recognize and document the continuing capability of each accredited laboratory to accurately perform instrument calibration. There is no intent to monitor the laboratory to the extent that each calibration can be guaranteed by the program; this responsibility rests solely with the accredited laboratory.

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

International Nuclear Information System (INIS)

Anderson, G.R.

1987-01-01

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

About the automated instrumentation in nuclear power plants; Sobre la instrumentacion automatizada en plantas nucleares

Energy Technology Data Exchange (ETDEWEB)

Segovia de los Rios, J. A.; Benitez R, J. S. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Garduno G, M P., E-mail: armando.segovia@inin.gob.mx [Instituto Tecnologica de Toluca, Av. Tecnologico s/n, 52140 Metepec, Estado de Mexico (Mexico)

2011-11-15

The automation of the inspection processes and monitoring in nuclear facilities have as main objective the reduction of acquired radiation dose for the operators of the diverse work programs. For example, a typical maintenance task is the problems correction of leaks in the hydraulic facilities of the vapor circuits where is necessary the repair of pipes, measuring and control elements, as the valves. A program of effective maintenance should contemplate strategies of appropriate monitoring for the immediate detection of possible failures, with the purpose of the remedy them opportunely. For this function of failures detection is necessary to have instruments that allow the measuring of the parameters that facilitate their characterization. Given the prevailing conditions in the nuclear facilities, such instruments should possess special characteristics, reason why is necessary a study of them, as well as a careful selection of the susceptible apparatuses of being used. For this reason, this work presents a discussion about some of the existent conditions in the nuclear power plants, as well as the aspects to consider for the automated instrumentation of some places of a nuclear power plant. (Author)

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

Embedded design based virtual instrument program for positron beam automation

International Nuclear Information System (INIS)

Jayapandian, J.; Gururaj, K.; Abhaya, S.; Parimala, J.; Amarendra, G.

2008-01-01

Automation of positron beam experiment with a single chip embedded design using a programmable system on chip (PSoC) which provides easy interfacing of the high-voltage DC power supply is reported. Virtual Instrument (VI) control program written in Visual Basic 6.0 ensures the following functions (i) adjusting of sample high voltage by interacting with the programmed PSoC hardware, (ii) control of personal computer (PC) based multi channel analyzer (MCA) card for energy spectroscopy, (iii) analysis of the obtained spectrum to extract the relevant line shape parameters, (iv) plotting of relevant parameters and (v) saving the file in the appropriate format. The present study highlights the hardware features of the PSoC hardware module as well as the control of MCA and other units through programming in Visual Basic

Instrument calibration optimization at Bruce Power: ECI loops

International Nuclear Information System (INIS)

Chugh, V.; Angelova, M.; Ghias, S.; Parmar, R.; Wang, V.; Xie, H.; Higgs, J.; Schut, J.; Cruchley, I.

2011-01-01

Most instruments in a nuclear power plant are calibrated at regular intervals to ensure consistency with the assumptions in the plant Technical Specifications and/or Safe Operating Envelope (SOE) compliance limits (e.g., As-Found Tolerance). In the Instrument Uncertainty Calculations (IUC), As-Found Tolerance for instrument drift is estimated based on statistical analysis of As-Found and As-Left calibration data such as that carried out for Bruce NGS by EPRI (Electric Power Research Institute) in 1998. Bruce specific drift values were found to compare favorably with industry benchmarks. Recently a significant amount of work has been done by EPRI and IAEA (International Atomic Energy Agency) on extending calibration intervals of safety related instruments. Reduction in calibration frequency reduces time commitments on the part of Authorized Nuclear Operators and safety system qualified Control Maintenance Technicians, and allows more schedule flexibility. To establish the proof of concept, As-Left/As-Found tolerances and available margins have been evaluated for the Bruce B Emergency Coolant Injection (ECI) system instrument loops to determine whether an extension of the calibration period from one or two year to three years is justifiable on the basis that these loops will still be in compliance with SOE. The analysis showed that 60% of instruments in the ECI system are qualified for calibration interval extension up to three years. Sensitivity assessment of the effect of proposed changes in calibration intervals for 60% of the instruments on the ECI system unavailability has also been performed using the current Bruce Power ECI unavailability model. The results show that, the largest ECI Predicted Future Unavailability (PFU) is 9.2E-4 year/year for in-core LOCA accident. This value is still below the target unavailability of 1.0E-3 year/year. (author)

Instrument calibration optimization at Bruce Power: ECI loops

Energy Technology Data Exchange (ETDEWEB)

Chugh, V.; Angelova, M.; Ghias, S.; Parmar, R.; Wang, V.; Xie, H. [AMEC NSS, Toronto, Ontario (Canada); Higgs, J.; Schut, J.; Cruchley, I. [Bruce Power, Tiverton, Ontario (Canada)

2011-07-01

Most instruments in a nuclear power plant are calibrated at regular intervals to ensure consistency with the assumptions in the plant Technical Specifications and/or Safe Operating Envelope (SOE) compliance limits (e.g., As-Found Tolerance). In the Instrument Uncertainty Calculations (IUC), As-Found Tolerance for instrument drift is estimated based on statistical analysis of As-Found and As-Left calibration data such as that carried out for Bruce NGS by EPRI (Electric Power Research Institute) in 1998. Bruce specific drift values were found to compare favorably with industry benchmarks. Recently a significant amount of work has been done by EPRI and IAEA (International Atomic Energy Agency) on extending calibration intervals of safety related instruments. Reduction in calibration frequency reduces time commitments on the part of Authorized Nuclear Operators and safety system qualified Control Maintenance Technicians, and allows more schedule flexibility. To establish the proof of concept, As-Left/As-Found tolerances and available margins have been evaluated for the Bruce B Emergency Coolant Injection (ECI) system instrument loops to determine whether an extension of the calibration period from one or two year to three years is justifiable on the basis that these loops will still be in compliance with SOE. The analysis showed that 60% of instruments in the ECI system are qualified for calibration interval extension up to three years. Sensitivity assessment of the effect of proposed changes in calibration intervals for 60% of the instruments on the ECI system unavailability has also been performed using the current Bruce Power ECI unavailability model. The results show that, the largest ECI Predicted Future Unavailability (PFU) is 9.2E-4 year/year for in-core LOCA accident. This value is still below the target unavailability of 1.0E-3 year/year. (author)

Continuous high-temperature surveillance instrumentation for Dresden-2 hydrogen water chemistry program

International Nuclear Information System (INIS)

Fleming, M.F.; Mitchell, R.A.; Nelson, J.L.

1987-01-01

The objective of this program (under EPRI Contract RP1930-11) is to install and operate a high-temperature surveillance instrumentation system capable of monitoring the length of cracks in boiling water reactor (BWR) piping during plant operation. The ability to measure crack growth in BWR power plant piping welds is important to rapidly identify the effectiveness of repairs (such as the Hydrogen Water Chemistry Program). The feasibility of a system capable of continuous ultrasonic instrumentation at 600 0 F (288 0 C) was successfully demonstrated at the Dresden-2 suction line known as N1B. This intergranular stress corrosion cracking (IGSCC) surveillance instrumentation is sound in principal, because it survived on N1B for a time period of more than nine months from April 1985 to January 1986 (the last time data were recorded). The redesigned low-profile transducer system used for this system operated successfully for the same nine-month time period. This low profile transducer fits in the two-inch space normally occupied by insulation. As a result of poor routing of the coaxial cables running from the low-profile transducer to the electrical feed-throughs between the drywell and containment, these cables melted. Other instrument cables nearby were not damaged

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

Soil monitoring instrumentation

International Nuclear Information System (INIS)

Umbarger, C.J.

1981-01-01

The Los Alamos Scientific Laboratory (LASL) has an extensive program for the development of nondestructive assay instrumentation for the quantitative analysis of transuranic (TRU) materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. Included are wastes generated in decontamination and decommissioning of outdated nuclear facilities, as well as from old waste-burial-ground exhumation programs. The assay instrumentation is designed to have detection limits below 10 nCi/g wherever practicable. The assay instrumentation that is applied specifically to soil monitoring is discussed

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

International Nuclear Information System (INIS)

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

1997-01-01

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

Texas Instruments Technical Seminar: Power Management and Wireless

CERN Multimedia

2006-01-01

Monday 6 November TECHNICAL TRAINING SEMINAR 14:00 to 17:30 - Training Centre Auditorium (bldg. 593) Texas Instruments Technical Seminar: Power Management and Wireless Michael Scholtholt, Field Application Engineer / TEXAS INSTRUMENTS (US, D, CH) The range of power management products available today offers the possibility to find the best solution for each application. To select the right product it is therefore necessary to understand system requirements, how power supply products work, and where they differentiate. This Technical Training Seminar will also present an overview of how to choose the right RF platform based on markets and applications: nowadays almost everbody has at least one wireless product in use, and this tendency seems to increase significantly. Power Management Voltage mode vs. current mode control Differentiating DC/DC converters by analyzing control and compensation schemes: line / load regulation, transient response, BOM, board space, ease-of-use Introduction to evaluati...

Texas Instruments Technical Seminar: Power Management and Wireless

CERN Multimedia

2006-01-01

Monday 6 November TECHNICAL TRAINING SEMINAR 14:00 to 17:30 - Training Centre Auditorium (bldg. 593) Texas Instruments Technical Seminar: Power Management and Wireless Michael Scholtholt, Field Application Engineer / TEXAS INSTRUMENTS (US, D, CH) The range of power management products available today offers the possibility to find the best solution for each application. To select the right product it is therefore necessary to understand system requirements, how power supply products work, and where they differentiate. This Technical Training Seminar will also present an overview of how to choose the right RF platform based on markets and applications: nowadays almost everbody has at least one wireless product in use, and this tendency seems to increase significantly. Power Management Voltage mode vs. current mode control Differentiating DC/DC converters by analyzing control and compensation schemes: line / load regulation, transient response, BOM, board space, ease-of-use Introduction to evalu...

Learning Team Breach of a Posted Barricade to Connect an Instrument to Power

Energy Technology Data Exchange (ETDEWEB)

Wilburn, Dianne Williams [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-04-19

On February 15, 2017, a DESHF-STO HPFC (health physics field coordinator) was asked by an NEN-1 employee if they could move an instrument, a radiation dosimetry system, from A166A to another lab at TA-35 Building 2. The HPFC walked the job down and discovered the instrument was connected to power. The instrument had not been connected to power previously. See photo 1. The instrument is located within an RCA (radiological control area). Entry to connect the instrument to power the instrument requires contacting RP. RP personnel had not been contacted as required as stated in the RCA posting.

Imperative-program transformation by instrumented-interpreter specialization

DEFF Research Database (Denmark)

Debois, Søren

2008-01-01

We describe how to implement strength reduction, loop-invariant code motion and loop quasi-invariant code motion by specializing instrumented interpreters. To curb code duplication intrinsic to such specialization, we introduce a new program transformation, rewinding, which uses Moore-automata mi......We describe how to implement strength reduction, loop-invariant code motion and loop quasi-invariant code motion by specializing instrumented interpreters. To curb code duplication intrinsic to such specialization, we introduce a new program transformation, rewinding, which uses Moore...

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)

The Instrumentation Program for the Thirty Meter Telescope

OpenAIRE

Simard, Luc; Crampton, David; Ellerbroek, Brent; Boyer, Corinne

2012-01-01

An overview of the current status of the Thirty Meter Telescope (TMT) instrumentation program is presented. Science cases and operational concepts as well as their links to the instruments are continually revisited and updated through a series of workshops and conferences. Work on the three first-light instruments (WFOS IRIS, and IRMS) has made significant progress, and many groups in TMT partner communities are developing future instrument concepts. Other instrument-related subsystems are al...

The Standard, Power, and Color Model of Instrument Combination in Romantic-Era Symphonic Works

Directory of Open Access Journals (Sweden)

Randolph Johnson

2011-08-01

Full Text Available The Standard, Power, and Color (SPC model describes the nexus between musical instrument combination patterns and expressive goals in music. Instruments within each SPC group tend to attract each other and work as a functional unit to create orchestral gestures. Standard instruments establish a timbral groundwork; Power instruments create contrast through loud dynamic climaxes; and Color instruments catch listeners’ attention by means of their sparing use. Examples within these three groups include violin (Standard, piccolo (Power, and harp (Color. The SPC theory emerges from analyses of nineteenth-century symphonic works. Multidimensional scaling analysis of instrument combination frequencies maps instrument relationships; hierarchical clustering analysis indicates three SPC groups within the map. The SPC characterization is found to be moderately robust through the results of hypothesis testing: (1 Color instruments are included less often in symphonic works; (2 when Color instruments are included, they perform less often than the average instrument; and (3 Color and non-Color instruments have equal numbers of solo occurrences. Additionally, (4 Power instruments are positively associated with louder dynamic levels; and (5 when Power instruments are present in the musical texture, the pitch range spanned by the entire orchestra does not become more extreme.

Efforts onto electricity and instrumentation technology for nuclear power generation

International Nuclear Information System (INIS)

Hayakawa, Toshifumi

2000-01-01

Nuclear power generation shares more than 1/3 of all amounts of in-land generation at present, as a supplying source of stable electric energy after 2000 either. As a recent example of efforts onto electricity and instrumentation technology for nuclear power generation, there are, on instrumentation control system a new central control board aiming at reduction of operator's load, protection of human error, and upgrading of system reliability and economics by applying high level micro-processor applied technique and high speed data transfer technique to central monitoring operation and plant control protection, on a field of reactor instrumentation a new digital control rod position indicator improved of conventional system on a base of operation experience and recent technology, on a field of radiation instrumentation a new radiation instrumentation system accumulating actual results in a wide application field on a concept of application to nuclear power plant by adopting in-situ separation processing system using local network technique, and on a field of operation maintenance and management a conservation management system for nuclear generation plant intending of further effectiveness of operation maintenance management of power plant by applying of operation experience and recent data processing and communication technology. And, in the large electric apparatus, there are some generators carried out production and verification of a model one with actual size in lengthwise dimension, to correspond to future large capacity nuclear power plant. By this verification, it was proved that even large capacity generator of 1800 MVA class could be manufactured. (G.K.)

Evolutionary programming for neutron instrument optimisation

Energy Technology Data Exchange (ETDEWEB)

Bentley, Phillip M. [Hahn-Meitner Institut, Glienicker Strasse 100, D-14109 Berlin (Germany)]. E-mail: phillip.bentley@hmi.de; Pappas, Catherine [Hahn-Meitner Institut, Glienicker Strasse 100, D-14109 Berlin (Germany); Habicht, Klaus [Hahn-Meitner Institut, Glienicker Strasse 100, D-14109 Berlin (Germany); Lelievre-Berna, Eddy [Institut Laue-Langevin, 6 rue Jules Horowitz, BP 156, 38042 Grenoble Cedex 9 (France)

2006-11-15

Virtual instruments based on Monte-Carlo techniques are now integral part of novel instrumentation development and the existing codes (McSTAS and Vitess) are extensively used to define and optimise novel instrumental concepts. Neutron spectrometers, however, involve a large number of parameters and their optimisation is often a complex and tedious procedure. Artificial intelligence algorithms are proving increasingly useful in such situations. Here, we present an automatic, reliable and scalable numerical optimisation concept based on the canonical genetic algorithm (GA). The algorithm was used to optimise the 3D magnetic field profile of the NSE spectrometer SPAN, at the HMI. We discuss the potential of the GA which combined with the existing Monte-Carlo codes (Vitess, McSTAS, etc.) leads to a very powerful tool for automated global optimisation of a general neutron scattering instrument, avoiding local optimum configurations.

Evolutionary programming for neutron instrument optimisation

International Nuclear Information System (INIS)

Bentley, Phillip M.; Pappas, Catherine; Habicht, Klaus; Lelievre-Berna, Eddy

2006-01-01

Virtual instruments based on Monte-Carlo techniques are now integral part of novel instrumentation development and the existing codes (McSTAS and Vitess) are extensively used to define and optimise novel instrumental concepts. Neutron spectrometers, however, involve a large number of parameters and their optimisation is often a complex and tedious procedure. Artificial intelligence algorithms are proving increasingly useful in such situations. Here, we present an automatic, reliable and scalable numerical optimisation concept based on the canonical genetic algorithm (GA). The algorithm was used to optimise the 3D magnetic field profile of the NSE spectrometer SPAN, at the HMI. We discuss the potential of the GA which combined with the existing Monte-Carlo codes (Vitess, McSTAS, etc.) leads to a very powerful tool for automated global optimisation of a general neutron scattering instrument, avoiding local optimum configurations

Program of RA reactor start-up to nominal power

International Nuclear Information System (INIS)

1959-01-01

The zero start-up program is followed by the program of RA reactor start-up to nominal power. This program is described in detail and includes the following measurements: radiation characteristics at the exit of the channels; gamma and fast neutron dose distribution in the reactor; influence of absorbers on the reactivity; temperature effect; absolute flux and calibration of ionization chambers; xenon effect; thermal and hydraulics; dosimetry around the reactor; neutron flux in the reactor core and in the reactor hall; heavy water level; thermal characteristics after shutdown. A list of measuring devices and instrumentation is included with the detailed action plan and list of responsible staff members

Safeguarding on-power fuelled reactors - instrumentation and techniques

International Nuclear Information System (INIS)

Waligura, A.; Konnov, Y.; Smith, R.M.; Head, D.A.

1977-01-01

Instrumentation and techniques applicable to safeguarding reactors that are fuelled on-power, particularly the CANDU type, have been developed. A demonstration is being carried out at the Douglas Point Nuclear Generating Station in Canada. Irradiated nuclear materials in certain areas - the reactor and spent fuel storage bays - are monitored using photographic and television cameras, and seals. Item accounting is applied by counting spent-fuel bundles during transfer from the reactor to the storage bay and by placing these spent-fuel bundles in a sealed enclosure. Provision is made for inspection and verification of the bundles before sealing. The reactor's power history is recorded by a track-etch power monitor. Redundancy is provided so that the failure of any single piece of equipment does not invalidate the entire safeguards system. Several safeguards instruments and devices have beeen developed and evaluated. These include a super-8 mm surveillance camera system, a television surveillance system, a spent-fuel bundle counter, a device to detect dummy fuel bundles, a cover for enclosing a stack of spent-fuel bundles, and a seal suitable for underwater installation and ultrasonic interrogation. The information provided by these different instruments should increase the effectiveness of Agency safeguards and, when used in combination with other measures, will facilitate inspection at reactor sites

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

Recognition of Instrumentation Gauge in the Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Cho, Jai Wan; Jeong, Kyung Min [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Nuclear emergency robots were developed in 2001 as the countermeasure following the criticality accident at the JCO (uranium refinery facility) in Tokaimura, Japan in 1999. We assumed that these nuclear emergency robots were deployed (or put into) for a mitigation (or management) of severe accident, for example, occurred at Fukushima Daiichi nuclear power plant. In the case, the image understanding using a color CCD camera, loaded on the nuclear emergency robot, is important. We proposed an image processing technique to read indication value of the IC water level gauges using the structural characteristics of the instrumentation panels (water level gauges) located inside the reactor building. At first, we recognized the scales on the instrumentation panel using the geometric shape of the panel. And then, we could read the values of the instrumentation gauge by calculating the slope of the needle on the gauge. Using the proposed algorithm, we deciphered instrumentation panels for the four water level gauges and indicators shown on the IC video released by TEPCO and Japanese Nuclear Regulatory Commission of Japan. In this paper, recognition of the instrumentation gauges inside reactor building of the nuclear power plant by an image processing technology is described.

Wilberforce Power Technology in Education Program

Science.gov (United States)

Gordon, Edward M.; Buffinger, D. R.; Hehemann, D. G.; Breen, M. L.; Raffaelle, R. P.

1999-01-01

The Wilberforce Power Technology in Education Program is a multipart program. Three key parts of this program will be described. They are: (1) WISE-The Wilberforce Summer Intensive Experience. This annual offering is an educational program which is designed to provide both background reinforcement and a focus on study skills to give the participants a boost in their academic performance throughout their academic careers. It is offered to entering Wilberforce students. Those students who take advantage of WISE learn to improve important skills which enable them to work at higher levels in mathematics, science and engineering courses throughout their college careers, but most notably in the first year of college study. (2) Apply technology to reaming. This is being done in several ways including creating an electronic chemistry text with hypertext links to a glossary to help the students deal with the large new vocabulary required to describe and understand chemistry. It is also being done by converting lecture materials for the Biochemistry class to PowerPoint format. Technology is also being applied to learning by exploring simulation software of scientific instrumentation. (3) Wilberforce participation in collaborative research with NASA's John H. Glenn Research Center at Lewis Field. This research has focused on two areas in the past year. The first of these is the deposition of solar cell materials. A second area involves the development of polymeric materials for incorporation into thin film batteries.

A borehole instrumentation program for characterization of unsaturated-zone percolation

International Nuclear Information System (INIS)

Kume, J.; Rousseau, J.P.

1994-01-01

A borehole instrumentation and monitoring program has been designed by the US Geological Survey to support site characterization of unsaturated-zone percolation at Yucca Mountain, Nye County, Nevada. This program provides a means of defining the unsaturated-zone fluid flow (liquid and gas) potential field in a setting that incorporates large-scale stratigraphic and structural features, and the influences of geothermal heat flow and atmospheric pressure changes. Data derived from this program will be used to evaluate the suitability of Yucca Mountain as a mined geologic-repository for the storage of high-level, radioactive waste. These data include in-situ temperature, pneumatic pressure, and water potential. In addition, the instrumentation program provides facilities for gas-sampling, gas-tracer diffusion testing, water-injection testing, water-level monitoring, neutron moisture-meter monitoring, temperature profiling, and in-situ recalibration of the downhole sensors. The program included testing and development of: (1) precision sensors for measurement; (2) a downhole instrumentation-station-apparatus to house the sensors, recalibrate sensors in-situ, and allow access to instrument stations for other testing purposes; and (3) surface-based support and instrumentation facilities

Soil monitoring instrumentation

International Nuclear Information System (INIS)

Umbarger, C.J.

1980-01-01

The Los Alamos Scientific Laboratory (LASL) has an extensive program for the development of nondestructive assay instrumentation for the quantitative analysis of transuranic (TRU) materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. Included are wastes generated in decontamination and decommissioning of outdated nuclear facilities as well as wastes from old waste burial ground exhumation programs. The assay instrumentation is designed to have detection limits below 10 nCi/g wherever practicable. Because of the topic of this workshop, only the assay instrumentation applied specifically to soil monitoring will be discussed here. Four types of soil monitors are described

Solar electric power for instruments at remote sites

Science.gov (United States)

McChesney, P.J.

2000-01-01

Small photovoltaic (PV) systems are the preferred method to power instruments operating at permanent locations away from the electric power grid. The low-power PV power system consists of a solar panel or small array of panels, lead-acid batteries, and a charge controller. Even though the small PV power system is simple, the job of supplying power at a remote site can be very demanding. The equipment is often exposed to harsh conditions. The site may be inaccessible part of the year or difficult and expensive to reach at any time. Yet the system must provide uninterrupted power with minimum maintenance at low cost. This requires good design. Successful small PV systems often require modifications by a knowledgeable fieldworker to adapt to conditions at the site. Much information is available in many places about solar panels, lead-acid batteries, and charging systems but very little of it applies directly to low power instrument sites. The discussion here aims to close some of the gap. Each of the major components is described in terms of this application with particular attention paid to batteries. Site problems are investigated. Finally, maintenance and test procedures are given. This document assumes that the reader is engaged in planning or maintaining low-power PV sites and has basic electrical and electronic knowledge. The area covered by the discussion is broad. To help the reader with the many terms and acronyms used, they are shown in bold when first used and a glossary is provided at the end of the paper.

Instrumentation of a manually programmed neutron diffractometer

DEFF Research Database (Denmark)

Hansen, K.B.; Neisig, K.E.

1966-01-01

This paper describes essentially the digital part of the instrumentation for a neutron diffractometer in which the measuring procedure is governed by a control unit involving a fixed number of program points. A simultaneously running test program monitors the information transfer from the data...... sources and to the print-out in table form. The experimental conditions must be set by a panel switch selected program, which allows a desired parameter program to be executed....

Biomass power generation in competitive markets - The impact of instruments and regulations

International Nuclear Information System (INIS)

Ackermann, Thomas; Soeder, Lennart

1999-01-01

This paper presents and briefly evaluates the most important existing market instruments and market schemes which support the development of renewable energy generation as well as the impact of market regulations on the development of biomass power generation. The evaluation of the existing instruments focuses on the incentives provided by the various instruments to reduce production costs. The instruments and schemes are: Feed-in Tariffs, Net Metering, Bidding Process, Fixed Quotas, Green Certificate Trading, Green Power Exchange, Green Pricing. Feed-in tariffs and net metering are important instruments to get the different technologies 'off the ground', however, they can only be considered an interim solution as they do not necessarily lead to cost reduction. A bidding process is one way to achieve these cost reductions, but high transaction costs will support the development of large renewable energy projects, which is not always the desired effect. Fixed quotas combined with green certificate trading or a power exchange in combination with Green Pricing seem to lead to similar costs reduction, however, so far there is only limited experience with such instruments. The analysis of the impact of market regulations focuses on international electricity markets with a power exchange. Such markets exist, for example, in Scandinavia, England and Wales, Australia, New Zealand and California. The analysis showed that new distributed generation, for example based on biomass, faces significant market barriers. Furthermore, distributed generation is not treated equally within the market regulations compared to large-scale power generation

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)

The Import-Substitution Adaptation of Power Engineering Programs

Directory of Open Access Journals (Sweden)

Aleksandr N. Kuzminov

2017-03-01

Full Text Available The realization problem of the import substitution policy in the context of existing programs for the individual branches development is considered in the paper on the example of power engineering. There is a contradiction to the objective of programs reflected in the process of alignment, which consists in stabilizing on the one hand and on the development of innovative on the other hand. In addition, the analysis of the implementation of power engineering of the Russian Federation for 2010-2020 and up to 2030 revealed significant shortcomings and deficiencies that reinforce the negative trends of this pairing. Classification of problems and purpose allowed choosing the most significant conceptual directions, methodologically based on the ideas of self-organization and balance, which can get instrumentality software by adapting programs for the development of power engineering in the system of the European model of Industry 4.0. As a fundamental position addresses the need for such a project, which would ensure the greatest impact with limited resources, including public funding, which lags far behind foreign. It is proposed to transform the efforts to implement the existing strategies of industry development in view of the policy of import substitution based on the implementation of the program of production of a balanced range of innovative products and providing replacement of imported equipment and the formation of the technological basis for the development of the industry

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

Program of RA reactor start-up to nominal power; Program dizanja reaktora 'RA' na nominalnu snagu

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-07-01

The zero start-up program is followed by the program of RA reactor start-up to nominal power. This program is desed in detail and includes the following measurements: radiation characteristics at the exit of the channels; gamma and fast neutron dose distribution in the reactor; influence of absorbers on the reactivity; temperature effect; absolute flux and calibration of ionization chambers; xenon effect; thermal and hydraulics; dosimetry around the reactor; neutron flux in the reactor core and in the reactor hall; heavy water level; thermal characteristics after shutdown. A list of measuring devices and instrumentation is included with the detailed action plan and list of responsible staff members.

Long Term Analysis of Adaptive Low-Power Instrument Platform Power and Battery Performance

Science.gov (United States)

Edwards, T.; Bowman, J. R.; Clauer, C. R.

2017-12-01

Operation of the Autonomous Adaptive Low-Power Instrument Platform (AAL-PIP) by the Magnetosphere-Ionosphere Science Team (MIST) at Virginia Tech has been ongoing for about 10 years. These instrument platforms are deployed on the East Antarctic Plateau in remote locations that are difficult to access regularly. The systems have been designed to operate unattended for at least 5 years. During the Austral summer, the systems charge batteries using solar panels and power is provided by the batteries during the winter months. If the voltage goes below a critical level, the systems go into hibernation and wait for voltage from the solar panels to initiate a restart sequence to begin operation and battery charging. Our first system was deployed on the East Antarctic Plateau in 2008 and we report here on an analysis of the power and battery performance over multiple years and provide an estimate for how long these systems can operate before major battery maintenance must be performed.

Power program and nuclear power

International Nuclear Information System (INIS)

Chernilin, Yu.F.

1990-01-01

Main points of the USSR power program and the role of nuclear power in fuel and power complex of the country are considered. Data on dynamics of economic indices of electric power generation at nuclear power plants during 1980-1988 and forecasts till 2000 are presented. It is shown that real cost of 1 kW/h of electric power is equal to 1.3-1.8 cop., and total reduced cost is equal to 1.8-2.4 cop

Nuclear Power Infrastructure Development Program: Korean Education Program

International Nuclear Information System (INIS)

Choi, Sung Yeol; Hwang, Il Soon; Kim, Si Hwan

2009-01-01

Many countries have decided nuclear power for next energy resources as one of the long-term energy supply options. IAEA projected nuclear power expansion up to 2030 reaching between 447 GWe and 691 GWe compared to 370 GWe and 2660 TWh at the end of 2006. Both low and high projection is accompanied with new nuclear power plant constructions respectively 178 and 357, about 11 units per year, and most new construction is in North America, the Far East, Eastern Europe, the Middle East, and Southeast Asia. During the last forty years, thirty three countries have established commercial nuclear power programs but only some of them have developed comprehensive and large scale peaceful nuclear power infrastructure. Although various cooperation and guidance program of nuclear power infrastructure, developing appropriate environment and infrastructure of nuclear power plant is still challenging problems for developing countries launching nuclear power program. With increasing the demand of safety and safeguard from international society, creating appropriate infrastructure becomes essential requirements in national nuclear power program. In the viewpoint of developing countries, without sufficient explanation and proper guidance, infrastructure could be seen only as another barrier in its nuclear power program. The importance of infrastructure development would be obscured by ostensible business and infrastructure program can result in increasing entering barriers to peaceful nuclear power application field without benefits to developing countries and international community. To avoid this situation by providing enough explanation and realistic case example and cooperate with the countries wanting to establish comprehensive nuclear power infrastructure in the peaceful applications, we are creating the education program of infrastructure development with basic guidelines of the IAEA infrastructure series and Korean experiences from least developed country to advanced country

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)

Policy instruments for development of wind power in Sweden

International Nuclear Information System (INIS)

Aastrand, Kerstin; Neij, Lena

2003-01-01

It is often believed that energy policy and policy instruments can play a significant role in the transition towards sustainable energy by stimulating and accelerating the development and deployment of new energy technologies. However, despite the known need for, and benefits of, new energy technologies their market introduction and expansion is often slow. Wind power has been on the political agenda since the 1970s in several European countries as well as in other countries throughout the world. However, the technology and market development of wind power has been very different in these countries. Despite three decades of policy intervention the installed capacity in Sweden was only 265 MW in 2000, compared with 6,107 MW in Germany, 2,836 MW in Spain and 2,341 MW in Denmark. This report analyses the effects of policy instruments on wind power development in Sweden and identifies possible reasons why wind power has not been installed to a greater extent. The analysis is based on an empirical example of a socio technological system-based approach to evaluation of technology and market development for new energy technologies; i.e. an approach focused on the technological system including the actors, institutions and organizations that build, drive and utilise it and the economic and legal framework that regulates it. The aim is to assess the impact on technology and market development and to discuss the relatively late and slow wind power development in Sweden. The report also examines the achievement of governmental energy policy goals. Using the socio-technological systems approach we analyse Swedish policy programmes and wind power development between 1975 and 2000. The political and economic framework is identified. The discussion of the political and economic frameworks is limited to public policy goals and policy instruments. The policy focus is set to policy instruments aimed for technology and market development of wind power, such as research and

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

The evaluation of equipment and Instrumentation Reliability Factors on Power Reactor

International Nuclear Information System (INIS)

Supriatna, Piping; Karlina, Itjeu; Widagdo, Suharyo; Santosa, Kussigit; Darlis; Sudiyono, Bambang; Yuniyanta, Sasongko; Sudarmin

1999-01-01

Equipment and instrumentation reliability on type power reactor control room was determined by its pattern and design. the principle of ergonomy applied on equipment and instrumentation layout in this ABWR type reactor are geometric pattern appropriate with economic body motion, average anthropometry data of operator especially operator hand-reach, range of vision, angle of vision, lighting, color arrangement and harmony as will as operator case in operating the equipment system. Limitation criteria of the parameter mentioned above are based on EPRI NP-3659, NURG 0700, and NUREG/CR-3331 documents. Besides that, the (working) physical environment parameter factor of the control room must be designed in order to fulfil the standard criteria of ergonomic condition based on NUREG-0800. The reliability evaluation of equipment and instrumentation system also occurs observed from man machine interaction side which happen between operator and equipment and instrumentation in the ABWR type power reactor control room. From the MMI analysis can be known the working failure possibility which is caused by the operator. The evaluation result of equipment and instrumentation reliability on ABWR type power reactor control room showed that the design of this ABWR control room is good and fulfils the ergonomy standard criteria have been determined

Nuclear reactor instrumentation power monitor

International Nuclear Information System (INIS)

Suzuki, Shigeru.

1989-01-01

The present invention concerns a nuclear reactor instrumentation power monitor that can be used in, for example, BWR type nuclear power plants. Signals from multi-channel detectors disposed on field units are converted respectively by LPRM signal circuits. Then, the converted signals are further converted by a multiplexer into digital signals and transmitted as serial data to a central monitor unit. The thus transmitted serial data are converted into parallel data in the signal processing section of the central monitor unit. Then, LPRM signals are taken out from each of channel detectors to conduct mathematical processing such as trip judgment or averaging. Accordingly, the field unit and the central monitor unit can be connected by way of only one data transmission cable thereby enabling to reduce the number of cables. Further, since the data are transmitted on digital form, it less undergoes effect of noises. (I.S.)

Modernizing and Maintaining Instrumentation and Control Systems in Nuclear Power Plants

International Nuclear Information System (INIS)

Naser, Joseph; Torok, Raymond; Shankar, Ramesh

2003-01-01

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

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

International Nuclear Information System (INIS)

2005-07-01

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

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

Instrumentation Cables Test Plan

Energy Technology Data Exchange (ETDEWEB)

Muna, Alice Baca [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaFleur, Chris Bensdotter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-10-01

A fire at a nuclear power plant (NPP) has the potential to damage structures, systems, and components important to safety, if not promptly detected and suppressed. At Browns Ferry Nuclear Power Plant on March 22, 1975, a fire in the reactor building damaged electrical power and control systems. Damage to instrumentation cables impeded the function of both normal and standby reactor coolant systems, and degraded the operators’ plant monitoring capability. This event resulted in additional NRC involvement with utilities to ensure that NPPs are properly protected from fire as intended by the NRC principle design criteria (i.e., general design criteria 3, Fire Protection). Current guidance and methods for both deterministic and performance based approaches typically make conservative (bounding) assumptions regarding the fire-induced failure modes of instrumentation cables and those failure modes effects on component and system response. Numerous fire testing programs have been conducted in the past to evaluate the failure modes and effects of electrical cables exposed to severe thermal conditions. However, that testing has primarily focused on control circuits with only a limited number of tests performed on instrumentation circuits. In 2001, the Nuclear Energy Institute (NEI) and the Electric Power Research Institute (EPRI) conducted a series of cable fire tests designed to address specific aspects of the cable failure and circuit fault issues of concern1. The NRC was invited to observe and participate in that program. The NRC sponsored Sandia National Laboratories to support this participation, whom among other things, added a 4-20 mA instrumentation circuit and instrumentation cabling to six of the tests. Although limited, one insight drawn from those instrumentation circuits tests was that the failure characteristics appeared to depend on the cable insulation material. The results showed that for thermoset insulated cables, the instrument reading tended to drift

Programming for a nuclear reactor instrument simulation

International Nuclear Information System (INIS)

Cohn, C.

1988-01-01

This note discusses 8086/8087 machine-language programming for simulation of nuclear reactor instrument current inputs by means of a digital-analog converter (DAC) feeding a bank of series input resistors. It also shows FORTRAN programming for generating the parameter tales used in the simulation. These techniques would be generally useful for high-speed simulation of quantities varying over many orders of magnitude

Counselor Competence, Performance Assessment, and Program Evaluation: Using Psychometric Instruments

Science.gov (United States)

Tate, Kevin A.; Bloom, Margaret L.; Tassara, Marcel H.; Caperton, William

2014-01-01

Psychometric instruments have been underutilized by counselor educators in performance assessment and program evaluation efforts. As such, we conducted a review of the literature that revealed 41 instruments fit for such efforts. We described and critiqued these instruments along four dimensions--"Target Domain," "Format,"…

Safeguarding on-power fuelled reactors - instrumentation and techniques

International Nuclear Information System (INIS)

Waligura, A.; Konnov, Y.; Smith, R.M.; Head, D.A.

1977-05-01

Instrumentation and techniques applicable to safeguarding reactors that are fuelled on-power, particularly the CANDU type, have been developed. A demonstration is being carried out at the Douglas Point Nuclear Generating Station in Canada. Irradiated nuclear materials in certain areas - the reactor and spent fuel storage bays - are monitored using photographic and television cameras, and seals. Item accounting is applied by counting spent-fuel bundles during transfer from the reactor to the storage bay and by placing these spent-fuel bundles in a sealed enclosure. Provision is made for inspection and verification of the bundles before sealing. The reactor's power history is recorded by a Track-Etch power monitor. Redundancy is provided so that the failure of any single piece of equipment does not invalidate the entire safeguards system. Several safeguards instruments and devices have been developed and evaluated. These include a super-8-mm surveillance camera system, a television surveillance system, a spent-fuel bundle counter, a device to detect dummy fuel bundles, a cover for enclosing a stack of spent-fuel bundles, and a seal suitable for underwater installation and ultrasonic interrogation. (author)

Policy instruments for offshore wind power; Styrmedel foer havsbaserad vindkraft

Energy Technology Data Exchange (ETDEWEB)

Soederholm, Patrik (Luleaa Technical Univ., Luleaa (Sweden))

2009-10-15

The future economic potential for offshore wind power is considered to be very good, and there is a strong interest in European wind power industry to improve the technology and generate additional experience. To enable such technology and a market introduction of offshore wind power it is believed that a supplementary or an alternative support for the offshore wind energy is required. This report aims to analyze conditions of different financial instruments to effectively support the rollout of offshore wind power in Sweden. Our mandate does not include an analysis whether any funding is economically justified or not, but a discussion about the objectives of such instruments is necessary for the second stage in order to discuss the instrument characteristics and design. The report takes up a number of different arguments in order to target a specific support for any single technology. An important message from this part of the analysis is that the strongest argument that can be used to extend a special generous support for offshore wind power is that its socio-economic costs may be lower, in the long run, than those which currently apply to established power production lines (e.g. on-shore wind). Any funding should be considered primarily as a means of political action, i.e. a measure not to meet today's short-term goals (eg quota requirement of certificate system) but to cut costs in order to reach the future (long term) goals. The offshore wind energy can be a very interesting candidate for such support, not least because of the favorable wind conditions that exist at sea. For these cost reductions to be realized, it is important to establish niche markets for the turbines and construction work that will be necessary. Such a technology policy presupposes a real development and not solely R and D and D projects. The report presents the results of previous research that supports this assumption, but it makes no attempt to assess whether the relevant effects

Highly Reliable Power and Communication System for Essential Instruments under a Severe Accident of NPPs

Energy Technology Data Exchange (ETDEWEB)

Yoo, S. J.; Choi, B. H.; Jung, S. Y.; Rim, Chun T. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2013-10-15

In this paper, three survivable strategies to overcome the problems listed above are proposed for the essential instruments under the severe accident of NPPs. First, wire/wireless multi power systems are adopted to the essential instruments for continuous power supply. Second, wire/wireless communication systems are proposed for reliable transmission of measuring information among instruments and operators. Third, a physical protection system such as a harness and a heat isolation box is introduced to ensure operable conditions for the proposed systems. In this paper, a highly reliable strategy, which consists of wire/wireless multi power and communication systems and physical protection system is proposed to ensure the survival of the essential instruments under harsh external conditions. The wire/wireless multi power and communication systems are designed to transfer power and data in spite of the failure of conventional wired systems. The physical protection system provides operable environments to the instruments. Therefore, the proposed system can be considered as a candidate of practical and urgent remedy for NPPs under the severe accident. After the Fukushima nuclear accident, survivability of essential instruments has been emphasized for immediate and accurate response. The essential instruments can measure environment conditions such as temperature, pressure, radioactivity and corium behavior inside nuclear power plants (NPPs) under a severe accident. Access to the inside of NPPs is restricted to human beings because of hazardous environment such as high radioactivity, high temperature and high pressure. Thus, monitoring the inside of NPPs is necessary for avoiding damage from the severe accident. Even though there were a number of instruments in Fukushima Daiichi NPP, they failed to obtain exact monitoring information. According to the details of the Fukushima nuclear accident, following problems can be counted as strong candidates of this instruments

Highly Reliable Power and Communication System for Essential Instruments under a Severe Accident of NPPs

International Nuclear Information System (INIS)

Yoo, S. J.; Choi, B. H.; Jung, S. Y.; Rim, Chun T.

2013-01-01

In this paper, three survivable strategies to overcome the problems listed above are proposed for the essential instruments under the severe accident of NPPs. First, wire/wireless multi power systems are adopted to the essential instruments for continuous power supply. Second, wire/wireless communication systems are proposed for reliable transmission of measuring information among instruments and operators. Third, a physical protection system such as a harness and a heat isolation box is introduced to ensure operable conditions for the proposed systems. In this paper, a highly reliable strategy, which consists of wire/wireless multi power and communication systems and physical protection system is proposed to ensure the survival of the essential instruments under harsh external conditions. The wire/wireless multi power and communication systems are designed to transfer power and data in spite of the failure of conventional wired systems. The physical protection system provides operable environments to the instruments. Therefore, the proposed system can be considered as a candidate of practical and urgent remedy for NPPs under the severe accident. After the Fukushima nuclear accident, survivability of essential instruments has been emphasized for immediate and accurate response. The essential instruments can measure environment conditions such as temperature, pressure, radioactivity and corium behavior inside nuclear power plants (NPPs) under a severe accident. Access to the inside of NPPs is restricted to human beings because of hazardous environment such as high radioactivity, high temperature and high pressure. Thus, monitoring the inside of NPPs is necessary for avoiding damage from the severe accident. Even though there were a number of instruments in Fukushima Daiichi NPP, they failed to obtain exact monitoring information. According to the details of the Fukushima nuclear accident, following problems can be counted as strong candidates of this instruments

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

Power MOSFET Linearizer of a High-Voltage Power Amplifier for High-Frequency Pulse-Echo Instrumentation.

Science.gov (United States)

Choi, Hojong; Woo, Park Chul; Yeom, Jung-Yeol; Yoon, Changhan

2017-04-04

A power MOSFET linearizer is proposed for a high-voltage power amplifier (HVPA) used in high-frequency pulse-echo instrumentation. The power MOSFET linearizer is composed of a DC bias-controlled series power MOSFET shunt with parallel inductors and capacitors. The proposed scheme is designed to improve the gain deviation characteristics of the HVPA at higher input powers. By controlling the MOSFET bias voltage in the linearizer, the gain reduction into the HVPA was compensated, thereby reducing the echo harmonic distortion components generated by the ultrasonic transducers. In order to verify the performance improvement of the HVPA implementing the power MOSFET linearizer, we measured and found that the gain deviation of the power MOSFET linearizer integrated with HVPA under 10 V DC bias voltage was reduced (-1.8 and -0.96 dB, respectively) compared to that of the HVPA without the power MOSFET linearizer (-2.95 and -3.0 dB, respectively) when 70 and 80 MHz, three-cycle, and 26 dB m input pulse waveforms are applied, respectively. The input 1-dB compression point (an index of linearity) of the HVPA with power MOSFET linearizer (24.17 and 26.19 dB m at 70 and 80 MHz, respectively) at 10 V DC bias voltage was increased compared to that of HVPA without the power MOSFET linearizer (22.03 and 22.13 dB m at 70 and 80 MHz, respectively). To further verify the reduction of the echo harmonic distortion components generated by the ultrasonic transducers, the pulse-echo responses in the pulse-echo instrumentation were compared when using HVPA with and without the power MOSFET linearizer. When three-cycle 26 dB m input power was applied, the second, third, fourth, and fifth harmonic distortion components of a 75 MHz transducer driven by the HVPA with power MOSFET linearizer (-48.34, -44.21, -48.34, and -46.56 dB, respectively) were lower than that of the HVPA without the power MOSFET linearizer (-45.61, -41.57, -45.01, and -45.51 dB, respectively). When five-cycle 20 dB m input

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)

Wind power in Argentina: Policy instruments and economic feasibility

International Nuclear Information System (INIS)

Recalde, M.

2010-01-01

Despite its great wind endowment, Argentina has not still succeeded in increasing wind power share in its wholesale market. However, the energy supply problem that this country is facing from 2004 on seems to open an opportunity for wind energy projects. A wide range of legislation has recently emerged. In this context, this paper discusses whether policy instruments in the Argentinean regulatory frame contribute to economic feasibility for wind power projects or not. To this purpose, we study wind installed capacity, Argentinean wind potential, the different promotion tools used worldwide and those employed in Argentina. Finally, we realize a feasibility study for a typical project. We found, that in spite of its high wind potential, economic feature, related to policy instruments, have been a boundary to the development of wind energy into the energy mix. (author)

Using a graphical programming language to write CAMAC/GPIB instrument drivers

Science.gov (United States)

Zambrana, Horacio; Johanson, William

1991-01-01

To reduce the complexities of conventional programming, graphical software was used in the development of instrumentation drivers. The graphical software provides a standard set of tools (graphical subroutines) which are sufficient to program the most sophisticated CAMAC/GPIB drivers. These tools were used and instrumentation drivers were successfully developed for operating CAMAC/GPIB hardware from two different manufacturers: LeCroy and DSP. The use of these tools is presented for programming a LeCroy A/D Waveform Analyzer.

An Evaluation Instrument for Object-Oriented Example Programs for Novices

DEFF Research Database (Denmark)

Christensen, Henrik Bærbak; Börstler, Jürgen; Nordström,, Marie

objectively and consistently requires some kind of measurement instrument. In this paper, we describe the development and initial validation of an evaluation instrument for example programs, based on three aspects of quality; technical quality, object-oriented quality, and didactical quality. Validation......Examples are important tools for programming education. In this paper, we investigate desirable properties of programming examples from a cognitive and a measurement point of view. We argue that some cognitive aspects of example programs are "caught" by common software measures......, but they are not sufficient to capture all important aspects of understandability. We propose a framework for measuring the understandability of example programs that also considers factors related to the usage context of examples. Research shows that examples play an important role for cognitive skill acquisition. Students...

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.

Instrumentation for chemical and radiochemical monitoring in nuclear power plants

International Nuclear Information System (INIS)

Nordmann, F.; Ballard, G.

2009-01-01

This article details the instrumentation implemented in French nuclear power plants for the monitoring of chemical and radiochemical effluents with the aim of limiting their environmental impact. It describes the controls performed with chemical automata for the search for drifts, anomalies or pollution in a given circuit. The operation principles of the different types of chemical automata are explained as well as the manual controls performed on samples manually collected. Content: 1 - general considerations; 2 - objectives of the chemical monitoring: usefulness of continuous monitoring with automata, transmission to control rooms and related actions, redundancy of automata; 3 - instrumentation and explanations for the main circuits: principle of chemical automata monitoring, instrumentation of the main primary circuit, instrumentation of the main secondary circuit, instrumentation of the tertiary circuit, preparation of water makeup (demineralized water), other loops, instrumentation for effluents and environment monitoring, measurement principles of chemical automata, control and maintenance of chemical automata; 4 - manual controls after sampling; 5 - radiochemical monitoring: automatized radiochemical measurements, manual radiochemical measurements; 6 - conclusion

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

The Korean nuclear power program

International Nuclear Information System (INIS)

Choi, Chang Tong

1996-01-01

Although the world nuclear power industry may appear to be in decline, continued nuclear power demand in Korea indicates future opportunities for growth and prosperity in this country. Korea has one of the world's most vigorous nuclear power programs. Korea has been an active promoter of nuclear power generation since 1978, when the country introduced nuclear power as a source of electricity. Korea now takes pride in the outstanding performance of its nuclear power plants, and has established a grand nuclear power scheme. This paper is aimed at introducing the nuclear power program of Korea, including technological development, international cooperation, and CANDU status in Korea. (author). 2 tabs

Green power programs in Canada : 2002 : Overview of Government green power policies, utility green power development programs, green power and certificate marketing initiatives, and their benefits

International Nuclear Information System (INIS)

Bramley, M.; Boustie, S.; Vadgama, J.; Wieler, C.; Pape-Salmon, A.; Holmes, R.

2003-11-01

Green power is generally defined as electricity produced from renewable sources, and whose production has low adverse impacts on the environment, human health and communities. Green power has near-zero greenhouse gas (GHG) emissions and includes sources such as wind, hydro, and solar power. Green power offers several environmental benefits, as well as the enhancement of energy security, regional development, economic diversification and the creation of skilled jobs. There are four categories of programs related to green power development in Canada: government green power policies, utility green power development programs, green power marketing initiatives, and green power certificate marketing initiatives. Most of the activities associated with these four categories in 2002 were discussed in this report. However, difficulties with quantification prevented the inclusion of some green power activities in the report, such as (1) the generation of green power not certified or identified by the generator as green power, (2) industry or residential self-generation, (3) net metering, and (4) small government programs. Each category was presented in detail. The information included in the report was based on surveys sent to each program proponent. Follow-up communications and other publicly available information was also included. New programs operating in 2003 or currently under development were listed. refs., 8 tabs

Cloud Instrument Powered by Solar Cell Sends Data to Pachube

Directory of Open Access Journals (Sweden)

Doru Ursutiu

2010-11-01

Full Text Available Despite the economic downturn, there have been quite a few new developments in the world of remote measurements lately. Tag4M (www.tag4m.com introduced the concept of cloud instrument where sensors connected to WiFi tags send data to off-the-shelf Access Points which are part of the WiFi infrastructure that exists in enterprises, retail outlets, factories, and warehouses. Access Points route the data to the Internet where specialized web applications receive the information for processing and display. One of these specialized web applications is Pachube, (http://www.pachube.com which bills itself as a “real-time data brokerage platform”. Pachube enables people to tag and share real time sensor data from objects, devices and spaces around the world. This article presents the pachube cloud instrument where sensors connected to Tag4M WiFi tags send digitized data to www.pachube.com for public display. The article contains very detailed analysis of the solar cell power source that is used to continuously power the Tag4M tag during this application. Cloud Instruments powered by solar cells enable people around the world to share real time sensor data using web pages on the Internet. This is a very interesting and exciting technology development that we want to bring to your attention.

Virginia power nuclear power station engineer training program

International Nuclear Information System (INIS)

Williams, T.M.; Haberstroh-Timpano, S.

1987-01-01

In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

Soil–structure interaction analyses to locate nuclear power plant free-field seismic instrumentation

Energy Technology Data Exchange (ETDEWEB)

Johnson, James J., E-mail: jasjjoh@aol.com [James J. Johnson and Associates, Alamo, CA (United States); Ake, Jon P. [US Nuclear Regulatory Commission, Washington, DC (United States); Maslenikov, Oleg R. [James J. Johnson and Associates, Alamo, CA (United States); Kenneally, Roger M. [Consultant, Seminole, FL (United States)

2015-12-15

Highlights: • Determine the location of seismic instrumentation so that recorded motion will be free-field motion. • Certified Designs of nuclear island for AP1000 and EPR; ABWR Reactor Building were analyzed. • Three site conditions and multiple recorded time histories were considered. • Instrumentation located 1-diameter from the edge of structure/foundation is adequate. • Acceptance criteria were probability of non-exceedance of response spectra values. - Abstract: The recorded earthquake ground motion at the nuclear power plant site is needed for several purposes. US Nuclear Regulatory Commission (NRC) Regulatory Guide 1.12, Nuclear Power Plant Instrumentation for Earthquakes, NRC (1997a), describes acceptable instrumentation to meet the requirements in NRC's regulations pertaining to earthquake engineering criteria for nuclear power plants. The ground motion data recorded by the free-field seismic instrumentation are used to compare the actual earthquake motion at the site with the design input motion. The result of the comparison determines if the Operating Basis Earthquake ground motion (OBE) has been exceeded and plant shutdown is required per the guidance in NRC Regulatory Guide 1.166, Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions, NRC (1979b). The free-field is defined as a location on the ground surface or in the site soil column that is sufficiently distant from the site structures to be essentially unaffected by the vibration of the site structures.

Increased Science Instrumentation Funding Strengthens Mars Program

Science.gov (United States)

Graham, Lee D.; Graff, T. G.

2012-01-01

As the strategic knowledge gaps mature for the exploration of Mars, Mars sample return (MSR), and Phobos/Deimos missions, one approach that becomes more probable involves smaller science instrumentation and integrated science suites. Recent technological advances provide the foundation for a significant evolution of instrumentation; however, the funding support is currently too small to fully utilize these advances. We propose that an increase in funding for instrumentation development occur in the near-term so that these foundational technologies can be applied. These instruments would directly address the significant knowledge gaps for humans to Mars orbit, humans to the Martian surface, and humans to Phobos/ Deimos. They would also address the topics covered by the Decadal Survey and the Mars scientific goals, objectives, investigations and priorities as stated by the MEPAG. We argue that an increase of science instrumentation funding would be of great benefit to the Mars program as well as the potential for human exploration of the Mars system. If the total non-Earth-related planetary science instrumentation budget were increased 100% it would not add an appreciable amount to the overall NASA budget and would provide the real potential for future breakthroughs. If such an approach were implemented in the near-term, NASA would benefit greatly in terms of science knowledge of the Mars, Phobos/Deimos system, exploration risk mitigation, technology development, and public interest.

The Assessment of Expressive and Instrumental Power Value Orientations in Sport and in Everyday Life.

Science.gov (United States)

Bredemeier, B. J.

A typical assumption has been that women and men possess distinct power orientations: women have expressive characteristics, such as interdependence and cooperativeness, while men have instrumental characteristics, such as self reliance and competitiveness. An inventory assessing expressive and instrumental power orientations (PVO's) was developed…

Virginia Power's capacity acquisition program

International Nuclear Information System (INIS)

Carney, R.W.

1991-01-01

Virginia Power is a utility with a growing demand for electricity. To meet that growth it has embarked on an aggressive program to encourage the construction of privately-owned generating plants. In 1988 it conducted the largest competitive acquisition program by any utility to date. Virginia Power has retained the option to build plants if the bids it receives are too costly or do not meet the needs of its customers. This paper describes the situation at Virginia Power, the program it has implemented, and the capacity additions which are scheduled between 1989 and 1995

Instrumentation development for the Waste Isolation Pilot Plant (WIPP) borehole plugging program (BHP)

International Nuclear Information System (INIS)

Cook, C.W.

1979-11-01

This report discusses the instrumentation development needs of the borehole testing program as it now exists. Although requirements may change as the program progresses, the items indicated are basic to any borehole plugging program. Instrumentation is discussed both for the plug environment and for the plug itself. For the plug environment, a probe for measuring the disturbed region and a coordinate logging tool are required. For the plug itself, instrumentation includes measurements above, within, and below the plug. Instrumentation for most measurements above the plug is currently available; for measurements within and below the plug, however, further development is required. Specifically, resistivity, induction, and acoustic probes; an in situ stressmeter; and a hardwire, feedthrough system need to be developed

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)

Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power

International Nuclear Information System (INIS)

Hoth, C.W.

1981-01-01

Two full size highly instrumented fuel assemblies were inserted into the core of the Fast Flux Test Facility in December of 1979. The major objectives of these instrumented tests are to provide verification of the FFTF core conditions and to characterize temperature patterns within FFTF driver fuel assemblies. A review is presented of the results obtained during the power ascents and during irradiation at a constant reactor power of 400 MWt. The results obtained from these instrumented tests verify the conservative nature of the design methods used to establish core conditions in FFTF. The success of these tests also demonstrates the ability to design, fabricate, install and irradiate complex, instrumented fuel tests in FFTF using commercially procured components

Recent applications of microprocessor-based instruments in nuclear power stations

International Nuclear Information System (INIS)

Cash, N.R.; Dennis, U.E.

1988-01-01

The incorporation of microprocessors in the design of nuclear power plant instrumentation has led to levels of measurement and control not available previously. In addition to the expected expansion of functional (system) capability, numerous desirable features now are possible. The added ability to both self-calibrate and perform compensation algorithms has led to dramatic improvements in accuracies, response times, and noise rejection. Automated performance checking and self-testing simplify troubleshooting and required periodic surveillance. Alphanumeric displays allow both menu-driven operation and user-prompting, which, in turn, contribute to mistake avoidance. New features of these microprocessor-based instruments are of specific benefit in nuclear power reactors, were safety is of prime concern. Greater reliability and accuracy can be provided. Shortened calibration, surveillance, and repair times reduce the exposure to unnecessary challenges of the plant's protection systems that can arise from spurious noise signals

Evaluation of a Kalman filter based power pressurizer instrument failure detection system implemented on a nuclear power plant training simulator

International Nuclear Information System (INIS)

Seegmiller, D.S.

1984-01-01

The usefulness of a nuclear power plant training simulator for developing and testing modern estimation and control applications for nuclear power plants is demonstrated. A Kalman filter based instrument failure detection technique for a pressurized water reactor pressurizer is implemented on the Department of Energy N Reactor Training Simulator. This real-time failure detection method computes the first two moments (mean and variance) of each element of a normalized filter innovations vector. Failed pressurizer instrumentation can be detected by comparing these moments to the known statistical properties of the steady state, linear Kalman fitler innovations sequence. The capabilities of the detection system are evaluated using simulated plant transients and instrument failures

IAEA integrated safeguards instrumentation program (I2SIP)

International Nuclear Information System (INIS)

Arlt, R.; Fortakov, V.; Gaertner, K.J.

1995-01-01

This article is a review of the IAEA integrated safeguards instrumentation program. The historical development of the program is outlined, and current activities are also noted. Brief technical descriptions of certain features are given. It is concluded that the results of this year's efforts in this area will provide significant input and be used to assess the viability of the proposed concepts and to decide on the directions to pursue in the future

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)

Creation of an instrument maintenance program at W. M. Keck Observatory

Science.gov (United States)

Hill, G. M.; Kwok, S. H.; Mader, J. A.; Wirth, G. D.; Dahm, S. E.; Goodrich, R. W.

2014-08-01

Until a few years ago, the W. M. Keck Observatory (WMKO) did not have a systematic program of instrument maintenance at a level appropriate for a world-leading observatory. We describe the creation of such a program within the context of WMKO's lean operations model which posed challenges but also guided the design of the system and resulted in some unique and notable capabilities. These capabilities and the flexibility of the system have led to its adoption across the Observatory for virtually all PM's. The success of the Observatory in implementing the program and its impact on instrument reliability are presented. Lessons learned are reviewed and strategic implications discussed.

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

The NASA CSTI High Capacity Power Program

International Nuclear Information System (INIS)

Winter, J.M.

1991-09-01

The SP-100 program was established in 1983 by DOD, DOE, and NASA as a joint program to develop the technology necessary for space nuclear power systems for military and civil applications. During 1986 and 1987, the NASA Advanced Technology Program was responsible for maintaining the momentum of promising technology advancement efforts started during Phase 1 of SP-100 and to strengthen, in key areas, the chances for successful development and growth capability of space nuclear reactor power systems for future space applications. In 1988, the NASA Advanced Technology Program was incorporated into NASA's new Civil Space Technology Initiative (CSTI). The CSTI program was established to provide the foundation for technology development in automation and robotics, information, propulsion, and power. The CSTI High Capacity Power Program builds on the technology efforts of the SP-100 program, incorporates the previous NASA advanced technology project, and provides a bridge to the NASA exploration technology programs. The elements of CSTI high capacity power development include conversion systems: Stirling and thermoelectric, thermal management, power management, system diagnostics, and environmental interactions. Technology advancement in all areas, including materials, is required to provide the growth capability, high reliability, and 7 to 10 year lifetime demanded for future space nuclear power systems. The overall program will develop and demonstrate the technology base required to provide a wide range of modular power systems while minimizing the impact of day/night operations as well as attitudes and distance from the Sun. Significant accomplishments in all of the program elements will be discussed, along with revised goals and project timelines recently developed

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.)

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.

Instrument validation system of general application

International Nuclear Information System (INIS)

Filshtein, E.L.

1990-01-01

This paper describes the Instrument Validation System (IVS) as a software system which has the capability of evaluating the performance of a set of functionally related instrument channels to identify failed instruments and to quantify instrument drift. Under funding from Combustion Engineering (C-E), the IVS has been developed to the extent that a computer program exists whose use has been demonstrated. The initial development work shows promise for success and for wide application, not only to power plants, but also to industrial manufacturing and process control. Applications in the aerospace and military sector are also likely

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)

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

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)

QA programs in nuclear power plants

International Nuclear Information System (INIS)

Ellingson, A.C.

1976-01-01

As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

Job analysis of the instrument and control technician position for the nuclear power plant maintenance personnel reliability model

International Nuclear Information System (INIS)

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

1983-08-01

This report is one of a series that is planned to describe the results of a program undertaken by the Oak Ridge National Laboratory (ORNL) for the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, to define, develop, validate, and disseminate a methodology for the quantitative prediction of human reliability in the conduct of maintenance tasks in nuclear power plants (NPPs). ORNL has subcontracted portions of this effort to Applied Psychological Services, Inc. This report on the job analysis of the Instrument and Control technician (NUREG/CR-3274) and a report on the job analysis of the electrician position (NUREG/CR-3275) comprise a part of the initial efforts of the development phase of this program. With the publication of the job analysis of the electrician position, the series of job analyses reports addressing nuclear power plant maintenance personnel will be complete. Subsequent reports addressing model development and validation are planned

Sensitivity analysis and power for instrumental variable studies.

Science.gov (United States)

Wang, Xuran; Jiang, Yang; Zhang, Nancy R; Small, Dylan S

2018-03-31

In observational studies to estimate treatment effects, unmeasured confounding is often a concern. The instrumental variable (IV) method can control for unmeasured confounding when there is a valid IV. To be a valid IV, a variable needs to be independent of unmeasured confounders and only affect the outcome through affecting the treatment. When applying the IV method, there is often concern that a putative IV is invalid to some degree. We present an approach to sensitivity analysis for the IV method which examines the sensitivity of inferences to violations of IV validity. Specifically, we consider sensitivity when the magnitude of association between the putative IV and the unmeasured confounders and the direct effect of the IV on the outcome are limited in magnitude by a sensitivity parameter. Our approach is based on extending the Anderson-Rubin test and is valid regardless of the strength of the instrument. A power formula for this sensitivity analysis is presented. We illustrate its usage via examples about Mendelian randomization studies and its implications via a comparison of using rare versus common genetic variants as instruments. © 2018, The International Biometric Society.

On-line calibration of process instrumentation channels in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hashemian, H.M.; Farmer, J.P. [Analysis and Measurement Services Corp., Knoxville, TN (United States)

1995-04-01

An on-line instrumentation monitoring system was developed and validated for use in nuclear power plants. This system continuously monitors the calibration status of instrument channels and determines whether or not they require manual calibrations. This is accomplished by comparing the output of each instrument channel to an estimate of the process it is monitoring. If the deviation of the instrument channel from the process estimate is greater than an allowable limit, then the instrument is said to be {open_quotes}out of calibration{close_quotes} and manual adjustments are made to correct the calibration. The success of the on-line monitoring system depends on the accuracy of the process estimation. The system described in this paper incorporates both simple intercomparison techniques as well as analytical approaches in the form of data-driven empirical modeling to estimate the process. On-line testing of the calibration of process instrumentation channels will reduce the number of manual calibrations currently performed, thereby reducing both costs to utilities and radiation exposure to plant personnel.

Development of BC based nuclear instrument

International Nuclear Information System (INIS)

Nolida Yussup; Atsushi Birumachi; Kazuaki Shimizu

2005-01-01

This paper describes the development of a low-power portable dose rate meter with RS232 interface for data acquisition during 6 months course under MEXT Nuclear Researchers Exchange Program 2004 at JAERI, Japan. The development involved defining the system, selection of detector and components, designing the pre-amplifier, main amplifier, noise discriminator and testing. Software programming was developed on PC to acquire the data via RS232 and display the real-time data. This will allow a small nuclear instrument to have powerful data processing and bigger data storage capability. (Author)

Statistical power as a function of Cronbach alpha of instrument questionnaire items.

Science.gov (United States)

Heo, Moonseong; Kim, Namhee; Faith, Myles S

2015-10-14

In countless number of clinical trials, measurements of outcomes rely on instrument questionnaire items which however often suffer measurement error problems which in turn affect statistical power of study designs. The Cronbach alpha or coefficient alpha, here denoted by C(α), can be used as a measure of internal consistency of parallel instrument items that are developed to measure a target unidimensional outcome construct. Scale score for the target construct is often represented by the sum of the item scores. However, power functions based on C(α) have been lacking for various study designs. We formulate a statistical model for parallel items to derive power functions as a function of C(α) under several study designs. To this end, we assume fixed true score variance assumption as opposed to usual fixed total variance assumption. That assumption is critical and practically relevant to show that smaller measurement errors are inversely associated with higher inter-item correlations, and thus that greater C(α) is associated with greater statistical power. We compare the derived theoretical statistical power with empirical power obtained through Monte Carlo simulations for the following comparisons: one-sample comparison of pre- and post-treatment mean differences, two-sample comparison of pre-post mean differences between groups, and two-sample comparison of mean differences between groups. It is shown that C(α) is the same as a test-retest correlation of the scale scores of parallel items, which enables testing significance of C(α). Closed-form power functions and samples size determination formulas are derived in terms of C(α), for all of the aforementioned comparisons. Power functions are shown to be an increasing function of C(α), regardless of comparison of interest. The derived power functions are well validated by simulation studies that show that the magnitudes of theoretical power are virtually identical to those of the empirical power. Regardless

Nuclear instrument maintenance - problems, solutions, and obstacles

International Nuclear Information System (INIS)

Vuister, P.H.

1983-01-01

In 200 laboratories of South-East Asia, Latin America and Africa a survey was made of the state of instrumentation for nuclear medicine. The principal cause of failures and defects was inadequate quality control and preventive maintenance. On the basis of the survey coordinated research programs were compiled for the maintenance of nuclear instruments. The four principal points of the programs are: to safeguard quality and stable electric power supplies for the instruments, to safeguard permanent temperature and humidity in the environment in which the equipment is operated, effective maintenance, and training of personnel. In the years 1981 and 1982, 14 local training courses were run in which emphasis was put on practicals and tests in mechanics and electronics

Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Haddam Neck Nuclear Power Plant

International Nuclear Information System (INIS)

Laudenbach, D.H.

1979-03-01

The technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Haddam Neck Nuclear Power Plant is presented. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory

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.

Impacts on power reactor health physics programs

International Nuclear Information System (INIS)

Meyer, B.A.

1991-01-01

The impacts on power reactor health physics programs form implementing the revised 10 CFR Part 20 will be extensive and costly. Every policy, program, procedure and training lesson plan involving health physics will require changes and the subsequent retraining of personnel. At each power reactor facility, hundreds of procedures and thousands of people will be affected by these changes. Every area of a power reactor health physics program will be affected. These areas include; ALARA, Respiratory Protection, Exposure Control, Job Coverage, Dosimetry, Radwaste, Effluent Accountability, Emergency Planning and Radiation Worker Training. This paper presents how power reactor facilities will go about making these changes and gives possible examples of some of these changes and their impact on each area of power reactor health physics program

76 FR 66284 - Wind and Water Power Program

Science.gov (United States)

2011-10-26

... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Wind and Water Power Program... projects. The 2011 Wind and Water Power Program, Water Power Peer Review Meeting will review the Program's... 2011 Water Power Peer Review Meeting will be held November 1 through November 3, 2011 in Alexandria, VA...

Design aid system for nuclear power plant instrumentations

International Nuclear Information System (INIS)

Hattori, Yoshiaki; Ito, Toshiichiro; Fujii, Makoto; Shimada, Nobuhide.

1987-01-01

Purpose: To enable to provide design aid for the nuclear power plant instrumentation of high reliability with the minimum cost while eliminating unrequired condition even if there are no data for the ground of the instrumentation design. Constitution: The information data base for the design of process radiation ray monitors are administrated by a data base administration device. The conditions to be satisfied in the process radiation monitors designed based on the data for the circumstances where particular predetermined process radiation monitors are installed, are derived by deduction using information obtained from the data base by way of the data base administration device. The derived design conditions are displayed and the optimum conditions are again reduced and displayed. In this way, the designers are assisted such that optimum designs can be obtained while sufficiently satisfying the safety and also in view of the cost. (Kamimura, M.)

The Nuclear Power Institute Programs for Human Resource Development for the Nuclear Industry

International Nuclear Information System (INIS)

Peddicord, K.L.

2014-01-01

Principal conclusions: 1. NPI is a full-scope, end-to-end, integrated approach to human resource development. Participation of government and government agencies, and elected officials and decision makers is vital. These key individuals and organizations encourage the effort, and provide support, a voice and advocacy for NPI and its programs. 2. Critical role of vocational training. The majority of the workforce does not involve only B.S. level engineers, but are graduates from two-year programs that are developed in collaboration with industry that prepare them for careers as technologists and technicians at a nuclear power plant. 3. In education and training, education is only part of the story. Collaboration with industry results in: – curricula, material, inputs and programs, – opportunities for students to benefit from industry mentors and get onsite experience, and – work on real-world, industry defined problems. 4. Outreach is instrumental in: –engaging with the next generation both for support of nuclear power and in building the workforce, and –generating vital contacts with the community to foster public understanding and acceptance of nuclear energy

Instrument failure monitoring in nuclear power systems

International Nuclear Information System (INIS)

Tylee, J.L.

1982-01-01

Methods of monitoring dynamic systems for instrument failures were developed and evaluated. In particular, application of these methods to nuclear power plant components is addressed. For a linear system, statistical tests on the innovations sequence of a Kalman filter driven by all system measurements provides a failure detection decision and identifies any failed sensor. This sequence (in an unfailed system) is zero-mean with calculable covariance; hence, any major deviation from these properties is assumed to be due to an instrument failure. Once a failure is identified, the failed instrument is replaced with an optimal estimate of the measured parameter. This failure accommodation is accomplished using optimally combined data from a bank of accommodation Kalman filters (one for each sensor), each driven by a single measurement. Using such a sensor replacement allows continued system operation under failed conditions and provides a system operator with information otherwise unavailable. To demonstrate monitor performance, a liner failure monitor was developed for the pressurizer in the Loss-of-Fluid Test (LOFT) reactor plant. LOFT is a small-scale pressurized water reactor (PWR) research facility located at the Idaho National Engineering Laboratory. A linear, third-order model of the pressurizer dynamics was developed from first principles and validated. Using data from the LOFT L6 test series, numerous actual and simulated water level, pressure, and temperature sensor failures were employed to illustrate monitor capabilities. Failure monitor design was applied to nonlinear dynamic systems by replacing all monitor linear Kalman filters with extended Kalman filters. A nonlinear failure monitor was derived for LOFT reactor instrumentation. A sixth-order reactor model, including descriptions of reactor kinetics, fuel rod heat transfer, and core coolant dynamics, was obtained and verified with test data

The predictive power of SIMION/SDS simulation software for modeling ion mobility spectrometry instruments

Science.gov (United States)

Lai, Hanh; McJunkin, Timothy R.; Miller, Carla J.; Scott, Jill R.; Almirall, José R.

2008-09-01

The combined use of SIMION 7.0 and the statistical diffusion simulation (SDS) user program in conjunction with SolidWorks® with COSMSOSFloWorks® fluid dynamics software to model a complete, commercial ion mobility spectrometer (IMS) was demonstrated for the first time and compared to experimental results for tests using compounds of immediate interest in the security industry (e.g., 2,4,6-trinitrotoluene, 2,7-dinitrofluorene, and cocaine). The effort of this research was to evaluate the predictive power of SIMION/SDS for application to IMS instruments. The simulation was evaluated against experimental results in three studies: (1) a drift:carrier gas flow rates study assesses the ability of SIMION/SDS to correctly predict the ion drift times; (2) a drift gas composition study evaluates the accuracy in predicting the resolution; (3) a gate width study compares the simulated peak shape and peak intensity with the experimental values. SIMION/SDS successfully predicted the correct drift time, intensity, and resolution trends for the operating parameters studied. Despite the need for estimations and assumptions in the construction of the simulated instrument, SIMION/SDS was able to predict the resolution between two ion species in air within 3% accuracy. The preliminary success of IMS simulations using SIMION/SDS software holds great promise for the design of future instruments with enhanced performance.

Green power programs in Canada : 2003 : overview of Government green power policies, utility green power implementation initiatives, green power and certificate marketing programs, and their benefits

International Nuclear Information System (INIS)

Whitmore, J.; Bramley, M.; Holmes, R.

2004-09-01

Green power is defined as electricity produced from renewable sources, and whose production has low adverse impacts on the environment, human health and communities. Green power has near-zero greenhouse gas (GHG) emissions and includes sources such as wind, hydro, and solar power. It offers several environmental benefits, as well as the enhancement of energy security, regional development, economic diversification and the creation of skilled jobs. There are four categories of programs related to green power development in Canada: government green power policies, utility green power development programs, green power marketing initiatives, and green power certificate marketing initiatives. Most of the activities in Canada associated with these four categories in 2003 were discussed in this report. However, difficulties with quantification prevented the inclusion of some green power activities such as (1) the generation of green power not certified or identified by the generator as green power, (2) industry or residential self-generation, (3) net metering, and (4) small government programs. Green power generation facilities in 2003 totaled 775 MW of capacity compared to 539 MW in 2002. Hydro capacity represented 41 per cent, followed by wind capacity at 40 per cent and wood waste at 17 per cent. Most of the green power generation facilities in 2003 were located in Alberta, followed by British Columbia, Ontario and Quebec. 230 refs., 8 tabs., 1 fig

Extrinsic Motivators Affecting Fourth-Grade Students' Interest and Enrollment in an Instrumental Music Program

Science.gov (United States)

Vasil, Martina

2013-01-01

The purpose of this study was to investigate fourth-grade students' extrinsic motivators for joining and continuing in a school instrumental music program. Three research questions were investigated: (a) What extrinsic motivators have influenced fourth-grade students' initial interest and continuing participation in an instrumental music program?…

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

The image of psychology programs: the value of the instrumental-symbolic framework.

Science.gov (United States)

Van Hoye, Greet; Lievens, Filip; De Soete, Britt; Libbrecht, Nele; Schollaert, Eveline; Baligant, Dimphna

2014-01-01

As competition for funding and students intensifies, it becomes increasingly important for psychology programs to have an image that is attractive and makes them stand out from other programs. The current study uses the instrumental-symbolic framework from the marketing domain to determine the image of different master's programs in psychology and examines how these image dimensions relate to student attraction and competitor differentiation. The samples consist of both potential students (N = 114) and current students (N = 68) of three psychology programs at a Belgian university: industrial and organizational psychology, clinical psychology, and experimental psychology. The results demonstrate that both instrumental attributes (e.g., interpersonal activities) and symbolic trait inferences (e.g., sincerity) are key components of the image of psychology programs and predict attractiveness as well as differentiation. In addition, symbolic image dimensions seem more important for current students of psychology programs than for potential students.

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.

Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions.

Energy Technology Data Exchange (ETDEWEB)

Muna, Alice Baca [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaFleur, Chris Bensdotter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brooks, Dusty Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-01

This report presents the results of instrumentation cable tests sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research and performed at Sandia National Laboratories (SNL). The goal of the tests was to assess thermal and electrical response behavior under fire-exposure conditions for instrumentation cables and circuits. The test objective was to assess how severe radiant heating conditions surrounding an instrumentation cable affect current or voltage signals in an instrumentation circuit. A total of thirty-nine small-scale tests were conducted. Ten different instrumentation cables were tested, ranging from one conductor to eight-twisted pairs. Because the focus of the tests was thermoset (TS) cables, only two of the ten cables had thermoplastic (TP) insulation and jacket material and the remaining eight cables were one of three different TS insulation and jacket material. Two instrumentation cables from previous cable fire testing were included, one TS and one TP. Three test circuits were used to simulate instrumentation circuits present in nuclear power plants: a 4–20 mA current loop, a 10–50 mA current loop and a 1–5 VDC voltage loop. A regression analysis was conducted to determine key variables affecting signal leakage time.

Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

Energy Technology Data Exchange (ETDEWEB)

Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T. [KAIST, Daejeon (Korea, Republic of); Lee, So I. [KHNP CRI, Daejeon (Korea, Republic of)

2014-10-15

According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident.

Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

International Nuclear Information System (INIS)

Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T.; Lee, So I.

2014-01-01

According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident

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

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)

Food Sanitation and Safety Self-Assessment Instrument for School Nutrition Programs.

Science.gov (United States)

California State Dept. of Education, Sacramento.

Like food-service establishments, child nutrition programs are responsible for preserving the quality and wholesomeness of food. Proper food-handling practices prevent contamination and job-related accidents. Application of the evaluation instrument presented in this document to individual programs helps to define proper practices, assess the…

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

Curriculum Management Practices in Pedagogical Coordinations of Araucania Schools: Unveiling Technical/Instrumental Rationality, Control and Power Mechanisms Underlying

Directory of Open Access Journals (Sweden)

Juan Carlos Beltrán-Véliz

2016-01-01

Full Text Available This article consists of a case study regarding curriculum management practices of pedagogical coordinators in schools in Araucania area. The study aims to reveal technical/instrumental rationality, control and power mechanisms that underlie the curriculum management practices of such pedagogical coordinators of schools in Araucania region. A descriptive qualitative design based on the constructionist grounded theory and the constant comparative method is considered. Subjects studied included 12 technical leaders and 22 teachers from Araucania schools. Techniques for collecting information were semi-structured interview and texts for reading. Four categories rose from axial coding. Findings reveal that the teaching process is reduced to an instructional process. Furthermore, there is no uniformity of criteria regarding general functions that must be met. In the same extent, activity coordination is centered on bureaucratic administrative aspects, with main focus on task control. Regulations, programs and educational projects are used as control mechanisms. In addition, absence of spaces for professional discussion of pedagogical work and for constructive criticism is envisioned. This study concludes that pedagogical coordination practices are geared from an “instrumental rationality”, anchored in technical management set up in control and power.

77 FR 38277 - Wind and Water Power Program

Science.gov (United States)

2012-06-27

... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Wind and Water Power Program... public meeting. SUMMARY: The Department of Energy (DOE) Wind and Water Power Program is planning a... in Washington, DC on June 13, 2012. Mark Higgins, Wind and Water Power Acting Program Manager, Office...

Advancement of High Power Quasi-CW Laser Diode Arrays For Space-based Laser Instruments

Science.gov (United States)

Amzajerdian, Farzin; Meadows, Byron L.; Baker, nathaniel R.; Baggott, Renee S.; Singh, Upendra N.; Kavaya, Michael J.

2004-01-01

Space-based laser and lidar instruments play an important role in NASA s plans for meeting its objectives in both Earth Science and Space Exploration areas. Almost all the lidar instrument concepts being considered by NASA scientist utilize moderate to high power diode-pumped solid state lasers as their transmitter source. Perhaps the most critical component of any solid state laser system is its pump laser diode array which essentially dictates instrument efficiency, reliability and lifetime. For this reason, premature failures and rapid degradation of high power laser diode arrays that have been experienced by laser system designers are of major concern to NASA. This work addresses these reliability and lifetime issues by attempting to eliminate the causes of failures and developing methods for screening laser diode arrays and qualifying them for operation in space.

MGR COMPLIANCE PROGRAM GUIDANCE PACKAGE FOR RADIATION PROTECTION EQUIPMENT, INSTRUMENTATION, AND FACILITIES

International Nuclear Information System (INIS)

2000-01-01

This Compliance Program Guidance Package identifies the regulatory guidance and industry codes and standards addressing radiation protection equipment, instrumentation, and support facilities considered to be appropriate for radiation protection at the Monitored Geologic Repository (MGR). Included are considerations relevant to radiation monitoring instruments, calibration, contamination control and decontamination, respiratory protection equipment, and general radiation protection facilities. The scope of this Guidance Package does not include design guidance relevant to criticality monitoring, area radiation monitoring, effluent monitoring, and airborne radioactivity monitoring systems since they are considered to be the topics of specific design and construction requirements (i.e., ''fixed'' or ''built-in'' systems). This Guidance Package does not address radiation protection design issues; it addresses the selection and calibration of radiation monitoring instrumentation to the extent that the guidance is relevant to the operational radiation protection program. Radon and radon progeny monitoring instrumentation is not included in the Guidance Package since such naturally occurring radioactive materials do not fall within the NRC's jurisdiction at the MGR

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

BROOKHAVEN NATIONAL LABORATORY INSTRUMENTATION DIVISION, R AND D PROGRAMS, FACILITIES, STAFF

International Nuclear Information System (INIS)

INSTRUMENTATION DIVISION STAFF

1999-01-01

To develop state-of-the-art instrumentation required for experimental research programs at BNL, and to maintain the expertise and facilities in specialized high technology areas essential for this work. Development of facilities is motivated by present BNL research programs and anticipated future directions of BNL research. The Division's research efforts also have a significant impact on programs throughout the world that rely on state-of-the-art radiation detectors and readout electronics. Our staff scientists are encouraged to: Become involved in challenging problems in collaborations with other scientists; Offer unique expertise in solving problems; and Develop new devices and instruments when not commercially available. Scientists from other BNL Departments are encouraged to bring problems and ideas directly to the Division staff members with the appropriate expertise. Division staff is encouraged to become involved with research problems in other Departments to advance the application of new ideas in instrumentation. The Division Head integrates these efforts when they evolve into larger projects, within available staff and budget resources, and defines the priorities and direction with concurrence of appropriate Laboratory program leaders. The Division Head also ensures that these efforts are accompanied by strict adherence to all ES and H regulatory mandates and policies of the Laboratory. The responsibility for safety and environmental protection is integrated with supervision of particular facilities and conduct of operations

BROOKHAVEN NATIONAL LABORATORY INSTRUMENTATION DIVISION, R AND D PROGRAMS, FACILITIES, STAFF.

Energy Technology Data Exchange (ETDEWEB)

INSTRUMENTATION DIVISION STAFF

1999-06-01

To develop state-of-the-art instrumentation required for experimental research programs at BNL, and to maintain the expertise and facilities in specialized high technology areas essential for this work. Development of facilities is motivated by present BNL research programs and anticipated future directions of BNL research. The Division's research efforts also have a significant impact on programs throughout the world that rely on state-of-the-art radiation detectors and readout electronics. Our staff scientists are encouraged to: Become involved in challenging problems in collaborations with other scientists; Offer unique expertise in solving problems; and Develop new devices and instruments when not commercially available. Scientists from other BNL Departments are encouraged to bring problems and ideas directly to the Division staff members with the appropriate expertise. Division staff is encouraged to become involved with research problems in other Departments to advance the application of new ideas in instrumentation. The Division Head integrates these efforts when they evolve into larger projects, within available staff and budget resources, and defines the priorities and direction with concurrence of appropriate Laboratory program leaders. The Division Head also ensures that these efforts are accompanied by strict adherence to all ES and H regulatory mandates and policies of the Laboratory. The responsibility for safety and environmental protection is integrated with supervision of particular facilities and conduct of operations.

Virtual instrumention-based linearity test platform for DCCT of digital power supply at SSRF

International Nuclear Information System (INIS)

Tang Junlong; Li Deming; Shen Tianjian; Liu Hong

2008-01-01

Based on virtual instrumentation, a reliable and effective test platform, performing instrument control, data acquisition and data recording, has been established to evaluate linearity of high performance DCCT (DC current transducer) for digital power supply at Shanghai Synchrotron Radiation Facility (SSRF). The software in LabVIEW language was developed to perform computer communication via serial communication (RS232) and GPIB, providing a friendly user interface to the linearity test platform. This makes it easy to test the linearity and control power on or off and current output of high-precision and high-current DC constant current output power supply. The experimental data, stored in an EXCEL file, can be processed to obtain DCCT linearity, and provide basis to further analyze DCCT performance in the future. (authors)

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)

Instrument for Airborne Measurement of Carbonyl Sulfide, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — In this Phase II SBIR program, Southwest Sciences will continue the development of small, low power instrumentation for real-time direct measurement of carbonyl...

Design of the power sources for portable nuclear instruments

International Nuclear Information System (INIS)

Chen Wei; Fang Fang; Cui Yan; Cui Junliang; Zhou Wei

2007-01-01

How to charge for the portable equipments is always a topical subject aimed by people, the application of new type batteries and Battery Management brings great facility to people's life, the rechargeable battery for portable equipments is widely used in portable equipments, but the convenience of the charging power source is limited in special situation. This paper will discuss how to combining rechargeable battery with traditional alkaline batteries for charging the portable instruments. (authors)

Subject to empowerment: the constitution of power in an educational program for health professionals.

Science.gov (United States)

Juritzen, Truls I; Engebretsen, Eivind; Heggen, Kristin

2013-08-01

Empowerment and user participation represents an ideal of power with a strong position in the health sector. In this article we use text analysis to investigate notions of power in a program plan for health workers focusing on empowerment. Issues addressed include: How are relationships of power between users and helpers described in the program plan? Which notions of user participation are embedded in the plan? The analysis is based on Foucault's idea that power which is made subject to attempts of redistribution will re-emerge in other forms. How this happens, and with what consequences, is our analytical concern. The analysis is contrasted with 'snapshots' from everyday life in a nursing home. The program plan communicates empowerment as a democracy-building instrument that the users need. It is a tool for providing expert assistance to the user's self-help. User participation is made into a tool which is external to the user him-/herself. Furthermore, the analysis shows that the plan's image of empowerment presupposes an 'élite user' able to articulate personal needs and desires. This is not very applicable to the most vulnerable user groups, who thereby may end up in an even weaker position. By way of conclusion, we argue that an exchange of undesirable dominating paternalism for a desirable empowerment will not abolish power, but may result in more covert and subtle forms of power that are less open to criticism. The paper offers insights that will facilitate reflections on the premises for practising empowerment-oriented health care.

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)

Visual interface for the automation of the instrumented pendulum of Charpy tests used in the surveillance program of reactors vessel of nuclear power plants; Interfase visual para la automatizacion del pendulo instrumentado de pruebas Charpy utilizado en el programa de vigilancia de la vasija de reactores de centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A. [ININ, Carretera Mexico-Toluca Km.36.5, Mpio. de Ocoyoacac, Estado de Mexico (Mexico)]. E-mail: asrs@nuclear.inin.mx; esm@nuclear.inin.mx; jare@nuclear.inin.mx

2004-07-01

Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)

The power professorship program at Washington State University

International Nuclear Information System (INIS)

Mosher, C.C.; Shamash, Y.

1993-01-01

As with most electric power programs, Washington State University's has existed since the beginning of the engineering program 100 years ago. It has grown and developed largely through the efforts of a few dedicated individuals. The Power Professorship Program has existed since 1972. The Power Professor has been Dr. Clifford C. Mosher until his recent semi-retirement. The Power Professorship was conceived of as an avenue for joint university-industry interaction. Considerable time and ingenuity by visionary engineers and others have resulted in development of a financial base for the Power Professorship Program. The program has been funded equally by public and investor-utility sectors. Following financial difficulties stemming from the Washington Public Power Supply System financial default on public utility bonds for several nuclear projects, funding for the program from the public sector was canceled. After several lean years, public-sector support was again restored by WSU's electrical engineering department offering a contract for services to the utilities in exchange for funding. This contract has been renewed annually, with costs and benefits firmly established through careful analysis and consultation. Problems facing the power industry in the early 1970s with regard to establishing a pipeline of future human resources, were almost identical with those of the present time: indifferent feelings about the industry in general, students being attracted to more glamorous disciplines, and a decline in educational opportunities available in the power area. A 1985 article in the IEEE Power Engineering Review describing today's declining enrollment in power engineering applies equally well to previous periods. A major driving force for initiating utility-industry participation in the Power Professorship Program was the concern for maintaining a source of entry-level engineers with a background in power engineering

Non-power application as an entry point to nuclear power program

International Nuclear Information System (INIS)

Nahrul Khair Alang Md Rashid

2009-01-01

Nuclear power is usually viewed as the flagship of nuclear technology. A nuclear power plant complex, visible and prominence, is iconic of the technology. That image makes its presence common knowledge to the extent that nuclear technology is equated almost totally with nuclear power by the general public. The downside of this visibility is that it becomes easy target in public misinformation programs. The non-power applications however are not visible, and devoid of icon. The non-power applications, therefore, can grow quite smoothly, attracting only little attention in the negative and in the positive senses. According to a study conducted in the USA in 2000 and in Japan in 2002, the socio-economic impact of non-power and power applications of nuclear technology are comparable. Involvement in non-power applications can be a good grounding for moving into power applications. This paper discusses the non-power nuclear technology applications and in what manner it can serve to prepare the introduction of nuclear power program. (Author)

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

A pragmatic study of speech as an instrument of power: Analysis of the 2016 USA presidential debate

Directory of Open Access Journals (Sweden)

Misyi Gusthini

2018-03-01

Full Text Available This research was aimed at analyzing the speeches of Donald Trump and of Hillary Clinton in the USA Presidential candidates’ debates as instruments of power. The data is a presidential final debate video of Trump and Clinton made in September 2016 which has been converted into a transcript. The data analyzing technique is divided into three steps: 1 describing the context, 2 analyzing the illocutionary acts, and 3 analyzing the power dimensions. The results of this research show that the speakers use the speech act as an instrument of power with classifications of representative, commissive and expressive. In this regard, the researchers found that the speakers demonstrated their power to try to convince the voters in their society to trust them to be the president. The research results also showed that the usage of speech in debate as an instrument of power can influence the voters especially on Election Day.

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.

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

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

Structural optimization of static power control programs of nuclear power plants with WWER-1000

International Nuclear Information System (INIS)

Kokol, E.O.

2015-01-01

The question of possibility the power control programs switching for WWER-1000 is considered. The aim of this research is to determine the best program for the power control of nuclear reactor under cyclic diurnal behavior of electrical generation, as well as the switching implementation. The considered problem of finding the best control program refers to the multicriteria optimization class of problems. Operation of the nuclear power generation system simulated using the following power control programs: with constant average temperature of transfer fluid, with constant pressure in the reactor secondary circuit, with constant temperature in input of the nuclear reactor. The target function was proposed. It consists of three normalized criteria: the burn up fraction, the damage level of fuel rod array shells, as well as changes in the power values. When simulation of the nuclear power generation system operation within the life was done, the values of the selected criteria were obtained and inserted in the target function. The minimum of three values of the target function depending on the control program at current time defined the criterion of switching of considered static power control programs for nuclear power generation system

Radiation monitoring instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Bharath Kumar, M.

2013-01-01

Measurement of nucleonic signals is required to control and operate the reactor in a safe and reliable manner. To achieve this, parameters like Neutron flux, other radiation fields, contamination levels, source strength, release thru stack etc. are required to be monitored and controlled. The above are required to be monitored throughout the life of the reactor whether it is operational or in shutdown condition. In addition such monitoring is also required during decommissioning phase of the reactor as needed. To measure these parameters a large number of instruments are used in Nuclear Power Plants (NPP) which includes sensors and electronics for detecting alpha, beta, gamma and neutron radiation with qualification to withstand harsh environment

Power Burst Facility: power oscillation problem

International Nuclear Information System (INIS)

Lussie, W.G.; Wadkins, R.P.; Wells, R.A.

1975-01-01

In late 1973 PBF achieved a power level of 15 MW. During this period of operation fluctuations in reactor power were observed. Many possible causes of these fluctuations were considered and a number of nuclear and non-nuclear tests were conducted. Initial instrumentation installed in the core showed coolant outlet temperature variations of 10 0 F for several fuel cannisters and approximately 10 percent power variations at 15 MW. Power spectral density analysis showed a predominant frequency of 0.05 to 0.06 HZ. The testing program to determine the cause of the power oscillations is described

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.

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

Systems analysis programs for hands-on integrated reliability evaluations (SAPHIRE) Version 5.0. Fault tree, event tree, and piping ampersand instrumentation diagram (FEP) editors reference manual: Volume 7

International Nuclear Information System (INIS)

McKay, M.K.; Skinner, N.L.; Wood, S.T.

1994-07-01

The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs), primarily for nuclear power plants. The Fault Tree, Event Tree, and Piping and Instrumentation Diagram (FEP) editors allow the user to graphically build and edit fault trees, and event trees, and piping and instrumentation diagrams (P and IDs). The software is designed to enable the independent use of the graphical-based editors found in the Integrated Reliability and Risk Assessment System (IRRAS). FEP is comprised of three separate editors (Fault Tree, Event Tree, and Piping and Instrumentation Diagram) and a utility module. This reference manual provides a screen-by-screen guide of the entire FEP System

Perceptually Salient Regions of the Modulation Power Spectrum for Musical Instrument Identification.

Science.gov (United States)

Thoret, Etienne; Depalle, Philippe; McAdams, Stephen

2017-01-01

The ability of a listener to recognize sound sources, and in particular musical instruments from the sounds they produce, raises the question of determining the acoustical information used to achieve such a task. It is now well known that the shapes of the temporal and spectral envelopes are crucial to the recognition of a musical instrument. More recently, Modulation Power Spectra (MPS) have been shown to be a representation that potentially explains the perception of musical instrument sounds. Nevertheless, the question of which specific regions of this representation characterize a musical instrument is still open. An identification task was applied to two subsets of musical instruments: tuba, trombone, cello, saxophone, and clarinet on the one hand, and marimba, vibraphone, guitar, harp, and viola pizzicato on the other. The sounds were processed with filtered spectrotemporal modulations with 2D Gaussian windows. The most relevant regions of this representation for instrument identification were determined for each instrument and reveal the regions essential for their identification. The method used here is based on a "molecular approach," the so-called bubbles method. Globally, the instruments were correctly identified and the lower values of spectrotemporal modulations are the most important regions of the MPS for recognizing instruments. Interestingly, instruments that were confused with each other led to non-overlapping regions and were confused when they were filtered in the most salient region of the other instrument. These results suggest that musical instrument timbres are characterized by specific spectrotemporal modulations, information which could contribute to music information retrieval tasks such as automatic source recognition.

77 FR 31839 - Wind and Water Power Program

Science.gov (United States)

2012-05-30

... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Wind and Water Power Program... projects. The 2012 Wind and Water Power Program, Wind Power Peer Review Meeting will review wind technology... portfolio. The 2012 Wind Power Peer Review Meeting will be held June 19 through June 21, 2012, in Alexandria...

Light Water Reactor Sustainability Program Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan for 2013

Energy Technology Data Exchange (ETDEWEB)

Hallbert, Bruce [Idaho National Laboratory (INL), Idaho Falls, ID (United States); Thomas, Ken [Idaho National Laboratory (INL), Idaho Falls, ID (United States)

2014-09-01

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.

A low power consumption and multi-function mini-printer for the portable nuclear instruments

International Nuclear Information System (INIS)

Jin Yuheng; Zhang Jiahong

1994-01-01

The authors presents a method of fitting a commercial printing calculator to the low power consumption and multi-function mini-printer. It can be employed as a compact data recorder and simple data processing device attached to the portable nuclear instruments, which are powered by dry batteries

Validation of smart sensor technologies for instrument calibration reduction in nuclear power plants

International Nuclear Information System (INIS)

Hashemian, H.M.; Mitchell, D.W.; Petersen, K.M.; Shell, C.S.

1993-01-01

This report presents the preliminary results of a research and development project on the validation of new techniques for on-line testing of calibration drift of process instrumentation channels in nuclear power plants. These techniques generally involve a computer-based data acquisition and data analysis system to trend the output of a large number of instrument channels and identify the channels that have drifted out of tolerance. This helps limit the calibration effort to those channels which need the calibration, as opposed to the current nuclear industry practice of calibrating essentially all the safety-related instrument channels at every refueling outage

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

Portable neutron and gamma-radiation instruments

International Nuclear Information System (INIS)

Murray, W.S.; Butterfield, K.B.

1990-01-01

This paper reports on the design and building of a smart neutron and gamma-radiation detection systems with embedded microprocessors programmed in the FORTH language. These portable instruments can be battery-powered and can provide many analysis functions not available in most radiation detectors. Local operation of the instruments is menu-driven through a graphics liquid crystal display and hex keypad; remote operation is through a serial communications link. While some instruments simply count particles, others determine the energy of the radiation as well as the intensity. The functions the authors have provided include absolute source-strength determination. Feynmann variance analysis, sequential-probability ratio test, and time-history recording

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

The role of policy instruments for promoting combined heat and power production with low CO2 emissions in district heating systems

International Nuclear Information System (INIS)

Marbe, A.; Harvey, S.

2005-01-01

Policy instruments clearly influence the choice of production technologies and fuels in large energy systems, including district heating networks. Current Swedish policy instruments aim at promoting the use of biofuel in district heating systems, and at promoting electric power generation from renewable energy sources. However, there is increasing pressure to harmonize energy policy instruments within the EU. In addition, natural gas based combined cycle technology has emerged as the technology of choice in the power generation sector in the EU. This study aims at exploring the role of policy instruments for promoting the use of low CO 2 emissions fuels in high performance combined heat and power systems in the district heating sector. The paper presents the results of a case study for a Swedish district heating network where new large size natural gas combined cycle (NGCC) combined heat and power (CHP) is being built. Given the aim of current Swedish energy policy, it is assumed that it could be of interest in the future to integrate a biofuel gasifier to the CHP plant and co-fire the gasified biofuel in the gas turbine unit, thereby reducing usage of fossil fuel. The goals of the study are to evaluate which policy instruments promote construction of the planned NGCC CHP unit, the technical performance of an integrated biofuelled pressurized gasifier with or without dryer on plant site, and which combination of policy instruments promote integration of a biofuel gasifier to the planned CHP unit. The power plant simulation program GateCycle was used for plant performance evaluation. The results show that current Swedish energy policy instruments favour investing in the NGCC CHP unit. The corresponding cost of electricity (COE) from the NGCC CHP unit is estimated at 253 SEK MWh -1 , which is lower than the reference power price of 284 SEK MWh -1 . Investing in the NGCC CHP unit is also shown to be attractive if a CO 2 trading system is implemented. If the value of

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)

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

Electromagnetic pulse research on electric power systems: Program summary and recommendations. Power Systems Technology Program

Energy Technology Data Exchange (ETDEWEB)

Barnes, P.R.; McConnell, B.W.; Van Dyke, J.W. [Oak Ridge National Lab., TN (United States); Tesche, F.M. [Tesche (F.M.), Dallas, TX (United States); Vance, E.F. [Vance (E.F.), Fort Worth, TX (United States)

1993-01-01

A single nuclear detonation several hundred kilometers above the central United States will subject much of the nation to a high-altitude electromagnetic pulse (BENT). This pulse consists of an intense steep-front, short-duration transient electromagnetic field, followed by a geomagnetic disturbance with tens of seconds duration. This latter environment is referred to as the magnetohydrodynamic electromagnetic pulse (NMENT). Both the early-time transient and the geomagnetic disturbance could impact the operation of the nation`s power systems. Since 1983, the US Department of Energy has been actively pursuing a research program to assess the potential impacts of one or more BENT events on the nation`s electric energy supply. This report summarizes the results of that program and provides recommendations for enhancing power system reliability under HENT conditions. A nominal HENP environment suitable for assessing geographically large systems was developed during the program and is briefly described in this report. This environment was used to provide a realistic indication of BEMP impacts on electric power systems. It was found that a single high-altitude burst, which could significantly disturb the geomagnetic field, may cause the interconnected power network to break up into utility islands with massive power failures in some areas. However, permanent damage would be isolated, and restoration should be possible within a few hours. Multiple bursts would likely increase the blackout areas, component failures, and restoration time. However, a long-term blackout of many months is unlikely because major power system components, such as transformers, are not likely to be damaged by the nominal HEND environment. Moreover, power system reliability, under both HENT and normal operating conditions, can be enhanced by simple, and often low cost, modifications to current utility practices.

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

International Nuclear Information System (INIS)

Stroebeck, E.

1992-01-01

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

KiloPower Program

Energy Technology Data Exchange (ETDEWEB)

McClure, Patrick Ray [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-08-04

These are the slides for a phone interview with Aerospace America magazine of the AIAA. It goes over the KiloPower Program at Los Alamos National Laboratory (LANL), and covers the following: 1 kWe Kilopower, 10 kWe Kilopower, Kilopower Reactor Using Stirling Technology (KRUSTY) Integration Test (DAF), Reactor Configuration, and Platen Positions.

HUD PowerSaver Pilot Loan Program

Energy Technology Data Exchange (ETDEWEB)

Zimring, Mark [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Hoffman, Ian [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2010-12-10

The U.S. Department of Housing and Urban Development (HUD) recently announced the creation of a pilot loan program for home energy improvements. The PowerSaver loan program is a new, energy-focused variant of the Title I Property Improvement Loan Insurance Program (Title I Program) and is planned for introduction in early 2011. The PowerSaver pilot will provide lender insurance for secured and unsecured loans up to $25,000 to single family homeowners. These loans will specifically target residential energy efficiency and renewable energy improvements. HUD estimates the two-year pilot will fund approximately 24,000 loans worth up to $300 million; the program is not capped. The Federal Housing Administration (FHA), HUD's mortgage insurance unit, will provide up to $25 million in grants as incentives to participating lenders. FHA is seeking lenders in communities with existing programs for promoting residential energy upgrades.

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

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

International Nuclear Information System (INIS)

Lu, Lixuan; Jiang, Jin

2004-01-01

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

Quality assurance program for nuclear power plants

International Nuclear Information System (INIS)

Gamon, T.H.

1976-02-01

The Topical Report presented establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of the report

Quality assurance program for nuclear power plants

International Nuclear Information System (INIS)

Gamon, T.H.

1976-06-01

This topical report establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of this report

Light Water Reactor Sustainability Program Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan for FY 2016

Energy Technology Data Exchange (ETDEWEB)

Hallbert, Bruce Perry [Idaho National Lab. (INL), Idaho Falls, ID (United States); Thomas, Kenneth David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-10-01

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.

2014 Water Power Program Peer Review Report

Energy Technology Data Exchange (ETDEWEB)

none,

2014-08-18

The Water Power Peer Review Meeting was held February 24-28, 2014 in Arlington, VA. Principle investigators from the Energy Department National Laboratories, academic, and industry representatives presented the progress of their DOE-funded research. This report documents the formal, rigorous evaluation process and findings of nine independent reviewers who examined the technical, scientific, and business results of 96 projects of the Water Power Program, as well as the productivity and management effectiveness of the Water Power Program itself.

Inspector-instrument interface in portable NDA instrumentation

International Nuclear Information System (INIS)

Halbig, J.K.; Klosterbuer, S.F.

1981-01-01

Recent electronics technology advances make it possible to design sophisticated instruments in small packages for convenient field implementation. An inspector-instrument interface design that allows communication of procedures, responses, and results between the instrument and user is presented. This capability has been incorporated into new spent-fuel instrumentation and a battery-powered multichannel analyzer

Inspector-instrument interface in portable NDA instrumentation

International Nuclear Information System (INIS)

Halbig, J.K.; Klosterbuer, S.F.

1981-01-01

Recent electronics technology advances make it possible to design sophisticated instruments in small packages for convenient field implementation. This report describes an inspector-instrument interface design which allows communication of procedures, responses, and results between the instrument and user. The interface has been incorporated into new spent-fuel instrumentation and a battery-powered multichannel analyzer

Aseismatic design of electrical equipments and instruments for nuclear power stations

International Nuclear Information System (INIS)

Suzuki, Yasuharu; Nishizawa, Kazuo; Miyazaki, Yoshio; Miura, Takumi

1977-01-01

The aseismatic design of electrical instruments is carried out according to IEEE Standard 344-1971 in the USA. In Japan also, the method of aseismatic design of electrical instruments has been investigated by the representatives of electric power companies and electric machine makers since 1972. In Hitachi Ltd., the statical method of confirming aseismatic property was established on the basis of the rigid design for electrical instruments. It is convenient to examine the aseismatic property of electrical equipments by classifying them into control and switch boards, electrical appliances, equipments and circuits. It is possible to use the static method treating earthquake force as static load by avoiding resonance with the electrical equipments which have the higher natural frequency than that of buildings. The purposes of the vibration test are to prove the validity of the theoretical analysis, to clarify the vibration characteristics, and to confirm the maintenance of functions and the strength of the equipments. The vibration tests of control boards, the switch boards of enclosed type, motor control centers, the racks for instrumentation, storage batteries and electrical appliances are explained. Moreover, the vibration analysis with a computer according to finite element method is described. (Kako, I.)

On the Measurement of Power Law Creep Parameters from Instrumented Indentation

Science.gov (United States)

Sudharshan Phani, P.; Oliver, W. C.; Pharr, G. M.

2017-11-01

Recently the measurement of the creep response of materials at small scales has received renewed interest largely because the equipment required to perform high-temperature nanomechanical testing has become available to an increasing number of researchers. Despite that increased access, there remain several significant experimental and modeling challenges in small-scale mechanical testing at elevated temperatures that are as yet unresolved. In this regard, relating the creep response observed with high-temperature instrumented indentation experiments to macroscopic uniaxial creep response is of great practical value. In this review, we present an overview of various methods currently being used to measure creep with instrumented indentation, with a focus on geometrically self-similar indenters, and their relative merits and demerits from an experimental perspective. A comparison of the various methods to use those instrumented indentation results to predict the uniaxial power law creep response of a wide range of materials will be presented to assess their validity.

Surveillance of instrumentation channels at nuclear power plants

International Nuclear Information System (INIS)

Thie, J.A.

1989-06-01

Surveillance activities at nuclear plants, involving-calibrations, functional tests, and simple checks, have many associated problems. These problems are of the following four types: administrative, equipment, human, and systemic. An extensive search of the literature has led to 63 generic classes of problems falling within these types and involving instrumentation department activities. The classification system is that which writers of incidents are essentially using, based on historical traditions, in naming their problems' causes. An interesting finding in the search was the strong correlation of this project to many aspects of industrial safety; technology transfer opportunities from the latter are identified. A survey of plant instrumentation experts was conducted to obtain a ranking of the most important problems. Classes of solutions to these problems are listed and discussed. Outlined is a possible methodology of matching these solutions to problems. Finally applications of this study are listed, and include extensions to training, operations, and maintenance departments of power plants. Appendices give several general examples for each problem class and many specific suggestions from experts on addressing the problems felt to be more important. 15 refs., 2 figs., 6 tabs

Space Solar Power Program. Final report

Energy Technology Data Exchange (ETDEWEB)

Arif, Humayun; Barbosa, Hugo; Bardet, Christophe; Baroud, Michel; Behar, Alberto; Berrier, Keith; Berthe, Phillipe; Bertrand, Reinhold; Bibyk, Irene; Bisson, Joel; Bloch, Lawrence; Bobadilla, Gabriel; Bourque, Denis; Bush, Lawrence; Carandang, Romeo; Chiku, Takemi; Crosby, Norma; De Seixas, Manuel; De Vries, Joha; Doll, Susan; Dufour, Francois; Eckart, Peter; Fahey, Michael; Fenot, Frederic; Foeckersperger, Stefan; Fontaine, Jean-Emmanuel; Fowler, Robert; Frey, Harald; Fujio, Hironobu; Gasa, Jaume Munich; Gleave, Janet; Godoe, Jostein; Green, Iain; Haeberli, Roman; Hanada, Toshiya; Harris, Peter; Hucteau, Mario; Jacobs, Didier Fernand; Johnson, Richard; Kanno, Yoshitsugu; Koenig, Eva Maria; Kojima, Kazuo; Kondepudi, Phani; Kottbauer, Christian; Kulper, Doede; Kulagin, Konstantin; Kumara, Pekka; Kurz, Rainer; Laaksonen, Jyrki; Lang, Andrew Neill; Lathan, Corinna; Le Fur, Thierry; Lewis, David; Louis, Alain; Mori, Takeshi; Morlanes, Juan; Murbach, Marcus; Nagatomo, Hideo; O' brien, Ivan; Paines, Justin; Palaszewski, Bryan; Palmnaes, Ulf; Paraschivolu, Marius; Pathare, Asmin; Perov, Egor; Persson, Jan; Pessoa-Lopes, Isabel; Pinto, Michel; Porro, Irene; Reichert, Michael; Ritt-Fischer, Monika; Roberts, Margaret; Robertson II, Lawrence; Rogers, Keith; Sasaki, Tetsuo; Scire, Francesca; Shibatou, Katsuya; Shirai, Tatsuya; Shiraishi, Atsushi; Soucaille, Jean-Francois; Spivack, Nova; St. Pierre, Dany; Suleman, Afzal; Sullivan, Thomas; Theelen, Bas Johan; Thonstad, Hallvard; Tsuji, Masatoshi; Uchiumi, Masaharu; Vidqvist, Jouni; Warrell, David; Watanabe, Takafumi; Willis, Richard; Wolf, Frank; Yamakawa, Hiroshi; Zhao, Hong

1992-08-01

Information pertaining to the Space Solar Power Program is presented on energy analysis; markets; overall development plan; organizational plan; environmental and safety issues; power systems; space transportation; space manufacturing, construction, operations; design examples; and finance.

Financial Instruments: the Essence, Diversity and Role in the Process of Modernization of the Electric Power Sector

Directory of Open Access Journals (Sweden)

Abakumenko Olha V.

2017-03-01

Full Text Available The aim of the article is to clarify the methodological basis for further research concerning analysis of the existing practices and development of proposals on using financial instruments for the modernization of the Ukrainian electric power sector, in particular, to clarify the definition of “financial instruments” and justify their classification, taking into account the defining characteristics. Based on the critical evaluation of various scientific approaches to interpretation of the essence of financial instruments, the author’s definition is proposed. Thus, it is advisable to consider them as means, techniques and methods of attracting financial resources (capital from other entities and as absolutely liquid assets. The generalization and rethinking of the criteria for classification of financial instruments allowed the authors to divide them into financial assets (cash, bank metals, currency, financial obligations (equity and debt instruments, and instruments of irrevocable financial aid (charitable contributions, grants, crowdfunding, fundraising. The received methodological conclusions quite fully characterize the essence and variety of types of financial instruments, taking into account their principal properties, which will allow to make a well-considered justification for choosing the optimal instruments for the modernization of the electric power sector.

University Reactor Instrumentation grant program. Final report, September 7, 1990--August 31, 1995

International Nuclear Information System (INIS)

Talnagi, J.W.

1998-01-01

The Ohio State University Nuclear Reactor Laboratory (OSU NRL) participated in the Department of Energy (DOE) grant program commonly denoted as the University Reactor Instrumentation (URI) program from the period September 1990 through August 1995, after which funding was terminated on a programmatic basis by DOE. This program provided funding support for acquisition of capital equipment targeted for facility upgrades and improvements, including modernizing reactor systems and instrumentation, improvements in research and instructional capabilities, and infrastructure enhancements. The staff of the OSU NRL submitted five grant applications during this period, all of which were funded either partially or in their entirety. This report will provide an overview of the activities carried out under these grants and assess their impact on the OSU NRL facilities

Upgrade of the NCSU PULSTAR instrumentation power channels. Final technical report, September 1, 1992 - August 31, 1994

International Nuclear Information System (INIS)

Perez, P.B.

1998-01-01

The Nuclear Reactor Program at North Carolina State University initiated an upgrade program at the NCSU PULSTAR Reactor in 1990. The originally supplied instrumentation has been replaced with solid-state and current technology equipment. The financial assistance from the US Department of Energy has been the primary source of support. This is the final report for the Instrumentation Upgrade

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.)

Green Power Partnership Related Programs & Organizations

Science.gov (United States)

The U.S. EPA's Green Power Partnership is a voluntary program designed to reduce the environmental impact of electricity generation by promoting renewable energy. This page provides a brief program overview, including vision and accomplishments.

Instrument response during overpower transients at TREAT

International Nuclear Information System (INIS)

Meek, C.C.; Bauer, T.H.; Hill, D.J.; Froehle, P.H.; Klickman, A.E.; Tylka, J.P.; Doerner, R.C.; Wright, A.E.

1982-01-01

A program to empirically analyze data residuals or noise to determine instrument response that occurs during in-pile transient tests is out-lined. As an example, thermocouple response in the Mark III loop during a severe overpower transient in TREAT is studied both in frequency space and in real-time. Time intervals studied included both constant power and burst portions of the power transient. Thermocouple time constants were computed. Benefits and limitations of the method are discussed

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

International Nuclear Information System (INIS)

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

1988-12-01

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

Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Laudenbach, D.H.

1979-03-01

The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory.

Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

International Nuclear Information System (INIS)

Laudenbach, D.H.

1979-03-01

The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory

India's power program and its concern over environmental safety

International Nuclear Information System (INIS)

Prasad, G.E.; Mittra, J.

2001-01-01

India's need of electrical power is enormous and per capita consumption of power is to be increased at least by ten times to reach the level of world average. Thermal Power generation faces two fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India's self reliant, three stage, 'closed-fuel-cycle' nuclear power program is promising better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating necessary safety features in the design, operational safety through structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from nuclear power program. Based on latest technology, as available in case of nuclear power option, it is quite possible to meet high energy requirement with least impact on the environment.. (authors)

Program for analyzing power boost tests

International Nuclear Information System (INIS)

Wills, C.A.

1982-03-01

A rapid increase of power in a reactor produces a failure in the fuel. Experiments to study the conditions in the NRU reactor after such failures have been planned and carried out. Given the concentrations of specified isotopes at a number of times over the length of an experiment as produced for example, from the program SARGS and the power history of the reactor, this program calculates the release rates, escape rate coefficients, and fractional releases for the isotopes. These values may be optionally printed and plotted. Decay schemes for a limited number of mass numbers are implemented. The program is written in FORTRAN and runs on the CDC 6600 - CYBER 170 system

Instrument performance evaluation

International Nuclear Information System (INIS)

Swinth, K.L.

1993-03-01

Deficiencies exist in both the performance and the quality of health physics instruments. Recognizing the implications of such deficiencies for the protection of workers and the public, in the early 1980s the DOE and the NRC encouraged the development of a performance standard and established a program to test a series of instruments against criteria in the standard. The purpose of the testing was to establish the practicality of the criteria in the standard, to determine the performance of a cross section of available instruments, and to establish a testing capability. Over 100 instruments were tested, resulting in a practical standard and an understanding of the deficiencies in available instruments. In parallel with the instrument testing, a value-impact study clearly established the benefits of implementing a formal testing program. An ad hoc committee also met several times to establish recommendations for the voluntary implementation of a testing program based on the studies and the performance standard. For several reasons, a formal program did not materialize. Ongoing tests and studies have supported the development of specific instruments and have helped specific clients understand the performance of their instruments. The purpose of this presentation is to trace the history of instrument testing to date and suggest the benefits of a centralized formal program

Nuclear Power Plant Control and Instrumentation activities in the United Kingdom

International Nuclear Information System (INIS)

Goodings, A.

1990-01-01

The paper describes the status of the NPP control and instrumentation in the United Kingdom. The general technology underlying most aspects of power reactor C and I in the UK has not altered since the last progress report although there have been many improvements in detail. In one field, however, that of computer applications, the change has almost been one of kind rather than degree. The following fields are briefly described: The status of nuclear power in the UK, the development of sensors, the development of electronic equipment, signal processing - information technology, quality assurance and the validation and verification of software, expert systems, training simulators. (author). 1 ref

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)

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

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

EPRI nuclear power plant decommissioning technology program

International Nuclear Information System (INIS)

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

2011-01-01

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

EU Science Diplomacy and Framework Programs as Instruments of STI Cooperation

Directory of Open Access Journals (Sweden)

К. А. Ibragimova

2017-01-01

Full Text Available This article examines the tools that the EU in interactions with third countries in the field of STI uses. The EU is a pioneer in the use of science and technology in the international arena, the creation of strategic bilateral agreements on science and technology and the conduct of political dialogues at the highest political level (at the country and regional levels. The EU actively uses its foreign policy instruments of influence, including the provision of access to its framework programs to researchers from third countries, as well as scientific diplomacy. The success of these programs and scientific diplomacy shows the effectiveness of the EU as a global actor. In its foreign policy global innovation strategy, the EU proceeds from the premise that no state in the world today can cope independently with modern global challenges such as climate change, migration, terrorism, etc. Therefore, the solution of these issues requires both an expert evaluation from an independent world scientific community, and the perseverance of diplomats and officials of branch ministries of national states capable of conveying the views of their government in international negotiations and defending national interests of the country to find a solution that suits everyone. The EU has the resources to create a "cumulative effect" by developing and applying common norms on the territory of theUnion, analyzing the innovation policies of member states and the possibility of sharing best practices. At the same time, the EU shares its vision of problems, values and priorities with partners and uses the tools of "soft power" (including its smart and normative force and scientific diplomacy in the field of STI. The soft power of the EU in the field of STI lies in the attractiveness of the EU as a research area in which it is possible to conduct modern high-quality international research with the involvement of scientific teams from different countries in both physical

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

Development and test of the ZELT-3D computer code for unfolding power distributions using side reflector instrumentation signals

International Nuclear Information System (INIS)

Knob, P.J.

1983-01-01

The impossibility of using internal instrumentation in high temperature reactor with spherical fuel, lead to the development of an instrumentation system that will be able to monitorate power perturbations only using detectors located in the reflectors. This instrumentation is divided in three parts: one for each reflector, higher, lower and lateral. The development of a system located in the lateral reflector is shown. The system was tested for Kahter from IRE-KFA of very low dimensions and for the PNP-300 power reactor of very large dimensions. Good results were obtained. (E.G.) [pt

Policy instruments for development of wind power in Sweden; Styrmedel foer vindkraftens utveckling i Sverige

Energy Technology Data Exchange (ETDEWEB)

Aastrand, Kerstin; Neij, Lena

2003-07-01

It is often believed that energy policy and policy instruments can play a significant role in the transition towards sustainable energy by stimulating and accelerating the development and deployment of new energy technologies. However, despite the known need for, and benefits of, new energy technologies their market introduction and expansion is often slow. Wind power has been on the political agenda since the 1970s in several European countries as well as in other countries throughout the world. However, the technology and market development of wind power has been very different in these countries. Despite three decades of policy intervention the installed capacity in Sweden was only 265 MW in 2000, compared with 6,107 MW in Germany, 2,836 MW in Spain and 2,341 MW in Denmark. This report analyses the effects of policy instruments on wind power development in Sweden and identifies possible reasons why wind power has not been installed to a greater extent. The analysis is based on an empirical example of a socio technological system-based approach to evaluation of technology and market development for new energy technologies; i.e. an approach focused on the technological system including the actors, institutions and organizations that build, drive and utilise it and the economic and legal framework that regulates it. The aim is to assess the impact on technology and market development and to discuss the relatively late and slow wind power development in Sweden. The report also examines the achievement of governmental energy policy goals. Using the socio-technological systems approach we analyse Swedish policy programmes and wind power development between 1975 and 2000. The political and economic framework is identified. The discussion of the political and economic frameworks is limited to public policy goals and policy instruments. The policy focus is set to policy instruments aimed for technology and market development of wind power, such as research and

Genesis of the Brazilian nuclear power plants program

International Nuclear Information System (INIS)

Syllus, G.; Lepecki, W.

1996-01-01

The genesis of the Brazilian Nuclear Power Program is described by the authors - who participated in the events - from the beginning of the sixties, until the definition and the start of the implementation in 1975 of the Reference Nuclear Power Program. A description is made of the main events, studies and decisions that contributed to the evolution of the Program: the GTRP (Nuclear Power Plant Working Group); the Thorium Group; the Lane Group; the decision about Angra 1; CNEN's analyses about the reactor line and, finally, the creation of CBTN (Nuclear Technology Brazilian Company), which elaborated the studies that resulted in the final definition of the Program and led to the Brazilian German Agreement and the establishment of NUCLEBRAS. (author)

India's power programs and its concern over environmental safety

International Nuclear Information System (INIS)

Prasad, G.E.; Mittra, J.; Sarma, M.S.R.

2000-01-01

India's need for electrical power is enormous and per capita consumption of power is to be increased at least by 10 times to reach the level of the world average. Thermal power generation faces two-fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India 's self reliant, . three stage, 'closed-fuel-cycle' nuclear power program is promising a better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, the Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating' necessary safety features in the design, operational safety through a structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from the nuclear power program. Based on the latest technology, as available in case of the nuclear power option, it is quite possible to meet high energy requirements with least impact on the environment. (authors)

Development of highly reliable power and communication system for essential instruments under severe accidents in NPP

Energy Technology Data Exchange (ETDEWEB)

Choi, Bo Hwan; Jang, Gi Chan; Shin, Sung Min; Kang, Hyun Gook; Rim, Chun Taek [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Lee, Soo Ill [I and C Group, Korea Hydro and Nuclear Power Co., Ltd, Central Research Institute, Daejeon (Korea, Republic of)

2016-10-15

This article proposes a highly reliable power and communication system that guarantees the protection of essential instruments in a nuclear power plant under a severe accident. Both power and communication lines are established with not only conventional wired channels, but also the proposed wireless channels for emergency reserve. An inductive power transfer system is selected due to its robust power transfer characteristics under high temperature, high pressure, and highly humid environments with a large amount of scattered debris after a severe accident. A thermal insulation box and a glass-fiber reinforced plastic box are proposed to protect the essential instruments, including vulnerable electronic circuits, from extremely high temperatures of up to 627 .deg. C and pressure of up to 5 bar. The proposed wireless power and communication system is experimentally verified by an inductive power transfer system prototype having a dipole coil structure and prototype Zigbee modules over a 7-m distance, where both the thermal insulation box and the glass-fiber reinforced plastic box are fabricated and tested using a high-temperature chamber. Moreover, an experiment on the effects of a high radiation environment on various electronic devices is conducted based on the radiation test having a maximum accumulated dose of 27 Mrad.

Development of Highly Reliable Power and Communication System for Essential Instruments Under Severe Accidents in NPP

Directory of Open Access Journals (Sweden)

Bo Hwan Choi

2016-10-01

Full Text Available This article proposes a highly reliable power and communication system that guarantees the protection of essential instruments in a nuclear power plant under a severe accident. Both power and communication lines are established with not only conventional wired channels, but also the proposed wireless channels for emergency reserve. An inductive power transfer system is selected due to its robust power transfer characteristics under high temperature, high pressure, and highly humid environments with a large amount of scattered debris after a severe accident. A thermal insulation box and a glass-fiber reinforced plastic box are proposed to protect the essential instruments, including vulnerable electronic circuits, from extremely high temperatures of up to 627°C and pressure of up to 5 bar. The proposed wireless power and communication system is experimentally verified by an inductive power transfer system prototype having a dipole coil structure and prototype Zigbee modules over a 7-m distance, where both the thermal insulation box and the glass-fiber reinforced plastic box are fabricated and tested using a high-temperature chamber. Moreover, an experiment on the effects of a high radiation environment on various electronic devices is conducted based on the radiation test having a maximum accumulated dose of 27 Mrad.

Development of highly reliable power and communication system for essential instruments under severe accidents in NPP

International Nuclear Information System (INIS)

Choi, Bo Hwan; Jang, Gi Chan; Shin, Sung Min; Kang, Hyun Gook; Rim, Chun Taek; Lee, Soo Ill

2016-01-01

This article proposes a highly reliable power and communication system that guarantees the protection of essential instruments in a nuclear power plant under a severe accident. Both power and communication lines are established with not only conventional wired channels, but also the proposed wireless channels for emergency reserve. An inductive power transfer system is selected due to its robust power transfer characteristics under high temperature, high pressure, and highly humid environments with a large amount of scattered debris after a severe accident. A thermal insulation box and a glass-fiber reinforced plastic box are proposed to protect the essential instruments, including vulnerable electronic circuits, from extremely high temperatures of up to 627 .deg. C and pressure of up to 5 bar. The proposed wireless power and communication system is experimentally verified by an inductive power transfer system prototype having a dipole coil structure and prototype Zigbee modules over a 7-m distance, where both the thermal insulation box and the glass-fiber reinforced plastic box are fabricated and tested using a high-temperature chamber. Moreover, an experiment on the effects of a high radiation environment on various electronic devices is conducted based on the radiation test having a maximum accumulated dose of 27 Mrad

Levelling the playing field? The influence of national wind power planning instruments on conflicts of interests in a Swedish county

International Nuclear Information System (INIS)

Bergek, Anna

2010-01-01

Slow and complicated wind power planning and permitting procedures have been a large obstacle for wind power diffusion in Sweden and other countries. This paper complements previous siting-oriented literature with a planning perspective on these problems. The focus is two national planning instruments implemented in Sweden in the early 2000s: a national planning target and an appointment of areas of national interest for wind power. The paper identifies different types of conflicts of interest related to wind power - in addition to the conflict between wind power as a national public interest and various local private interests - and analyses the impact of the national planning instruments on the handling of these conflicts in the land-use planning process in the County of Ostergoetland. The analysis shows that the planning target actually made local planning officials even more inclined to treat wind power as a private rather than a public interest and that the method used to identify areas of national interest of wind power forced wind power to compete with the combined strengths of all other public interest. The planning instruments thus left wind power to fight an uphill battle rather than to meet other interests face-to-face on a level playing field.

IAEA eLearning Program: The Use of Radiation Detection Instruments

International Nuclear Information System (INIS)

2010-01-01

This CD-ROM contains a computer based training on Radiation Detection Techniques for Nuclear Security Applications. The IAEA Nuclear Security eLearning tool offers computer based training to Frontline Officers to improve their understanding about key elements of the use of radiation detection instruments. The eLearning program prepares Frontline Officers for the IAEA Detection and Response Frontline Officer course

Defense waste processing facility at Savannah River Plant. Instrument and power jumpers

International Nuclear Information System (INIS)

Heckendorm, F.M. II.

1983-06-01

The Defense Waste Processing Facility (DWPF) for waste vitrification at the Savannah River Plant is in the final design stage. Development of equipment interconnecting devices or jumpers for use within the remotely operated processing canyon is now complete. These devices provide for the specialized instrument and electrical requirements of the DWPF process for low-voltage, high-frequency, and high-power interconnections

Technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun Nuclear Power Plant

International Nuclear Information System (INIS)

Hackett, D.B.

1980-01-01

This report documents the technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun nuclear power plant. The review criteria are based on IEEE Std-279-1971 requirements for the safety signals to all purge and ventilation isolation valves. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory

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.)

The Bonneville Power Administration's geothermal program

International Nuclear Information System (INIS)

Darr, G.D.

1990-01-01

Despite being a power source with many desirable characteristics, geothermal has not been developed in the Pacific Northwest because of high costs, high risks, and the lack of a market for power. The region will require new power sources in the 1990s, and will need to know to what extent it can rely on geothermal. The Bonneville Power Administration has developed a geothermal RD and D program which includes a proposal to award power contracts to three pilot projects in the Northwest. Public outreach efforts, environmental base line studies, and economic and land use impact studies will also be undertaken. In this paper two projects already under way are discussed

PLC/DTAM Software Programs for Pumping Instrumentation and Control Skid X

International Nuclear Information System (INIS)

HORNER, T.M.

2001-01-01

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 ''X''. 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 will be tailored for each individual BY-farm skid. An Acceptance Test Procedure (ATP) and an Operational Test Procedure (OTP) verify that the software programs meet the specific requirements for BY-105 pumping. This document represents the final PLC and DTAM programs for PIC skid ''X'' at BY-105. 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

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.

The design of an instrument to evaluate software for EFL/ESL pronunciation teaching

Directory of Open Access Journals (Sweden)

Cristiana Gomes de Freitas Menezes Martins

2016-01-01

Full Text Available http://dx.doi.org/10.5007/2175-8026.2016v69n1p141 The purpose of this study was to develop and test the reliability and validity of an instrument to evaluate the extent to which software programs teach English as a Foreign Language and/or Second Language (EFL/ESL pronunciation following the principles of the Communicative Approach (Celce-Murcia et al, 2010, thus having the potential to develop English pronunciation. After the development of the instrument, 46 EFL/ESL teachers used it to analyze an online version of the software program Pronunciation Power 2. The responses of the participants were submitted to statistical analysis and the validity and reliability of the instrument were tested. The good reliability indexes obtained in this study suggest the instrument has some degree of validity for evaluating how well an ESL/EFL pronunciation teaching software program potentially develops English pronunciation.

Low power data acquisition unit for autonomous geophysical instrumentation

Science.gov (United States)

Prystai, Andrii

2017-04-01

The development of an autonomous instrumentation for field research is always a challenge which needs knowledge and application of recent advances in technology and components production. Using this information a super-low power, low-cost, stand-alone GPS time synchronized data acquisition unit was created. It comprises an extended utilization of the microcontroller modules and peripherals and special firmware with flexible PLL parameters. The present report is devoted to a discussion of synchronization mode of data sampling in autonomous field instruments with possibility of GPS random breaks. In the result the achieved sampling timing accuracy is better than ± 60 ns without phase jumps and distortion plus fixed shift depending on the sample rate. The main application of the system is for simultaneous measurement of several channels from magnetic and electric sensors in field conditions for magneto-telluric instruments. First utilization of this system was in the new developed versions of LEMI-026 magnetometer and LEMI-423 field station, where it was applied for digitizing of up to 6 analogue channels with 32-bit resolution in the range ± 2.5V, digital filtration (LPF) and maximum sample rate 4kS/s. It is ready for record in 5 minutes after being turned on. Recently, this system was successfully utilized with the drone-portable magnetometers destined for the search of metallic objects, like UXO, in rural areas, research of engineering underground structure and for mapping ore bodies. The successful tests of drone-portable system were made and tests results are also discussed.

Automated Instrumentation, Monitoring and Visualization of PVM Programs Using AIMS

Science.gov (United States)

Mehra, Pankaj; VanVoorst, Brian; Yan, Jerry; Lum, Henry, Jr. (Technical Monitor)

1994-01-01

We present views and analysis of the execution of several PVM (Parallel Virtual Machine) codes for Computational Fluid Dynamics on a networks of Sparcstations, including: (1) NAS Parallel Benchmarks CG and MG; (2) a multi-partitioning algorithm for NAS Parallel Benchmark SP; and (3) an overset grid flowsolver. These views and analysis were obtained using our Automated Instrumentation and Monitoring System (AIMS) version 3.0, a toolkit for debugging the performance of PVM programs. We will describe the architecture, operation and application of AIMS. The AIMS toolkit contains: (1) Xinstrument, which can automatically instrument various computational and communication constructs in message-passing parallel programs; (2) Monitor, a library of runtime trace-collection routines; (3) VK (Visual Kernel), an execution-animation tool with source-code clickback; and (4) Tally, a tool for statistical analysis of execution profiles. Currently, Xinstrument can handle C and Fortran 77 programs using PVM 3.2.x; Monitor has been implemented and tested on Sun 4 systems running SunOS 4.1.2; and VK uses XIIR5 and Motif 1.2. Data and views obtained using AIMS clearly illustrate several characteristic features of executing parallel programs on networked workstations: (1) the impact of long message latencies; (2) the impact of multiprogramming overheads and associated load imbalance; (3) cache and virtual-memory effects; and (4) significant skews between workstation clocks. Interestingly, AIMS can compensate for constant skew (zero drift) by calibrating the skew between a parent and its spawned children. In addition, AIMS' skew-compensation algorithm can adjust timestamps in a way that eliminates physically impossible communications (e.g., messages going backwards in time). Our current efforts are directed toward creating new views to explain the observed performance of PVM programs. Some of the features planned for the near future include: (1) ConfigView, showing the physical topology

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)

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

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.

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

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

Validation of the efficacy of a solar-thermal powered autoclave system for off-grid medical instrument wet sterilization.

Science.gov (United States)

Kaseman, Tremayne; Boubour, Jean; Schuler, Douglas A

2012-10-01

This work describes the efficacy of a solar-thermal powered autoclave used for the wet sterilization of medical instruments in off-grid settings where electrical power is not readily available. Twenty-seven trials of the solar-thermal powered system were run using an unmodified non-electric autoclave loaded with a simulated bundle of medical instruments and biological test agents. Results showed that in 100% of the trials the autoclave achieved temperatures in excess of 121°C for 30 minutes, indicator tape displayed visible reactions to steam sterilization, and biological tests showed that microbial agents had been eliminated, in compliance with the Centers for Disease Control and Prevention requirements for efficacious wet sterilization.

Southern California Edison instrument setpoint program

International Nuclear Information System (INIS)

Bockhorst, R.M.; Quinn, E.L.

1991-01-01

In November of 1989, the US Nuclear Regulatory Commission (NRC) conducted an electrical safety system functional inspection (ESSFI) at the San Onofre nuclear generating station (SONGS), which was followed by an NRC audit on instrument setpoint methodology in January 1991. Units 2 and 3 at SONGS are 1100-MW(electric) Combustion Engineering (C-E) pressurized water reactors (PWRs) operated by Southern California Edison (SCE). The purpose of this paper is to summarize the results of the NRC audit and SCE's follow-up activities. The NRC team inspection reinforced the need to address several areas relative to the SCE setpoint program. The calculations withstood the intensive examination of four NRC inspectors for 2 weeks and only a few minor editorial-type problems were noted. Not one of the calculated plant protections system setpoints will change as a result of the audit. There were no questions raised relative to setpoint methodology

Neutron instrumentation for biology

Energy Technology Data Exchange (ETDEWEB)

Mason, S.A. [Institut Laue-Langevin, Grenoble (France)

1994-12-31

In the October 1994 round of proposals at the ILL, the external biology review sub- committee was asked to allocate neutron beam time to a wide range of experiments, on almost half the total number of scheduled neutron instruments: on 3 diffractometers, on 3 small angle scattering instruments, and on some 6 inelastic scattering spectrometers. In the 3.5 years since the temporary reactor shutdown, the ILL`s management structure has been optimized, budgets and staff have been trimmed, the ILL reactor has been re-built, and many of the instruments up-graded, many powerful (mainly Unix) workstations have been introduced, and the neighboring European Synchrotron Radiation Facility has established itself as the leading synchrotron radiation source and has started its official user program. The ILL reactor remains the world`s most intense dedicated neutron source. In this challenging context, it is of interest to review briefly the park of ILL instruments used to study the structure and energetics of small and large biological systems. A brief summary will be made of each class of experiments actually proposed in the latest ILL proposal round.

Low-voltage Power Supply Subsystem for a Sub-Orbital Particle Physic Instrument

Directory of Open Access Journals (Sweden)

Hector Hugo Silva Lopez

2014-01-01

Full Text Available The Japanese Experiment Module–Extreme Universe Space Observatory (JEM-EUSO is a wide-field (+/-~30°of aperture 2.5m refractor telescope to be installed in the International Space Station (ISS. The instrument looks downward from its orbit, into Earth’s atmosphere, with the main objective of observing ultra-violet (UV fluorescence light generated by Ultra-High Energy Cosmic Rays (UHECR extensive air showers (EAS. It is a frontier particle-physics experiment, the first of its kind. The validation of the technical readiness level of such a complex and unique instrument requires prototypes at several levels of integration. At the highest level, the EUSO-Balloon instrument has been conceived, through French space agency (CNES. At a smaller scale and in suborbital flight, EUSO-Balloon integrates all the sub-systems of the full space JEM-EUSO telescope, allowing end-to-end testing of hardware and interfaces, and to probing the global detection chain and strategy, while improving at the same time our knowledge of atmospheric and terrestrial UV background. EUSO-Balloon will be flown by CNES for the first time from Timmins, Canada; on spring 2014.This article presents the low-voltage power supply (LVPS subsystem development for the EUSO-Balloon instrument. This LVPS is the fully operational prototype for the space instrument JEM-EUSO. Besides design and construction, all performance tests and integration results with the other involved subsystems are shown.

Problems with radiological surveillance instrumentation

International Nuclear Information System (INIS)

Swinth, K.L.; Tanner, J.E.; Fleming, D.M.

1984-09-01

Many radiological surveillance instruments are in use at DOE facilities throughout the country. These instruments are an essential part of all health physics programs, and poor instrument performance can increase program costs or compromise program effectiveness. Generic data from simple tests on newly purchased instruments shows that many instruments will not meet requirements due to manufacturing defects. In other cases, lack of consideration of instrument use has resulted in poor acceptance of instruments and poor reliability. The performance of instruments is highly variable for electronic and mechanical performance, radiation response, susceptibility to interferences and response to environmental factors. Poor instrument performance in these areas can lead to errors or poor accuracy in measurements

Problems with radiological surveillance instrumentation

International Nuclear Information System (INIS)

Swinth, K.L.; Tanner, J.E.; Fleming, D.M.

1985-01-01

Many radiological surveillance instruments are in use at DOE facilities throughout the country. These instruments are an essential part of all health physics programs, and poor instrument performance can increase program costs or compromise program effectiveness. Generic data from simple tests on newly purchased instruments shows that many instruments will not meet requirements due to manufacturing defects. In other cases, lack of consideration of instrument use has resulted in poor acceptance of instruments and poor reliability. The performance of instruments is highly variable for electronic and mechanical performance, radiation response, susceptibility to interferences and response to environmental factors. Poor instrument performance in these areas can lead to errors or poor accuracy in measurements

Survey and analysis on environmental and electromagnetic effect on instrumentation and control equipment of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hwang, In Koo; Lee, Dong Young; Cha, Kyung Ho

2001-03-01

As the instrumentation and control (I and C) equipment suppliers tend to provide digital components rather than conventional analog type components for instrumentation and control systems of nuclear power plants(NPPs), it is unavoidable to adopt digital equipment for safety I and C systems as well as non-safety systems. However, the full introduction of digital equipment for I and C systems of nuclear power plants raises several concerns which have not been considered in conventional analog I and C equipment. The two major examples of the issues of digital systems are environmental/electromagnetic compatibility (EMC) and software reliability. This report presents the survey and research results on environmental and electromagnetic effect on I and C equipment of nuclear power plants to give a guideline for aging management and design process. Electromagnetic site surveys were conducted to be used as a part of technical basis to demonstrate that I and C systems are compatible with the ambient electromagnetic noise in Korean nuclear power plants.

Quality assurance program for isotopic power systems

International Nuclear Information System (INIS)

Hannigan, R.L.; Harnar, R.R.

1982-12-01

This report summarizes the Sandia National Laboratories Quality Assurance Program that applies to non-weapon (reimbursable) Radioisotopic Thermoelectric Generators. The program has been implemented over the past 16 years on power supplies used in various space and terrestrial systems. The quality assurance (QA) activity of the program is in support of the Department of Energy, Office of Space Nuclear Projects. Basic elements of the program are described in the report and examples of program decumentation are presented

Quality assurance program for isotopic power systems

Energy Technology Data Exchange (ETDEWEB)

Hannigan, R.L.; Harnar, R.R.

1982-12-01

This report summarizes the Sandia National Laboratories Quality Assurance Program that applies to non-weapon (reimbursable) Radioisotopic Thermoelectric Generators. The program has been implemented over the past 16 years on power supplies used in various space and terrestrial systems. The quality assurance (QA) activity of the program is in support of the Department of Energy, Office of Space Nuclear Projects. Basic elements of the program are described in the report and examples of program decumentation are presented.

Wind Power Today: Wind Energy Program Highlights 2001

Energy Technology Data Exchange (ETDEWEB)

2002-05-01

Wind Power Today is an annual publication that provides an overview of the U.S. Department of Energy's Wind Energy Program accomplishments for the previous year. The purpose of Wind Power Today is to show how DOE's Wind Energy Program supports wind turbine research and deployment in hopes of furthering the advancement of wind technologies that produce clean, low-cost, reliable energy. Content objectives include: educate readers about the advantages and potential for widespread deployment of wind energy; explain the program's objectives and goals; describe the program's accomplishments in research and application; examine the barriers to widespread deployment; describe the benefits of continued research and development; facilitate technology transfer; and attract cooperative wind energy projects with industry. This 2001 edition of Wind Power Today also includes discussions about wind industry growth in 2001, how DOE is taking advantage of low wind speed regions through advancing technology, and distributed applications for small wind turbines.

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

Nuclear power programs in the world's developed and developing countries

International Nuclear Information System (INIS)

Czibolya, L.

1983-01-01

The significance of nuclear power in the world's energy balance related to fossile energy sources is discussed. The general trend of declination of the national power programs could be observed from the seventies as a result of the oil crisis and the economic recession. The main features of the national energy programs including the ratio of the different energy sources in the power supply, the distribution of power production among the different types of nuclear reactors, the time schedules of the national nuclear power programs are reviewed through the examples of some developed and developing countries: USA, FRG, Canada, Japan, France, Sweden, the Soviet Union, Czechoslovakia, Bulgaria, Hungary, Romania, India, and the Republic of Korea. (V.N.)

Economic consideration for Indonesia's nuclear power program

International Nuclear Information System (INIS)

Ahimsa, D.; Sudarsono, B.

1987-01-01

Indonesia experienced relatively high economic growth during the 1970s and the energy supply system was strained to keep up with demand. Several energy studies were thus carried out around 1980, including a nuclear power planning study and a nuclear plant feasibility study. During the 1980s, economic growth rates were subtantially lower, but surprisingly electricity demand remained fairly high. In 1984 it was therefore decided to update previous nuclear power studies. This effort was completed in 1986. Using energy projections and cost estimates developed during the updating of previous nuclear power studies, the paper discusses the economic justification for a nuclear power program in Indonesia. Results of the update, including computer runs of MAED and WASP models supplied by the IAEA, will be presented along with appropriate sensitivity analysis. These results are then analyzed in the light of 1986 developments in international oil price. Preparations for the forthcoming nuclear power program are described, including the construction of a multi-purpose reactor and associated laboratories in Serpong, near Jakarta. (author)

Human resources in nuclear power program

International Nuclear Information System (INIS)

Machi, Sueo

2008-01-01

Nuclear power utilization within 2020 horizon is expanding in Asia, particularly in Japan, China, India, Republic of Korea, Vietnam and Indonesia. The nuclear energy policy iof Japan sees the increase of nuclear power contribution for energy security and to control CO 2 emission with the contribution ratio through the 21 st century kept at the current level of 30-40% or even higher. Japan expects its first reprocessing plant to be operational in 2007 and its first commercial fast breeder reactor operational in 2050. Starting with her experience with the operation of its first research reactor in 1957, a power demonstration reactor from USA in 1963; the first commercial 166 MW power plant from UK in 1966 and then its first commercial 375 MW light water reactor from USA in 1970, Japan developed her own nuclear reactor technology. Today, Japan has 55 operating nuclear power plants (NPPs) totaling 49 GW which supply 30% of its electricity needs. There are two NPPs under construction and 11 additional NPPs to be completed by 2017. Japan's experience showed that engineers in the nuclear, mechanical, electrical, material and chemical fields are needed to man their nuclear power plant. For the period 1958 to about 1970, there was a rapid increase in the number of students enrolled for their bachelor of science majoring in nuclear science and technology but this number of enrollees leveled off beyond 1970 up to 2002. For those pursuing their masters of science degree in this field, there was a steady but moderate rise in the number of students from 1958 to 2002. The population of students in the Ph.D program in nuclear science and technology had the lowest number of enrollees and lowest level of increase from 1958 to 2002. The courses offered at the university for nuclear power are nuclear reactor physics and engineering, nuclear reactor safety engineering and radiation safety. Prior to graduation, the students undergo training at a nuclear research institute, nuclear power

Wind power today: 1999 Wind Energy program highlights

Energy Technology Data Exchange (ETDEWEB)

Weis-Taylor, Pat

2000-04-06

Wind Power Today is an annual publication that provides an overview for the Department of Energy's Wind Energy Program. The purpose of Wind Power Today is to show how DOE's Wind Energy Program supports wind turbine research and deployment in hopes of furthering the advancement of wind technologies that produce clean, low-cost, reliable energy for the 21st century. Content objectives include: Educate readers about the advantages and potential for widespread deployment of wind energy; explain DOE wind energy program objectives and goals; describe program accomplishments in research and application; examine the barriers to widespread deployment; describe benefits of continued research and development; facilitate technology transfer; attract cooperative wind energy projects with industry.

The BEAR program NRL plasma physics instrumentation measurements

Energy Technology Data Exchange (ETDEWEB)

Walker, D.N.; Baumback, M.M.; Haas, D.G.; Rodriguez, P.; Siefring, C.L.; Doggett, R.A. [Naval Research Lab., Washington, DC (United States)

1989-11-15

The BEAR program was a joint effort to launch, and demonstrate the feasibility of operating, a 1 MeV 10 ma Neutral Particle Beam (NPB) accelerator from a space platform. The accelerator design and manufacture were the responsibility of Los Alamos National Lab (LANL); diagnostics associated with accelerator operation and beam-plasma effects were also to be undertaken by LANL and NRL. Payload Integration and Telemetry was provided by the Air Force Geophysical Lab (AFGL) and Northeastern University (NEU). Beam effects on the local plasma in addition to accelerator produced vehicle effects (e.g., charging) were the responsibility of NRL as outlined herein. The BEAR rocket was launched successfully during the early morning hours of July 13 from White Sands Missile Range, White Sands, N.M. The NRL contribution to this effort included three instrument packages designed to diagnose beam-plasma and vehicle-plasma interactions. The instruments included: (1) Langmuir probe (LP) design consisting of 4 separate sensors; (2) High voltage (HIV) Langmuir Probe designed to monitor vehicle charging through current polarity changes; and (3) Plasma Wave Receive (PWR) designed to characterize the plasma wave emissions covering a broad frequency range from near DC to 50 MHz.

The standard calibration instrument automation system for the atomic absorption spectrophotometer. Part 3: Program documentation

Science.gov (United States)

Ryan, D. P.; Roth, G. S.

1982-04-01

Complete documentation of the 15 programs and 11 data files of the EPA Atomic Absorption Instrument Automation System is presented. The system incorporates the following major features: (1) multipoint calibration using first, second, or third degree regression or linear interpolation, (2) timely quality control assessments for spiked samples, duplicates, laboratory control standards, reagent blanks, and instrument check standards, (3) reagent blank subtraction, and (4) plotting of calibration curves and raw data peaks. The programs of this system are written in Data General Extended BASIC, Revision 4.3, as enhanced for multi-user, real-time data acquisition. They run in a Data General Nova 840 minicomputer under the operating system RDOS, Revision 6.2. There is a functional description, a symbol definitions table, a functional flowchart, a program listing, and a symbol cross reference table for each program. The structure of every data file is also detailed.

Ageing studies on materials, components and process instruments used in nuclear power plants

International Nuclear Information System (INIS)

Bora, J.S.

1997-04-01

This report is a compilation of test results of thermal and radiation ageing tests carried out in the laboratory over a period of 25 years on diverse engineering materials, components and instruments used in nuclear power plants. Test items covered are different types of electrical cables, elastomers, surface coatings, electrical and electronics components and process instruments. Effects of thermal and radiation ageing on performance parameters are shown in tabular forms. Apart from finding the characteristics, capabilities and limitations of test items, ageing research has helped in pin-pointing sub-standard and critical parts and necessary corrective action has been taken. This report is expected to be quite useful to the manufacturers users and researchers for reference and guidance. (author)

Instrumentation of a Charpy-pendulum. Additional data obtained from it and its application to nuclear reactor pressure vessels surveillance programs

International Nuclear Information System (INIS)

Chomik, Enrique P.; Dhers, Horacio; Iorio, Antonio F.; Ciriani, Dario F.

1999-01-01

Charpy test gives information about a material dynamic fracture behavior. In a plain Charpy test, this information is the absorbed energy during fracture of the specimen, lateral deformation and the percentage of ductile fracture of the specimen. These parameters can then be used for the determination of the material response to a dynamic applied load, and are used at present to determine the brittle-ductile transition temperature of a material. However, there is a lot of additional information that can be obtained from a Charpy test, which is vital for the case of surveillance programs of nuclear power plants, where it is necessary to get the most available information from the specimens to be tested, because each one of them was irradiated for many years under temperature and neutronic flux conditions similar to that of the internal surface of the reactor pressure vessel, which converts these specimens in unique and very expensive ones. This additional information can be obtained from the curve that determines the evolution of the applied force to the specimen throughout the time involved in its fracture. It was possible to instrument a Charpy pendulum at a fraction of the cost necessary to buy an instrumentation package like the ones available in the market, and since the instrumentation equipment obtained is easy to transport. It has the additional advantage that can be used to instrument any other pendulum replacing only the hammer of the pendulum with a instrumented one for that pendulum. (author)

Overall quality assurance program requirements for nuclear power plants

International Nuclear Information System (INIS)

1992-09-01

This standard contains the requirements for the owner's overall quality assurance program for a nuclear power plant. This program encompasses all phases of a nuclear power plant life cycle, including site evaluation, design, procurement, manufacturing, construction and installation, commissioning, operation, and decommissioning. It covers the activities associated with specifying, directing, and administering the work to be done during these phases, and the evaluation and integrated of the activities and programs of participants

Design automation of switching mode high voltage power supply for nuclear instruments

International Nuclear Information System (INIS)

El-araby, S.M.S.

1999-01-01

This paper presents an automation procedure for the design of switching mode high voltage power supplies, using Pc programming facility. The procedure permits the selection of a ready made or designed ferrite transformer. This selection could be achieved according to the designer desire; as the program includes complete information about ready made ferrite transformer through complete database. The procedure is based on suggested template circuit. Micro-Cap IV simulation package is used to verify the desired high voltage power supply design. Simulation results agree quite well with suggested procedure's results. Design aspects and development needed to increase automation capabilities are also discussed

Gene expression programming for power system static security ...

African Journals Online (AJOL)

user

Keywords: static security, gene expression programming, probabilistic neural network ... Hence digital computers are usually installed in operations control centers to gather ...... power system protection, and applications of AI in power systems.

A Dynamic Programming based method for optimizing power system restoration with high wind power penetration

DEFF Research Database (Denmark)

Hu, Rui; Hu, Weihao; Li, Pengfei

2016-01-01

and relatively low cost. Thus, many countries are increasing the wind power penetration in their power system step by step, such as Denmark, Spain and Germany. The incremental wind power penetration brings a lot of new issues in operation and programming. The power system sometimes will operate close to its...... stable limits. Once the blackout happens, a well-designed restoration strategy is significant. This paper focuses on how to ameliorate the power system restoration procedures to adapt the high wind power penetration and how to take full advantages of the wind power plants during the restoration....... In this paper, the possibility to exploit the stochastic wind power during restoration was discussed, and a Dynamic Programming (DP) method was proposed to make wind power contribute in the restoration rationally as far as possible. In this paper, the method is tested and verified by a modified IEEE 30 Buses...

Virginia Power's regulatory reduction program

International Nuclear Information System (INIS)

Miller, G.D.

1996-01-01

Virginia Power has two nuclear plants, North Anna and Surry Power Stations, which have two units each for a total of four nuclear units. In 1992, the Nuclear Regulatory Commission solicited comments from the nuclear industry to obtain their ideas for reducing the regulatory burden on nuclear facilities. Pursuant to the new regulatory climate, Virginia Power developed an internal program to evaluate and assess the regulatory and self-imposed requirements to which they were committed, and to pursue regulatory relief or internal changes where possible and appropriate. The criteria were that public safety must be maintained, and savings must be significant. Up to the date of the conference, over US$22 million of one-time saving had been effected, and US$2.75 million in annual savings

Space Power Program, Instrumentation and Control System Architecture, Preconceptual Design, for Information

International Nuclear Information System (INIS)

JM Ross

2005-01-01

The purpose of this letter is to forward the Prometheus preconceptual Instrumentation and Control (I and C) system architecture (Enclosure (1)) to NR for information as part of the Prometheus closeout work. The preconceptual 1 and C system architecture was considered a key planning document for development of the I and C system for Project Prometheus. This architecture was intended to set the technical approach for the entire I and C system. It defines interfaces to other spacecraft systems, defines hardware blocks for future development, and provides a basis for accurate cost and schedule estimates. Since the system requirements are not known at this time, it was anticipated that the architecture would evolve as the design of the reactor module was matured

Development of thermocouple re-instrumentation technique for irradiated fuel rod. Techniques for making center hole into UO2 pellets and thermocouple re-instrumentation to fuel rod

International Nuclear Information System (INIS)

Shimizu, Michio; Saito, Junichi; Oshima, Kunio

1995-07-01

The information on FP gas pressure and centerline temperature of fuel pellets during power transient is important to study the pellet clad interaction (PCI) mechanism of high burnup LWR fuel rods. At the Department of JMTR, a re-instrumentation technique of FP gas pressure gage for an irradiated fuel rod was developed in 1990. Furthermore, a thermocouple re-instrumentation technique was successfully developed in 1994. Two steps were taken to carry out the development program of the thermocouple re-instrumentation technique. In the first step, a drilling technique was developed for making a center hole of the irradiated fuel pellets. Various drilling tests were carried out using dummy of fuel rods consisted of Ba 2 FeO 3 pellets and Zry-2 cladding. On this work it is important to keep the pellets just the state cracked at a power reactor. In these tests, the technique to fix the pellets by frozen CO 2 was used during the drilling work. Also, diamond drills were used to make the center hole. These tests were completed successfully. A center hole, 54mm depth and 2.5mm diameter, was realized by these methods. The second step of this program is the in-pile demonstration test on an irradiated fuel rod instrumented dually a thermocouple and FP gas pressure gage. The demonstration test was carried out at the JMTR in 1995. (author)

Computer program analyzes and monitors electrical power systems (POSIMO)

Science.gov (United States)

Jaeger, K.

1972-01-01

Requirements to monitor and/or simulate electric power distribution, power balance, and charge budget are discussed. Computer program to analyze power system and generate set of characteristic power system data is described. Application to status indicators to denote different exclusive conditions is presented.

Wind Power Today: 2000 Wind Energy Program Highlights

Energy Technology Data Exchange (ETDEWEB)

Weis-Taylor, W.

2001-05-08

Wind Power Today is an annual publication that provides an overview of the U.S. Department of Energy's Wind Energy Program. The purpose of Wind Power Today is to show how DOE's Wind Energy Program supports wind turbine research and deployment in hopes of furthering the advancement of wind technologies that produce clean, low-cost, reliable energy. Content objectives include: educate readers about the advantages and potential for widespread deployment of wind energy; explain the program's objectives and goals; describe the program's accomplishments in research and application; examine the barriers to widespread deployment; describe the benefits of continued research and development; facilitate technology transfer; and attract cooperative wind energy projects with industry.

Digital nuclear instrumentation application to nuclear power plant

International Nuclear Information System (INIS)

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

1993-01-01

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

NASA developments in solid state power amplifiers

Science.gov (United States)

Leonard, Regis F.

1990-01-01

Over the last ten years, NASA has undertaken an extensive program aimed at development of solid state power amplifiers for space applications. Historically, the program may be divided into three phases. The first efforts were carried out in support of the advanced communications technology satellite (ACTS) program, which is developing an experimental version of a Ka-band commercial communications system. These first amplifiers attempted to use hybrid technology. The second phase was still targeted at ACTS frequencies, but concentrated on monolithic implementations, while the current, third phase, is a monolithic effort that focusses on frequencies appropriate for other NASA programs and stresses amplifier efficiency. The topics covered include: (1) 20 GHz hybrid amplifiers; (2) 20 GHz monolithic MESFET power amplifiers; (3) Texas Instruments' (TI) 20 GHz variable power amplifier; (4) TI 20 GHz high power amplifier; (5) high efficiency monolithic power amplifiers; (6) GHz high efficiency variable power amplifier; (7) TI 32 GHz monolithic power amplifier performance; (8) design goals for Hughes' 32 GHz variable power amplifier; and (9) performance goals for Hughes' pseudomorphic 60 GHz power amplifier.

Life extension activities and modernization strategies for instrumentation ampersand control systems of research and power reactors in India

International Nuclear Information System (INIS)

Chaganty, S.P.; Bairi, B.R.

1993-01-01

Based on three and half decades of experience gained in the operation and maintenance of Instrumentation and Control Systems of nuclear reactors in India, specific investigations were made to understand various aspects of aging. The analysis of the failure rates of various instruments, plant outage figures and obsolescence of components have necessitated the replacement of instrumentation to improve the reliability and performance. The aging models available were used to determine the extent of performance degradation and to formulate maintenance strategies. The nuclear instrumentation of the aging research reactors at Bhabha Atomic Research Centre (BARC) has been replaced with high reliability equipment using modern integrated circuits. This has resulted in an improvement in the mean time between failure (MTBF) by a factor of five. The neutronic instrumentation of Fast Breeder Test Reactor (FBTR) at Madras is currently being upgraded with the introduction of microprocessor based safety units for reactivity computation and online testing of safety logic with Fine Impulse Technique. The operating experience has also indicated the necessity of developing online surveillance methods and status monitoring of various systems to detect aging. Online cable insulation measurement technique and noise analysis methods for vibration monitoring have been developed. Campbell method of signal processing has been successfully used in extending the useful life of Local Power Range monitors in the Boiling Water Reactor at Tarapur. In order to improve reliability, accuracy and provide efficient man machine interface, microprocessor based systems with online testing features have been installed in power reactors. These include the high performance reactor regulating system and centralised radiation monitoring systems commissioned at Kakrapara power station. The paper describes the above systems and the modernization strategies for nuclear instrumentation and control

Concentrating Solar Power Program Review 2013 (Book) (Revised)

Energy Technology Data Exchange (ETDEWEB)

2013-06-01

This U.S. Department of Energy (DOE) Concentrating Solar Power Program Review Meeting booklet will be provided to attendees at the Concentrating Solar Power Review Meeting in Phoenix, Arizona on April 23-25, 2013.

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

Research and engineering application of coordinated instrumentation control and protection technology between reactor and steam turbine generator on nuclear power plant

International Nuclear Information System (INIS)

Sun Xingdong

2014-01-01

The coordinated instrumentation control and protection technology between reactor and steam turbine generator (TG) usually is very significant and complicated for a new construction of nuclear power plant, because it carries the safety, economy and availability of nuclear power plant. Based on successful practice of a nuclear power plant, the experience on interface design and hardware architecture of coordinated instrumentation control and protection technology between reactor and steam turbine generator was abstracted and researched. In this paper, the key points and engineering experience were introduced to give the helpful instructions for the new project. (author)

Instrumentation development

International Nuclear Information System (INIS)

Ubbes, W.F.; Yow, J.L. Jr.

1988-01-01

Instrumentation is developed for the Civilian Radioactive Waste Management Program to meet several different (and sometimes conflicting) objectives. This paper addresses instrumentation development for data needs that are related either directly or indirectly to a repository site, but does not touch on instrumentation for work with waste forms or other materials. Consequently, this implies a relatively large scale for the measurements, and an in situ setting for instrument performance. In this context, instruments are needed for site characterization to define phenomena, develop models, and obtain parameter values, and for later design and performance confirmation testing in the constructed repository. The former set of applications is more immediate, and is driven by the needs of program design and performance assessment activities. A host of general technical and nontechnical issues have arisen to challenge instrumentation development. Instruments can be classed into geomechanical, geohydrologic, or other specialty categories, but these issues cut across artificial classifications. These issues are outlined. Despite this imposing list of issues, several case histories are cited to evaluate progress in the area

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1976-01-01

The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

Instrument and Survey Analysis Technical Report: Program Implementation Survey. Technical Report #1112

Science.gov (United States)

Alonzo, Julie; Tindal, Gerald

2011-01-01

This technical document provides guidance to educators on the creation and interpretation of survey instruments, particularly as they relate to an analysis of program implementation. Illustrative examples are drawn from a survey of educators related to the use of the easyCBM learning system. This document includes specific sections on…

Simulator of the NUMAC SRMN module as virtual instrument for the personnel training of the LVNP

International Nuclear Information System (INIS)

Rojas S, A.S.; Rivero G, T.; Ruiz E, J.A.

2006-01-01

Inside the training programs of the personnel's of the Laguna Verde Nuclear power station (CNLV) Veracruz, Mexico, is necessary to carry out practices with instruments or electronic equipment contained inside the reactor instrumentation, most of these equipment are in operation and its can be part important of the safety system of the reactor, for what is sometimes impossible to carry out or to modify its operation conditions. The nuclear industry always has offered the improvement of the systems and equipment that compose the nuclear power station. In this context, during the last years, they have been carried out diverse upgrades of the systems in the CNLV, among them they are the dedicated measurement equipment and nuclear control (NUMAC, by its initials in English). It would be desirable to have a support tool that allows the interactive knowledge of these systems elevating by this way the quality of the personnel's preparation. In this work the NUMAC system by means of a virtual instrument, which has the facilities of developing practices and programs of training is presented. The NUMAC (Nuclear Measurement Analysis and Control), its are controllers connected to the SIIP (Integral System of Process Information), of the following types: RWM (Rod Worth Minimizer), LDM (Leak Detection Monitor), ATCU (Automatic TIP Control Unit [TIP: Traversing In-Core Probe]), LCR (Log Count Rate), LRM (Logarithmic Radiation Monitor), PRNM Power Range Neutron Monitor, SRNM (Start-up Range Neutron Monitor). The NUMAC, are instruments for monitoring and control of the reactor whose introduction is relatively recent, these instruments are connected to the SIIP, its are microprocessors similar to the industrial computers, dedicated to measure and to control systems in the plant. By safety, the control is programmed and it is configured locally in each processor and in the workstations of the SIIP, only the acquired information of these devices is presented. This work describes the

Hydrogen Monitoring in Nuclear Power Cycles

International Nuclear Information System (INIS)

Maurer, Heini; Staub, Lukas

2012-09-01

Maintaining constant Hydrogen levels in Nuclear power cycles is always associated with the challenge to determine the same reliably. Grab sample analysis is complicated and costly and online instruments currently known are difficult to maintain, verify and calibrate. Although amperometry has been proven to be the most suitable measuring principle for online instruments, it has never been thoroughly investigated what electrode materials would best perform in terms of measurement drift and regeneration requirements. This paper we will cover the findings of a research program, conducted at the R and D centre of Swan Analytische Instrumente AG in Hinwil Switzerland, aimed to find ideal electrode materials and sensor design to provide the nuclear industry with an enhanced method to determine dissolved hydrogen in nuclear power cycles. (authors)

The program of reactors and nuclear power plants

International Nuclear Information System (INIS)

Calabrese, Carlos R.

2001-01-01

Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined

Mental Models and Programming Aptitude

DEFF Research Database (Denmark)

Caspersen, Michael Edelgaard; Bennedsen, Jens; Larsen, Kasper Dalgaard

2007-01-01

Predicting the success of students participating in introductory programming courses has been an active research area for more than 25 years. Until recently, no variables or tests have had any significant predictive power. However, Dehnadi and Bornat claim to have found a simple test for programm......Predicting the success of students participating in introductory programming courses has been an active research area for more than 25 years. Until recently, no variables or tests have had any significant predictive power. However, Dehnadi and Bornat claim to have found a simple test...... for programming aptitude to cleanly separate programming sheep from non-programming goats. We briefly present their theory and test instrument. We have repeated their test in our local context in order to verify and perhaps generalise their findings, but we could not show that the test predicts students' success...... in our introductory program-ming course. Based on this failure of the test instrument, we discuss various explanations for our differing results and suggest a research method from which it may be possible to generalise local results in this area. Furthermore, we discuss and criticize Dehnadi and Bornat...

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)

Environment for the instruments

International Nuclear Information System (INIS)

Ambro, P.

1992-01-01

A properly conditioned AC power supply is necessary for reliable functioning of instruments. Electric mains power is produced primarily for industry, workshops, lighting and household uses. Its quality is adjusted to these uses. In areas sand countries with a fast growing demand for electric power, these requirements are far from being met. Electronic instruments and computers, especially in these countries, need protection against disturbances of the mains supply. A clean and dry environment is needed for reliable functioning and long life of instruments. High humidity, specially at higher temperatures, changes the characteristics of electronic components. Moreover, under these conditions fungal growth causes leakage of currents and corrosion causes poor contacts. The presence of dust enhances these effects. They give rise to malfunction of instruments, particularly of high voltage equipment

Environment for the instruments

Energy Technology Data Exchange (ETDEWEB)

Ambro, P

1993-12-31

A properly conditioned AC power supply is necessary for reliable functioning of instruments. Electric mains power is produced primarily for industry, workshops, lighting and household uses. Its quality is adjusted to these uses. In areas sand countries with a fast growing demand for electric power, these requirements are far from being met. Electronic instruments and computers, especially in these countries, need protection against disturbances of the mains supply. A clean and dry environment is needed for reliable functioning and long life of instruments. High humidity, specially at higher temperatures, changes the characteristics of electronic components. Moreover, under these conditions fungal growth causes leakage of currents and corrosion causes poor contacts. The presence of dust enhances these effects. They give rise to malfunction of instruments, particularly of high voltage equipment

Suggestions for an updated fusion power program

International Nuclear Information System (INIS)

Clarke, J.F.

1976-02-01

This document contains suggestions for a revised CTR Program strategy which should allow us to achieve equivalent goals while operating within the above constraints. The revised program is designed around three major facilities. The first is an upgrading of the present TFTR facility which will provide a demonstration of the generation of tens of megawatts electric equivalent originally envisioned for the 1985 EPR. The second device is the TTAP which will allow the integration and optimization of the plasma physics results obtained from the next generation of plasma physics experiments. The improvement in tokamak reactor operation resulting from this optimization of fusion plasma performance will enable an EPR to be designed which will produce several hundred megawatts of electric power by 1990. This will move the fusion program much closer to its goal of commercial fusion power by the turn of the century. In addition to this function the TTAP will serve as a prototype of the 1990 EPR system, thus making more certain the successful operation of this device. The third element of this revised program is an intense radiation damage facility which will provide the radiation damage information necessary for the EPR and subsequent fusion reactor facilities. The sum total of experience gained from reacting plasma experiments on TFTR, reactor grade plasma optimization and technological prototyping on TTAP, and end of life radiation damage results from the intense neutron facility will solve all of the presently foreseen problems associated with a tokamak fusion power reactor except those associated with the external nuclear systems. These external system problems such as tritium breeding and optimal power recovery can be developed in parallel on the 1990 EPR

Advanced optical diagnostics for a coal-fired MHD retrofit of an existing power station

International Nuclear Information System (INIS)

Shepard, W.S.; Cook, R.L.

1990-01-01

The retrofit concept involves integrating a magnetohydrodynamic (MHD) power generation facility with an existing commercial steam power plant. The MHD power train will be 250 MW t and represents a 5:1 scale-up of existing developmental, proof-of-concept (POC) facilities. The program provides a cost effective way to demonstrate the effectiveness, reliability, and operability of the technology and a basis for future commercialization. An aspect of the program must be to accumulate information on component performance and scale-up relations to enable a smooth transition to commercial plant designs. Special state-of-the-art optical diagnostic instrumentation systems are required for this modern energy conversion technology. In-situ measurements with such systems provide a clearer understanding of the processes involved in the ash/seed-laden MHD gas stream, fundamental scale-up data, performance monitors, and a basis for improved control strategies and control instruments. The types of instrumentation, the measurement locations and frequency, and the benefits for the retrofit program are discussed

Tritium instrumentation for a fusion reactor power plant

International Nuclear Information System (INIS)

Shank, K.E.; Easterly, C.E.

1976-09-01

A review of tritium instrumentation is presented. This includes a discussion of currently available in-plant instrumentation and methods required for sampling stacks, monitoring process streams and reactor coolants, analyzing occupational work areas for air and surface contamination, and personnel monitoring. Off-site instrumentation and collection techniques are also presented. Conclusions are made concerning the adequacy of existing instrumentation in relation to the monitoring needs for fusion reactors

Startup program after SGR and power increase

International Nuclear Information System (INIS)

Krajnc, B.; Dudas, M.; Spiler, J.; Novsak, M.

2000-01-01

NPP Krsko replaced steam generators during the outage 2000. Parallel with the steam generator replacement all required systems modifications to accommodate new steam generators into the existing plant (upper feed,..) and support plant power increase of 6.3%, have been implemented. During the years 1997 - 2000 all the required licensing, technical analyses and systems verifications to support such plant changes have been completed. One of the activities within this effort was also the preparation of a detailed Plant Startup Program, which was subject of licensing review and approval process. An integrated plant startup program was then developed based on the plant startup test program, performed regularly during plant startup after refueling and above-mentioned Plant Startup Program. These additional tests defined by the Startup Test Program have been required due to new steam generators, steam generator replacement and related modifications, and power increase from previous 1882 MWt to 2000 MWt. During the preparation period, a startup team was established and procedures were written. All procedures sensitive to the operation were validated on the plant specific simulator. This paper presents more about the Startup Test Program, analysis of its implementation, the results of some key tests as well as the lessons learned. (author)

Nuclear instrument upgrade at Connecticut Yankee Atomic Power Station

International Nuclear Information System (INIS)

Brothers, M.H.; Flynn, B.J.; Shugars, H.G.

1989-01-01

After 20 years of commercial operation, the Connecticut Yankee Atomic Power Station decided to replace the original nuclear instrument system. The plant was motivated primarily by reliability and maintainability problems, the former attributed to equipment wearout and discrete component failure, and the latter to the unavailability of qualified spare parts, another effect of the equipment's age. In replacing the system, the plant also had to address current regulatory, design, and plant technical specification requirements, including physical separation, signal isolation, and changes in equipment qualification. This paper discusses the motivation for the system's replacement, the challenges to the plant engineers and equipment designers, the ways in which the new design met the challenges, the test results of the new system, and other potential benefits supported by the test results

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.

Remote Monitoring of Instrumentation in Sealed Compartments

International Nuclear Information System (INIS)

Landron, Clinton; Moser, John C.

1999-01-01

The Instrumentation and Telemetry Departments at Sandia National Laboratories have been exploring the instrumentation of sealed canisters where the flight application will not tolerate either the presence of a chemical power source or penetration by power supply wires. This paper will describe the application of a low power micro-controller based instrumentation system that uses magnetic coupling for both power and data to support a flight application

Manitoba Hydro's earth power program and Manitoba market update

International Nuclear Information System (INIS)

Pearson, K.

2005-01-01

An outline of Manitoba Hydro's Earth Power program was presented. Details of the heat pump market in Manitoba were provided, including details of residential and commercial sales. Total residential heat pump sales amounted to 577 units in 2004, equivalent to over $11.2 million in sales. Commercial installations amounted to approximately $12.7 million. An outline of industry players was presented. The goals of Manitoba Hydro were outlined in relation to geothermal energy and the Power Smart program. Their objectives included increasing awareness of geothermal energy, making heat pumps more accessible, and improving industry infrastructure. Other objectives included educating the public about life-cycle cost implications, residential loans and commercial incentives. To date, the residential power loan has provided financing to over 300 Manitoba home owners for installations, with electrical savings of over 1.34 Gwh and natural gas savings of 279,425 m 3 . The program is also committed to providing assistance with feasibility studies. Provincial tax credits for the Earth Program included a 10 per cent deduction of geothermal heat pump purchases from corporation income tax. Case studies of the program were presented along with an outline of the geothermal heat pump for homes booklet. Details of the residential earth power loan were provided, including details of installation, system completion and approval processes. Awards and accolades for the program include the 2004 HRAI Education supporter award and recognition by the David Suzuki Foundation, which highlighted the program as a national leader in encouraging and facilitating the use of GeoExchange technology. tabs, figs

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

Department of Defense high power laser program guidance

Science.gov (United States)

Muller, Clifford H.

1994-06-01

The DoD investment of nominally $200 million per year is focused on four high power laser (HPL) concepts: Space-Based Laser (SBL), a Ballistic Missile Defense Organization effort that addresses boost-phase intercept for Theater Missile Defense and National Missile Defense; Airborne Laser (ABL), an Air Force effort that addresses boost-phase intercept for Theater Missile Defense; Ground-Based Laser (GBL), an Air Force effort addressing space control; and Anti-Ship Missile Defense (ASMD), a Navy effort addressing ship-based defense. Each organization is also supporting technology development with the goal of achieving less expensive, brighter, and lighter high power laser systems. These activities represent the building blocks of the DoD program to exploit the compelling characteristics of the high power laser. Even though DoD's HPL program are focused and moderately strong, additional emphasis in a few technical areas could help reduce risk in these programs. In addition, a number of options are available for continuing to use the High-Energy Laser System Test Facility (HELSTF) at White Sands Missile Range. This report provides a brief overview and guidance for the five efforts which comprise the DoD HPL program (SBL, ABL, GBL, ASMD, HELSTF).

Georgia Power Company's college degree program

International Nuclear Information System (INIS)

Coggin, C.L.

1988-01-01

The purpose of this paper is to describe Georgia Power Company's on-site college degree program for nuclear power plant personnel. In February 1986, the US Nuclear Regulatory Commission issued a policy statement concerning engineering expertise on shift (Generic Letter 86-04), which appeared in Volume 50, Number 208 of the October 28, 1985 Federal Register. One of the options available to nuclear power plant personnel to meet the requirement was the combined senior reactor operator/shift technical adviser position. One of the methods for meeting the option included a bachelor's degree in engineering technology for an accredited institution, including course work in the physical, mathematical, or engineering sciences

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.)

The nuclear power public education and information program in the Philippines

International Nuclear Information System (INIS)

Garcia, E.A.; Natera, E.S.

1996-01-01

The nuclear power public education and information program aims to present the beneficial uses of radiation and nuclear energy. Considering that there are pros and cons to the use of nuclear energy, the program aims to give the public an objective and balanced view of this source of energy. A decision to use or not to use nuclear energy, to be sound,must be based on an adequate and objective knowledge of the atom and nuclear energy. Executive Order 243 created the Nuclear Power Steering committee including subcommittee on Nuclear Power Public Education and Information. This subcommittee is tasked to formulate an effective nuclear power public education and information program. Said program must include training component for science teachers in the high school and college levels and shall also work for the inclusion of nuclear related subjects in all engineering curriculum. It shall coordinate with the University of the Philippines for the revival of the M.S. in Nuclear Engineering Program of the university. This paper will discuss a brief history of nuclear power public education and awareness programs and the present and projected activities of this subcommittee. (author)

Overview of government and market driven programs for the promotion of renewable power generation

International Nuclear Information System (INIS)

Ackermann, T.; Andersson, G.; Soeder, L.

2001-01-01

This paper presents and briefly evaluates some existing government instruments and market schemes which support the development of renewable energy generation. The brief evaluation focuses on the incentives provided by the various instruments to reduce production costs. The instruments and schemes are: feed-in tariffs, net metering, bidding process, fixed quotas, green certificate trading, green power exchange, green pricing. (author)

Energy Industry Powers CTE Program

Science.gov (United States)

Khokhar, Amy

2012-01-01

Michael Fields is a recent graduate of Buckeye Union High School in Buckeye, Arizona. Fields is enrolled in the Estrella Mountain Community College (EMCC) Get Into Energy program, which means he is well on his way to a promising career. Specializing in power plant technology, in two years he will earn a certificate that will all but guarantee a…

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

Kryptonate-based instrumentation development for automobile exhaust pollutants. Phase III report: design and construction of four (4) experimental models

International Nuclear Information System (INIS)

Goodman, P.; Donaghue, T.

This phase of the program encompasses the design, construction and evaluation of four (4) prototype instruments for the detection of automobile exhaust pollutant. These instruments employ the radio release mechanism utilized by Panametrics in detection of various trace gases. The prototype instruments are of two (2) designs. One design is operable from a power source supplied by an automobile battery. The second design is operable from 110 volts AC power. Successful evaluation in the laboratory as well as with various automobiles were performed with both type instruments. Scale-up of the quantity of sensor material prepared introduced unexpected problems with respect to detection lifetime which were not satisfactorily resolved within the time and funds available to the program. Nevertheless, a Kryptonate-based instrument using a single detection method for the measurement of hydrocarbons, CO and NO/sub x/ as pollutants by automobile exhausts was shown to be operable with actual automobile exhausts, to provide more than adequate sensitivity for inspection purposes, and to provide response and recovery times for full scale reading in the range 10-15 secs. (auth)

Identification of the Predictive Power of Five Factor Personality Traits for Individual Instrument Performance Anxiety

Science.gov (United States)

Özdemir, Gökhan; Dalkiran, Esra

2017-01-01

This study, with the aim of identifying the predictive power of the five-factor personality traits of music teacher candidates on individual instrument performance anxiety, was designed according to the relational screening model. The study population was students attending the Music Education branch of Fine Arts Education Departments in…

Novel seismic instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Bolleter, W.; Savary, C.

1998-01-01

Conforming to the latest issues of the Nuclear Regulatory Commission Regulatory Guide, a novel hardware and software solution for seismic instrumentation is presented. Both instrumentation and PC-based data evaluation software for post-earthquake actions are type-tested and approved by the German TUeV. Reference installations replacing obsolete analog instrumentation were successfully completed and are presented. The instrumentation consists of highly linear, solid-state capacitive accelerometers as well as digital recorders storing the signals from the sensors in situ. These recorders are linked in a star-topology network to a central unit that permanently communicates with them via fiber-optic cable or current-loop links. The central unit is responsible for alerting and synchronizes all recorders which otherwise act autonomously. Data evaluation is handled by a PC-based software package. It includes automatic data evaluation after earthquakes (batch mode), interactive data evaluation software for detailed data analysis, and software tools for remote operation, maintenance and data storage. (author)

Status of nuclear power programs in South America

International Nuclear Information System (INIS)

Spitalnik, J.

2010-10-01

Analysis of nuclear power plants construction in four South American countries - Argentina, Brazil, Chile and Uruguay - is made based on programs set up by government specialized agencies. In Argentina, in a time-span up to 2023, the nuclear power program considers a five-fold increase of the current installed capacity reaching some 5,000 M We. The Brazilian reference scenario will install additional 4,000 M We, up to 2030, to reach a total installed capacity of about 6,000 M We. Other scenarios could bring this total to some 8,000 - 10,000 M We. Chile and Uruguay have started strategic studies to place the nuclear power option in the future energy matrix of the country. The government of Chile set up, in 2007, a Task Group to determine whether nuclear power could be considered a viable option. This Group concluded that nuclear power is a mature, safe competitive, and low carbon emitter technology that could be considered a viable option. A Nuclear Advisory Group was created who made studies to install a nuclear power plant in the 2016-2021 time-span. In December 2008, the Uruguayan Government created a high level Working Group to establish the feasibility conditions for Nuclear Power Generation in the country. (Author)

Radiation Monitoring - A Key Element in a Nuclear Power Program

International Nuclear Information System (INIS)

Hussein, A.S.; El-dally, T.A.

2008-01-01

For a nuclear power plant, radiation is especially of great concern to the public and the environment. Therefore, a radiation monitoring program is becoming a critical importance. This program covers all phases of the nuclear plant including preoperational, normal operation, accident and decommissioning. The fundamental objective of radiation monitoring program is to ensure that the health and safety of public inside and around the plant and to confirm the radiation doses are below the dose limits for workers and the public. This paper summarizes the environmental radiation monitoring program for a nuclear power plant

Rio Branco, grand strategy and naval power

Directory of Open Access Journals (Sweden)

João Paulo Alsina Jr.

2014-12-01

Full Text Available This article addresses Baron of Rio Branco's grand strategy and the role played by the naval reorganization program (1904-1910 in this context. The ensuing case study determined the domestic and international constraints that affected the program, as well as the worldview of the patron of Brazilian diplomacy regarding military power's instrumentality to foreign policy.

Test program for NIS calibration to reactor thermal output in HTTR

International Nuclear Information System (INIS)

Nakagawa, Shigeaki; Shinozaki, Masayuki; Tachibana, Yukio; Kunitomi, Kazuhiko

2000-03-01

Rise-to-power test program for reactor thermal output measurement has been established to calibrate a neutron instrumentation system taking account of the characteristics of the High Temperature Engineering Test Reactor (HTTR). An error of reactor thermal output measurement was evaluated taking account of a configuration of instrumentation system. And the expected dispersion of measurement in the full power operation was evaluated from non-nuclear heat-up of primary coolant up to 213degC. From the evaluation, it was found that an error of reactor thermal output measurement would be less than ±2.0% at the rated power. This report presents the detailed program of rise-to-power test for reactor thermal output measurement and discusses its measurement error. (author)

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)

Ten Years of Boundary-Layer and Wind-Power Meteorology at Høvsøre, Denmark

DEFF Research Database (Denmark)

Pena Diaz, Alfredo; Floors, Rogier Ralph; Sathe, Ameya

2016-01-01

Operational since 2004, the National Centre for Wind Turbines at Høvsøre, Denmark has become a reference research site for wind-power meteorology. In this study, we review the site, its instrumentation, observations, and main research programs. The programs comprise activities on, inter alia......, remote sensing, where measurements from lidars have been compared extensively with those from traditional instrumentation on masts. In addition, with regard to wind-power meteorology, wind-resource methodologies for wind climate extrapolation have been evaluated and improved. Further, special attention...

Canadian fusion program

International Nuclear Information System (INIS)

Brown, T.S.

1982-06-01

The National Research Council of Canada is establishing a coordinated national program of fusion research and development that is planned to grow to a total annual operating level of about $20 million in 1985. The long-term objective of the program is to put Canadian industry in a position to manufacture sub-systems and components of fusion power reactors. In the near term the program is designed to establish a minimum base of scientific and technical expertise sufficient to make recognized contributions and thereby gain access to the international effort. The Canadian program must be narrowly focussed on a few specializations where Canada has special indigenous skills or technologies. The programs being funded are the Tokamak de Varennes, the Fusion Fuels Technology Project centered on tritium management, and high-power gas laser technology and associated diagnostic instrumentation

A Computer Program for Short Circuit Analysis of Electric Power ...

African Journals Online (AJOL)

The Short Circuit Analysis Program (SCAP) is to be used to assess the composite effects of unbalanced and balanced faults on the overall reliability of electric power system. The program uses the symmetrical components method to compute all phase and sequence quantities for any bus or branch of a given power network ...

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)…

Bibliography of the Maryland Power Plant Research Program, fourteenth edition

International Nuclear Information System (INIS)

McLean, R.I.

1993-02-01

The Power Plant Siting Act of 1971 (Sec. 3-303) established the Power Plant Research Program to ensure that demands for electric power would be met in a timely manner at a reasonable cost while assuring that the associated environmental impact would be acceptable. The scope of the Program extends to estimating the impact of proposed new generating facilities, evaluating the acceptability of proposed transmission line routes, assessing the impact of existing generation facilities, and investigating generic issues related to power plant site evaluation and associated environmental and land use considerations. The bibliography is a compilation of all the studies performed for and/or by the Power Plant and Environmental Review Division since its inception

Systematic evaluation program review of NRC Safety Topic VI-7.3 associated with the electrical, instrumentation and control portions of the ECCS actuation system for the Dresden II Nuclear Power Plant

International Nuclear Information System (INIS)

St Leger-Barter, G.

1980-11-01

This report documents the technical evaluation and review of NRC Safety Topic VI-7.A.3, associated with the electrical, instrumentation, and control portions of the classification of the ECCS actuation system for the Dresden II nuclear power plant, using current licensing criteria

Space Power Program, Instrumentation and Control System Architecture, Pre-conceptual Design, for Information

Energy Technology Data Exchange (ETDEWEB)

JM Ross

2005-10-20

The purpose of this letter is to forward the Prometheus preconceptual Instrumentation and Control (I&C) system architecture (Enclosure (1)) to NR for information as part of the Prometheus closeout work. The preconceptual 1&C system architecture was considered a key planning document for development of the I&C system for Project Prometheus. This architecture was intended to set the technical approach for the entire I&C system. It defines interfaces to other spacecraft systems, defines hardware blocks for future development, and provides a basis for accurate cost and schedule estimates. Since the system requirements are not known at this time, it was anticipated that the architecture would evolve as the design of the reactor module was matured.

Worldwide nuclear power

International Nuclear Information System (INIS)

Royen, J.

1981-01-01

Worldwide nuclear power (WNP) is a companion volume to UPDATE. Our objective in the publication of WNP is to provide factual information on nuclear power programs and policies in foreign countries to U.S. policymakers in the Federal Government who are instrumental in defining the direction of nuclear power in the U.S. WNP is prepared by the Office of the Assistant Secretary for Nuclear Energy from reports obtained from foreign Embassies in Washington, U.S. Embassies overseas, foreign and domestic publications, participation in international studies, and personal communications. Domestic nuclear data is included only where its presence is needed to provide easy and immediate comparisons with foreign data

Instrument setpoints and data gathering techniques

International Nuclear Information System (INIS)

Leong, J.L.; Ornellas, R.P.; Atkinson, J.L.; Gross, R.S.

1994-01-01

Setpoint calculation project sizes vary greatly depending upon the level of effort required and can generally be classified as small or large depending on the number of setpoint calculations required. Small projects usually consist of new system upgrades, power uprates, and the utility's response to industry wide issues and concerns, and require between 10 and 120 setpoint calculations. Large projects usually involve design basis reconstitutions and the complete recalculating of all setpoints prioritized on system or safety related bases. Both large and small project schedules are usually directly tied to Nuclear Regulatory Commission (NRC) commitment dates and it is not uncommon for a large project to take 2 to 3 years to complete. Setpoint calculation projects have historically been performed by the brute force technique employing a variety of methodologies. The brute force technique typically employed today involves putting together a project team large enough to perform all the scheduled setpoint calculations. Setpoint calculations vary in size and complexity and, therefore, may require a wide range of man-hours of a qualified instrument setpoint engineer's time to perform instrument input data retrieval, resolve conflicting input data values, and complete the calculation. The actual time to perform the setpoint calculation using a computer program to calculate results is relatively small in comparison with the time required for data collection and the preparation of supporting documentation. Three major issues have traditionally plagued setpoint calculation projects: data collection; methodology; and incomplete and inconsistent calculations. These traditional problems are addressed and an innovative solution to performing instrument setpoint calculation projects is presented. Through the use of the POWRTRAK database and powerful computer software programs, a new solution to an old and persistent industry challenge is established

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)

Apollo experience report: Development flight instrumentation. [telemetry equipment for space flight test program

Science.gov (United States)

Farmer, N. B.

1974-01-01

Development flight instrumentation was delivered for 25 Apollo vehicles as Government-furnished equipment. The problems and philosophies of an activity that was concerned with supplying telemetry equipment to a space-flight test program are discussed. Equipment delivery dates, system-design details, and flight-performance information for each mission also are included.

Program change management during nuclear power plant decommissioning

International Nuclear Information System (INIS)

Bushart, Sean; Kim, Karen; Naughton, Michael

2011-01-01

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

Survey of the state-of-the-art in aging of electronics with application to nuclear-power-plant instrumentation

International Nuclear Information System (INIS)

Johnson, R.T. Jr.; Thome, F.V.; Craft, C.M.

1983-04-01

The purpose of this report is to present results of a study to evaluate the state-of-the-art and outline needed research on aging of electronics in nuclear power plants. The emphasis is on aging of electronics (e.g., semiconductors, capacitors, resistors) used in safety-related Class 1E instrumentation, particularly those used in harsh environments. Some attention is also given to encapsulants, printed circuit boards and bonds (e.g., solder joints) since they are integral parts of circuits. Four major tasks were addressed in this study and are the subject of this report. These include (1) selecting candidate electronic components for study and review; (2) defining the aging environment and initiating an effort to determine the state-of-the-art in aging degradation; (3) recommending follow-on investigations and research; and (4) outlining the first steps in defining a program on accelerated aging

Excel 2013 power programming with VBA

CERN Document Server

Walkenbach, John

2013-01-01

Maximize your Excel 2013 experience using VBA application development The new Excel 2013 boasts updated features, enhanced power, and new capabilities. Naturally, that means John Walkenbach returns with a new edition of his bestselling VBA Programming book and covers all the methods and tools you need to know in order to program with Excel. With this comprehensive guide, ""Mr. Spreadsheet"" shows you how to maximize your Excel experience using professional spreadsheet application development tips from his own personal bookshelf. Featuring a complete introduction to Visual Basic f

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

Pulse Power--A Heart Physiology Program for Children.

Science.gov (United States)

Hinson, Curt

1994-01-01

Primary grade students at a Delaware elementary school currently participate in the Pulse Power heart physiology program. Students receive mastery instruction and use heart monitors to exercise performance throughout the 6-phase program. Data from homework and from the heart monitors identify student progress, knowledge, and cardiovascular…

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

International Nuclear Information System (INIS)

Bauer, K.G.

1997-01-01

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

Revised inspection program for nuclear power plants

International Nuclear Information System (INIS)

1978-01-01

The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

2015 Key Water Power Program and National Laboratory Accomplishments

Energy Technology Data Exchange (ETDEWEB)

Office of Energy Efficiency and Renewable Energy

2016-01-01

The U.S. Department of Energy Water Power Program is committed to developing and deploying a portfolio of innovative technologies and market solutions for clean, domestic power generation from water resources across the United States.

State program on scientific support of nuclear power development in Belarus

International Nuclear Information System (INIS)

Mikhalevich, A.

2010-01-01

Following the decision on NPP construction in Belarus, the Organization on Technical and Scientific Support of Nuclear Power Development (Joint Institute of Power and Nuclear Research - 'Sosny') has been nominated. In 2009, the Government adopted the State Program on Scientific Support of Nuclear Power Development in the Republic of Belarus for period up to 2020. The paper reviews activities implemented within the framework of this Program. (author)

International and Domestic Development Trends of Electromagnetic Transient Analysis Programs for Power Systems

Science.gov (United States)

Noda, Taku

Nowadays, there is quite high demand for electromagnetic transient (EMT) analysis programs and real-time simulators for power systems. In addition to the conventional demand such as overvoltage, over-current and oscillation simulations, the new demand that includes simulations of power-electronics circuits and power quality is increasing. With this background, development groups of EMT programs and real-time simulators have made progress in terms of computational performance and user experience. In Japan, Central Research Institute of Electric Power Industry has newly developed an EMT analysis program called XTAP (eXpandable Transient Analysis Program). This article overviews these international and domestic development trends of EMT analysis programs and real-time simulators.

Development of multifunctional radiation monitoring instrument based on PLC technology

International Nuclear Information System (INIS)

Li Ziqiang; Zhu Yuye; Zhuang Min

2007-01-01

This eight-channel multifunctional Radiation Monitoring Instrument is developed by making use of the built-in high-speed counters and the powerful instruction system of the SIEMES SIMATICS S7 series Programmable Logic Controllers (PLC) to record and process the pulse signal output by the detectors. The instrument with functions, such as analog and digital display, digital storage of digital data, pulse signal generator, network communication, can connect various types of pulse detectors. The initial process can be translated between Graduation Apparatus method and Formula method. the logicality of the high-dosage warning system is processed itself. The signal output will drive the alarm lights and bell directly. This paper mainly describes the configuration, programming and feature of the instrument. (authors)

Thermal neutron measurement using the instrumented test bundle and assessment of maximum linear power in HANARO

Energy Technology Data Exchange (ETDEWEB)

Lee, C. S.; Seo, C. K.; Lee, B. C.; Kim, H. N.; Kang, B. W. [KAERI, Taejon (Korea, Republic of)

2000-10-01

The HANARO fuel, U{sub 3}Si-Al, has been developed by AECL and tested in NRU reactor. Due to the lack of the data performed under the high power, the repetitive conduct of the irradiation test was required under the power greater than 108kW/m, which is the estimated maximum linear power in the design stage. Accordingly, the instrumented test bundle with SPND(Self Powered Neutron Detector) was fabricated and its irradiation test was performed in IR2 of HANARO. The measured thermal neutron flux with SPND is compared with calculation results by HANAFMS(HANARO Fuel Management System). The difference in the measured and calculated thermal flux values are below {+-}11% and the accuracy of the linear power predicted by HANAFMS is consequently accompanied. Therefore, it is believed that the maximum linear power above 120kW/m is achieved during the irradiation test of the test bundle.

First results of Chinese particle instruments in the Double Star Program

Directory of Open Access Journals (Sweden)

J. B. Cao

2005-11-01

Full Text Available Double Star Program (DSP aims to investigate the trigger mechanism and physical models of geomagnetic storms and substorms. The DSP involves two satellites: the equatorial satellite of DSP (TC-1 in China and the polar satellite of DSP (TC-2 in China. On board the two satellites of TC-1 and TC-2, there are four kinds of particle instruments developed by the Center for Space Science and Applied Research (CSSAR, namely: the High Energy Electron Detector (HEED, TC-1, 2, the High Energy Proton Detector (HEPD, TC-1, 2, the High Energy Heavy Ion Detector (HID, TC-1, 2 and the Low Energy Ion Detector (LEID, TC-2. HEED, HEPD and HID were developed and calibrated in China. The LEID was developed in China and calibrated in France. This paper introduces the scientific objectives and characteristics of each instrument, their status and some preliminary results.

Trace Gas Retrievals from the GeoTASO Aircraft Instrument

Science.gov (United States)

Nowlan, C. R.; Liu, X.; Leitch, J. W.; Liu, C.; Gonzalez Abad, G.; Chance, K.; Cole, J.; Delker, T.; Good, W. S.; Murcray, F.; Ruppert, L.; Soo, D.; Loughner, C.; Follette-Cook, M. B.; Janz, S. J.; Kowalewski, M. G.; Pickering, K. E.; Zoogman, P.; Al-Saadi, J. A.

2015-12-01

The Geostationary Trace gas and Aerosol Sensor Optimization (GeoTASO) instrument is a passive remote sensing instrument capable of making 2-D measurements of trace gases and aerosols from aircraft. The instrument measures backscattered UV and visible radiation, allowing the retrieval of trace gas amounts below the aircraft at horizontal resolutions on the order of 250 m x 250 m. GeoTASO was originally developed under NASA's Instrument Incubator Program as a test-bed instrument for the Geostationary Coastal and Air Pollution Events (GEO-CAPE) decadal survey mission, and is now also part of risk reduction for the upcoming Tropospheric Emissions: Monitoring of Pollution (TEMPO) and Geostationary Environment Monitoring Spectrometer (GEMS) geostationary satellite missions. We present spatially resolved observations of ozone, nitrogen dioxide, formaldehyde and sulfur dioxide over urban areas and power plants from flights during the DISCOVER-AQ field campaigns in Texas and Colorado, as well as comparisons with observations made by ground-based Pandora spectrometers, in situ monitoring instruments and other aircraft instruments deployed during these campaigns. These measurements at various times of day are providing a very useful data set for testing and improving TEMPO and GEMS retrieval algorithms, as well as demonstrating prototype validation strategies.

Dewitt Wallace-Reader's Digest Fund National Library Power Program.

Science.gov (United States)

School Library Media Annual (SLMA), 1993

1993-01-01

Describes the National Library Power Program, a collaborative effort sponsored by the Dewitt Wallace-Reader's Digest Fund in cooperation with local education funds and public school districts that was designed to create public elementary and middle school library programs that are central to the education program of the school. (LRW)

Neutron-multiplication measurement instrument

Energy Technology Data Exchange (ETDEWEB)

Nixon, K.V.; Dowdy, E.J.; France, S.W.; Millegan, D.R.; Robba, A.A.

1982-01-01

The Advanced Nuclear Technology Group of the Los Alamos National Laboratory is now using intelligent data-acquisition and analysis instrumentation for determining the multiplication of nuclear material. Earlier instrumentation, such as the large NIM-crate systems, depended on house power and required additional computation to determine multiplication or to estimate error. The portable, battery-powered multiplication measurement unit, with advanced computational power, acquires data, calculates multiplication, and completes error analysis automatically. Thus, the multiplication is determined easily and an available error estimate enables the user to judge the significance of results.

Neutron multiplication measurement instrument

International Nuclear Information System (INIS)

Nixon, K.V.; Dowdy, E.J.; France, S.W.; Millegan, D.R.; Robba, A.A.

1983-01-01

The Advanced Nuclear Technology Group of the Los Alamos National Laboratory is now using intelligent data-acquisition and analysis instrumentation for determining the multiplication of nuclear material. Earlier instrumentation, such as the large NIM-crate systems, depended on house power and required additional computation to determine multiplication or to estimate error. The portable, battery-powered multiplication measurement unit, with advanced computational power, acquires data, calculates multiplication, and completes error analysis automatically. Thus, the multiplication is determined easily and an available error estimate enables the user to judge the significance of results

Neutron-multiplication measurement instrument

International Nuclear Information System (INIS)

Nixon, K.V.; Dowdy, E.J.; France, S.W.; Millegan, D.R.; Robba, A.A.

1982-01-01

The Advanced Nuclear Technology Group of the Los Alamos National Laboratory is now using intelligent data-acquisition and analysis instrumentation for determining the multiplication of nuclear material. Earlier instrumentation, such as the large NIM-crate systems, depended on house power and required additional computation to determine multiplication or to estimate error. The portable, battery-powered multiplication measurement unit, with advanced computational power, acquires data, calculates multiplication, and completes error analysis automatically. Thus, the multiplication is determined easily and an available error estimate enables the user to judge the significance of results

EPRTM Reactor neutron instrumentation

International Nuclear Information System (INIS)

Pfeiffer, Maxime; SALA, Stephanie

2013-06-01

The core safety during operation is linked, in particular, to the respect of criteria related to the heat generated in fuel rods and to the heat exchange between the rods and the coolant. This local power information is linked to the power distribution in the core. In order to evaluate the core power distribution, the EPR TM reactor relies on several types of neutron detectors: - ionization chambers located outside the vessel and used for protection and monitoring - a fixed in-core instrumentation based on Cobalt Self Powered Neutron Detectors used for protection and monitoring - a mobile reference in-core instrumentation based on Vanadium aero-balls This document provides a description of this instrumentation and its use in core protection, limitation, monitoring and control functions. In particular, a description of the detectors and the principles of their signal generation is supplied as well as the description of the treatments related to these detectors in the EPR TM reactor I and C systems (including periodical calibration). (authors)

Troubleshooting in nuclear instruments

International Nuclear Information System (INIS)

1987-06-01

This report on troubleshooting of nuclear instruments is the product of several scientists and engineers, who are closely associated with nuclear instrumentation and with the IAEA activities in the field. The text covers the following topics: Preamplifiers, amplifiers, scalers, timers, ratemeters, multichannel analyzers, dedicated instruments, tools, instruments, accessories, components, skills, interfaces, power supplies, preventive maintenance, troubleshooting in systems, radiation detectors. The troubleshooting and repair of instruments is illustrated by some real examples

Air Force electrochemical power research and technology program for space applications

Science.gov (United States)

Allen, Douglas

1987-01-01

An overview is presented of the existing Air Force electrochemical power, battery, and fuel cell programs for space application. Present thrusts are described along with anticipated technology availability dates. Critical problems to be solved before system applications occur are highlighted. Areas of needed performance improvement of batteries and fuel cells presently used are outlined including target dates for key demonstrations of advanced technology. Anticipated performance and current schedules for present technology programs are reviewed. Programs that support conventional military satellite power systems and special high power applications are reviewed. Battery types include bipolar lead-acid, nickel-cadmium, silver-zinc, nickel-hydrogen, sodium-sulfur, and some candidate advanced couples. Fuel cells for pulsed and transportation power applications are discussed as are some candidate advanced regenerative concepts.

Technical Training seminar: Texas Instruments

CERN Multimedia

2006-01-01

Monday 6 November TECHNICAL TRAINING SEMINAR 14:00 to 17:30 - Training Centre Auditorium (bldg. 593) Texas Instruments Technical Seminar Michael Scholtholt, Field Application Engineer / TEXAS INSTRUMENTS (US, D, CH) POWER - A short approach to Texas Instruments power products Voltage mode vs. current mode control Differentiating DC/DC converters by analyzing control and compensation schemes: line / load regulation, transient response, BOM, board space, ease-of-use Introduction to the SWIFT software FPGA + CPLD power solutions WIRELESS / CHIPCON Decision criteria when choosing a RF platform Introduction to Texas Instruments wireless products: standardized platforms proprietary platforms ( 2.4 GHz / sub 1 GHz) development tools Antenna design: example for 2.4 GHz questions, discussion Industrial partners: Robert Medioni, François Caloz / Spoerle Electronic, CH-1440 Montagny (VD), Switzerland Phone: +41 24 447 0137, email: RMedioni@spoerle.com, http://www.spoerle.com Language: English. Free s...

Experimental development of power reactor intelligent control

International Nuclear Information System (INIS)

Edwards, R.M.; Garcia, H.E.; Lee, K.Y.

1992-01-01

The US nuclear utility industry initiated an ambitious program to modernize the control systems at a minimum of ten existing nuclear power plants by the year 2000. That program addresses urgent needs to replace obsolete instrumentation and analog controls with highly reliable state-of-the-art computer-based digital systems. Large increases in functionality that could theoretically be achieved in a distributed digital control system are not an initial priority in the industry program but could be logically considered in later phases. This paper discusses the initial development of an experimental sequence for developing, testing, and verifying intelligent fault-accommodating control for commercial nuclear power plant application. The sequence includes an ultra-safe university research reactor (TRIGA) and a passively safe experimental power plant (Experimental Breeder Reactor 2)

Nuclear Power Reactor simulator - based training program

International Nuclear Information System (INIS)

Abdelwahab, S.A.S.

2009-01-01

nuclear power stations will continue playing a major role as an energy source for electric generation and heat production in the world. in this paper, a nuclear power reactor simulator- based training program will be presented . this program is designed to aid in training of the reactor operators about the principles of operation of the plant. also it could help the researchers and the designers to analyze and to estimate the performance of the nuclear reactors and facilitate further studies for selection of the proper controller and its optimization process as it is difficult and time consuming to do all experiments in the real nuclear environment.this program is written in MATLAB code as MATLAB software provides sophisticated tools comparable to those in other software such as visual basic for the creation of graphical user interface (GUI). moreover MATLAB is available for all major operating systems. the used SIMULINK reactor model for the nuclear reactor can be used to model different types by adopting appropriate parameters. the model of each component of the reactor is based on physical laws rather than the use of look up tables or curve fitting.this simulation based training program will improve acquisition and retention knowledge also trainee will learn faster and will have better attitude

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

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

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)

Effects of interruptible load program on equilibrium outcomes of electricity markets with wind power

Energy Technology Data Exchange (ETDEWEB)

An, Xuena; Zhang, Shaohua; Li, Xue [Shanghai Univ. (China). Key Lab. of Power Station Automation Technology

2013-07-01

High wind power penetration presents a lot of challenges to the flexibility and reliability of power system operation. In this environment, various demand response (DR) programs have got much attention. As an effective measure of demand response programs, interruptible load (IL) programs have been widely used in electricity markets. This paper addresses the problem of impacts of the IL programs on the equilibrium outcomes of electricity wholesale markets with wind power. A Cournot equilibrium model of wholesale markets with wind power is presented, in which IL programs is included by a market demand model. The introduction of the IL programs leads to a non-smooth equilibrium problem. To solve this equilibrium problem, a novel solution method is proposed. Numerical examples show that IL programs can lower market price and its volatility significantly, facilitate the integration of wind power.

U.S. Department of Energy University Reactor Instrumentation Program Final Report for 1992-94 Grant for the University of Florida Training Reactor

International Nuclear Information System (INIS)

Vernetson, William G.

1999-01-01

Overall, the instrumentation obtained under the first year 1992-93 University Reactor Instrumentation Program grant assured that the goals of the program were well understood and met as well as possible at the level of support provided for the University of Florida Training Reactor facility. Though the initial grant support of $21,000 provided toward the purchase of $23,865 of proposed instrumentation certainly did not meet many of the facility's needs, the instrumentation items obtained and implemented did meet some critical needs and hence the goals of the Program to support modernization and improvement of reactor facilities such as the UFTR within the academic community. Similarly, the instrumentation obtained under the second year 1993-94 University Reactor Instrumentation Program grant again met some of the critical needs for instrumentation support at the UFTR facility. Again, though the grant support of $32,799 for proposed instrumentation at the same cost projection does not need all of the facility's needs, it does assure continued facility viability and improvement in operations. Certainly, reduction of forced unavailability of the reactor is the most obvious achievement of the University Reactor Instrumentation Program to date at the UFTR. Nevertheless, the ability to close out several expressed-inspection concerns of the Nuclear Regulatory Commission with acquisition of the low level survey meter and the area radiation monitoring system is also very important. Most importantly, with modest cost sharing the facility has been able to continue and even accelerate the improvement and modernization of a facility, especially in the Neutron Activation Analysis Laboratory, that is used by nearly every post-secondary school in the State of Florida and several in other states, by dozens of departments within the University of Florida, and by several dozen high schools around the State of Florida on a regular basis. Better, more reliable service to such a broad

Designing new guides and instruments using McStas

CERN Document Server

Farhi, E; Wildes, A R; Ghosh, R; Lefmann, K

2002-01-01

With the increasing complexity of modern neutron-scattering instruments, the need for powerful tools to optimize their geometry and physical performances (flux, resolution, divergence, etc.) has become essential. As the usual analytical methods reach their limit of validity in the description of fine effects, the use of Monte Carlo simulations, which can handle these latter, has become widespread. The McStas program was developed at Riso National Laboratory in order to provide neutron scattering instrument scientists with an efficient and flexible tool for building Monte Carlo simulations of guides, neutron optics and instruments. To date, the McStas package has been extensively used at the Institut Laue-Langevin, Grenoble, France, for various studies including cold and thermal guides with ballistic geometry, diffractometers, triple-axis, backscattering and time-of-flight spectrometers. In this paper, we present some simulation results concerning different guide geometries that may be used in the future at th...

Mastering C pointers tools for programming power

CERN Document Server

Traister, Robert J

2014-01-01

If you don't fully understand C pointers and how they are used, you're not getting the most out of C programming. This book features complete coverage on using and controlling C language pointers to make C applications more powerful and expressive. This new edition is completely updated and revised to reflect the changes that have been brought about with the full adoption of ANSI C. All discussions and program examples have been updated, and reading materials necessary for any modern ANSI C programmer have also been added.Includes one 3 1/2"" disk containing all of the working programs and m

Coal Power Systems strategic multi-year program plans

Energy Technology Data Exchange (ETDEWEB)

None

2001-02-01

The Department of Energy's (DOE) Office of Fossil Energy (FE), through the Coal and Power Systems (C and PS) program, funds research to advance the scientific knowledge needed to provide new and improved energy technologies; to eliminate any detrimental environmental effects of energy production and use; and to maintain US leadership in promoting the effective use of US power technologies on an international scale. Further, the C and PS program facilitates the effective deployment of these technologies to maximize their benefits to the Nation. The following Strategic Plan describes how the C and PS program intends to meet the challenges of the National Energy Strategy to: (1) enhance American's energy security; (2) improve the environmental acceptability of energy production and use; (3) increase the competitiveness and reliability of US energy systems; and (4) ensure a robust US energy future. It is a plan based on the consensus of experts and managers from FE's program offices and the National Energy Technology Laboratory (NETL).

Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

Energy Technology Data Exchange (ETDEWEB)

None

1975-03-28

The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

Photovoltaic Power System and Power Distribution Demonstration for the Desert RATS Program

Science.gov (United States)

Colozza, Anthony; Jakupca, Ian; Mintz, Toby; Herlacher, Mike; Hussey, Sam

2012-01-01

A stand alone, mobile photovoltaic power system along with a cable deployment system was designed and constructed to take part in the Desert Research And Technology Studies (RATS) lunar surface human interaction evaluation program at Cinder Lake, Arizona. The power system consisted of a photovoltaic array/battery system. It is capable of providing 1 kW of electrical power. The system outputs were 48 V DC, 110 V AC, and 220 V AC. A cable reel with 200 m of power cable was used to provide power from the trailer to a remote location. The cable reel was installed on a small trailer. The reel was powered to provide low to no tension deployment of the cable. The cable was connected to the 220 V AC output of the power system trailer. The power was then converted back to 110 V AC on the cable deployment trailer for use at the remote site. The Scout lunar rover demonstration vehicle was used to tow the cable trailer and deploy the power cable. This deployment was performed under a number of operational scenarios, manned operation, remote operation and tele-robotically. Once deployed, the cable was used to provide power, from the power system trailer, to run various operational tasks at the remote location.

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

International Nuclear Information System (INIS)

Plas, Y. van der

1990-01-01

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

Impacts of alternative allowance allocation methods under a cap-and-trade program in power sector

International Nuclear Information System (INIS)

Liu Beibei; He Pan; Zhang Bing; Bi Jun

2012-01-01

Emission trading is considered to be a cost-effective environmental economic instrument for pollution control. However, the policy design of an emission trading program has a decisive impact on its performance. Allowance allocation is one of the most important policy design issues in emission trading, not only for equity but also for policy performance. In this research, an artificial market for sulfur dioxide (SO 2 ) emission trading was constructed by applying an agent-based model. The performance of the Jiangsu SO 2 emission trading market was examined under different allowance allocation methods and transaction costs. The results showed that the market efficiency of emission trading would be affected by the allocation methods when the transaction costs are positive. The auction allowance allocation method was more efficient and had the lowest total emission control costs than the other three allocation methods examined. However, the use of this method will require that power plants pay for all of their allowance, and doing so will increase the production costs of power plants. On the other hand, output-based allowance allocation is the second best method. - Highlights: ► The impact of allowance allocation methods is examined for a cap-and-trade program. ► The market efficiency would be distinct when the transaction costs are positive. ► The auction method would have lowest total emission control costs.

Astrobiology Sample Analysis Program (ASAP) for Advanced Life Detection Instrumentation Development and Calibration

Science.gov (United States)

Glavin, Daniel; Brinkerhoff, Will; Dworkin, Jason; Eigenbrode, Jennifer; Franz, Heather; Mahaffy, Paul; Stern, Jen; Blake, Daid; Sandford, Scott; Fries, marc;

IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The majority of instrumentation and control (I and C) equipment in nuclear power plants in the world was designed 30 to over 45 years ago with analog and relay components, and in some cases rudimentary digital technology. Today, most of these plants continue to operate with a substantial amount of this original I and C equipment that is or soon will be obsolete. Much of this equipment is approaching or exceeding its life expectancy, resulting in increasing maintenance efforts to sustain acceptable system performance. Decreasing availability of replacement parts, and the accelerating deterioration of the infrastructure of manufacturers that support analog technology, accentuate the obsolescence problems and cause operation and maintenance (O and M) cost increases. Refurbishments and license extensions mean that a plant must be supported longer, which will increase the obsolescence issues. In addition, the older technology limits the possibilities for adding new beneficial capabilities to the plant systems and interfaces. New technology provides the opportunity to improve plant performance, human system interface (HSI) functionality, and reliability; to enhance operator performance and reliability, and to address difficulties in finding young professionals with education and experience with older analog technology. Finally, there may be changes in regulatory requirements that could necessitate modernization activities. Modernization of I and C systems and components, using digital equipment to address these obsolescence issues and the need to improve plant performance (e.g., increase power output capacity, reliability, and availability) while maintaining high levels of safety, is a current major issue for nuclear power plants throughout the world. A number of nuclear power utilities are committing to major modernization programs. The need for this modernization will accelerate as plants age, obsolescence issues increase, plants receive license renewals, and features

Romanian nuclear power program - status and trends

International Nuclear Information System (INIS)

Chirica, T.; Condu, M.; Stiopol, M.; Bilegan, I. C.; Glodeanu, F.; Popescu, D.

1997-01-01

This paper presents the status and the forecast for the Romanian Nuclear Power Program, as a component of the national strategy of power sector in Romania. The successful commissioning and operation of Cernavoda NPP - Unit 1 consolidated the opinion to go further for completion of Unit 2 to 5 on Cernavoda site. The focus is now on Unit 2, planed to be commissioned in 2001, and on the related projects for radioactive waste treatment and disposal. The Romanian national infrastructure supporting this program is also presented, including the research and development facilities. Romanian nuclear industry represent today one of the most advanced sector in engineering and technology and has the ability to meet the requirements of international codes and standards, proving also excellent quality assurance skills. Romanian nuclear industry has also the capability to compete on third markets, for nuclear projects, together with the traditional suppliers. The conclusion of the paper is that for Romania the nuclear energy is the best solution for future development of power sector, is safe, economic and ethical. Nuclear sector created in Romania new jobs and activities, contributing to the progress of Romanian society. (author). 5 refs

Romanian nuclear power program - status and trends

International Nuclear Information System (INIS)

Chirica, T.; Condu, M.; Bilegan, I.C.; Glodeanu, F.; Popescu, D.

1997-01-01

The paper presents the status and the forecast for the Romanian Nuclear Power Program, as a component of the national strategy of power sector in Romania. The successful commissioning and operation of Cernavoda NPP - Unit 1 consolidated the opinion to go further for completion of Unit 2 to 5 on Cernavoda site. The focus is now on Unit 2, planned to be commissioned in 2001, and on the related projects for radioactive waste treatment and disposal. The Romanian national infrastructure supporting this program is also presented, including the research and development facilities. Romanian nuclear industry represents today one of the most advanced sector in engineering and technology and has the ability to meet the requirements of international codes and standards, proving also excellent quality assurance skills. Romanian nuclear industry has also the capability to compete on third market, for nuclear projects, together with the traditional suppliers. The conclusion of the paper is that for Romania, the nuclear energy is the best solution for future development of power sector, is safe, economic, and ethical. Nuclear sector created in Romania new jobs and activities contributing to the progress of Romanian society. (authors)

Software-Enabled Modular Instrumentation Systems

NARCIS (Netherlands)

Soijer, M.W.

2003-01-01

Like most other types of instrumentation systems, flight test instrumentation is not produced in series; its development is a one-time achievement by a test department. With the introduction of powerful digital computers, instrumentation systems have included data analysis tasks that were previously

Impact of Financing Instruments and Strategies on the Wind Power Production Costs: A Case of Lithuania

Science.gov (United States)

Bobinaite, V.; Konstantinaviciute, I.

2018-04-01

The paper aims at demonstrating the relevance of financing instruments, their terms and financing strategies in relation to the cost of wind power production and the ability of wind power plant (PP) to participate in the electricity market in Lithuania. The extended approach to the Levelized Cost of Energy (LCOE) is applied. The feature of the extended approach lies in considering the lifetime cost and revenue received from the support measures. The research results have substantiated the relevance of financing instruments, their terms and strategies in relation to their impact on the LCOE and competitiveness of wind PP. It has been found that financing of wind PP through the traditional financing instruments (simple shares and bank loans) makes use of venture capital and bonds coming even in the absence of any support. It has been estimated that strategies consisting of different proportions of hard and soft loans, bonds, own and venture capital result in the average LCOE of 5.1-5.7 EURct/kWh (2000 kW), when the expected electricity selling price is 5.4 EURct/kWh. The financing strategies with higher shares of equity could impact by around 6 % higher LCOE compared to the strategies encompassing higher shares of debt. However, seeking to motivate venture capitalists, bond holders or other new financiers entering the wind power sector, support measures (feed-in tariff or investment subsidy) are relevant in case of 250 kW wind PP. It has been estimated that under the unsupported financing strategies, the average LCOE of 250 kW wind PP will be 7.8-8.8 EURct/kWh, but it will reduce by around 50 % if feed-in tariff or 50 % investment subsidy is applied.

76 FR 30147 - Application of the Energy Planning and Management Program Power Marketing Initiative to the...

Science.gov (United States)

2011-05-24

... Management Program Power Marketing Initiative to the Boulder Canyon Project AGENCY: Western Area Power.... SUMMARY: The Western Area Power Administration (Western), a Federal power marketing agency of the..., the Energy Management and Planning Program (Program), and the Conformed General Consolidated Power...

The Mid-Infrared Instrument for the James Webb Space Telescope, II: Design and Build

DEFF Research Database (Denmark)

Wright, G. S.; Wright, David; Goodson, G. B.

2015-01-01

The Mid-InfraRed Instrument (MIRI) on the James Webb Space Telescope (JWST) provides measurements over the wavelength range 5 to 28: 5 µm. MIRI has, within a single "package," four key scientific functions: photometric imaging, coronagraphy, single-source low-spectral resolving power (R similar...... in terms of the "as-built" instrument. It also describes the test program that led to delivery of the tested and calibrated Flight Model to NASA in 2012, and the confirmation after delivery of the key interface requirements....

Code of practice for in-core instrumentation for neutron fluence rate (flux) measurements in power reactors

International Nuclear Information System (INIS)

Anon.

1982-01-01

This standard applies to in-core (on-line) neutron detectors and instrumentation which is designed for safety, information or control purposes. It also applies to components in so far as these components are contained within the primary envelope of the reactor. The detector types usually used are dc ionization chambers and self-powered neutron detectors

75 FR 36659 - Proposed Collection; Comment Request; Brain Power! The NIDA Junior Scientist Program and the...

Science.gov (United States)

2010-06-28

... of the Brain Power! Program's ability to: Increase students' knowledge about the biology of the brain... Request; Brain Power! The NIDA Junior Scientist Program and the Companion Program, Brain Power! Challenge.... Proposed Collection: Title: Brain Power! The NIDA Junior Scientist Program, for grades K-5, and the...

76 FR 23583 - Application of the Energy Planning and Management Program Power Marketing Initiative to the...

Science.gov (United States)

2011-04-27

... Management Program Power Marketing Initiative to the Boulder Canyon Project AGENCY: Western Area Power... Area Power Administration (Western), a Federal power marketing agency of the Department of Energy (DOE), will apply the Energy Planning and Management Program (Program) Power Marketing Initiative (PMI), as...

The summary of the fundamental power development program for fiscal 1981

International Nuclear Information System (INIS)

Murakami, Masami

1982-01-01

The Power Source Development Coordination Council put tentatively the target of starting construction in fiscal 1981 at hydraulic 1,000 MW, thermal 5,000 MW and nuclear 5,000 MW, totaling 11,000 MW. Subsequently, after the coordination among the ministries and agencies concerned, the following development program was formally decided for fiscal 1981: hydraulic power 290 MW at 22 sites, thermal power 5,480 MW at 9 sites and nuclear power 1,980 MW at two sites, totaling 7,750 MW at 33 sites. This is 70 % of the tentative target. Nuclear power generation thus put in the fundamental power development program was: one BWR unit of 825 MW in Maki, Niigata Prefecture (Tohoku Electric), and two PWR units of 579 MW each in Kyowa-Tomari in Hokkaido (Hokkaido Electric). (J.P.N.)

The chinese space program as the image instrument of the great China

Directory of Open Access Journals (Sweden)

Daniel Lemus Delgado

2012-10-01

Full Text Available This article analyzes the Chinese space program and how the bureaucratic elite acts to convert China as a leading nation in international arena. This article assumes that, beyond the scientific advances that space exploration has in multiple fields of knowledge, the support to the space program depicts a way to project a positive image of China. This image is a China rising in the international community. The author discusses how space missions and the discourse around the space program strengthen national pride. Thus, China’s space program projects the image of a Greater China. The article concludes that the space program shows that China is modernizing rapidly and is able to be a world power.

Smart instrumentation development at Los Alamos

International Nuclear Information System (INIS)

Erkkila, B.

1984-01-01

For several years Los Alamos has incorporated microprocessors into instruments to expand the capability of portable survey type equipment. Beginning with portable pulse height analyzers, the developments have expanded to small dedicated instruments which handle the measurement and interpretation of various radiation fields. So far, instruments to measure gamma rays, neutrons, and beta particles have been produced. The computer capability built into these instruments provides significant computational power into the instruments. Capability unheard of a few years ago in small portable instruments is routine today. Large computer-based laboratory measurement systems which required much space and electrical power can now be incorporated in a portable hand-held instrument. The microprocessor developments at Los Alamos are now restricted to radiation monitoring equipment but can be expanded to chemical and biological applications as well. Applications for radiation monitoring equipment and others are discussed

Effects of a School-Based Instrumental Music Program on Verbal and Visual Memory in Primary School Children: A Longitudinal Study

OpenAIRE

Roden, Ingo; Kreutz, Gunter; Bongard, Stephan

2012-01-01

This study examined the effects of a school-based instrumental training program on the development of verbal and visual memory skills in primary school children. Participants either took part in a music program with weekly 45 minutes sessions of instrumental lessons in small groups at school, or they received extended natural science training. A third group of children did not receive additional training. Each child completed verbal and visual memory tests for three times over a period of 18 ...

Kilowatt isotope power system. Phase II plan. Volume I. Phase II program plan

International Nuclear Information System (INIS)

1978-01-01

The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Phase II of the overall 3-phase KIPS program is described. This volume presents a program plan for qualifying the organic Rankine power system for flight test in 1982. The program plan calls for the design and fabrication of the proposed flight power system; conducting a development and a qualification program including both environmental and endurance testing, using an electrical and a radioisotope heat source; planning for flight test and spacecraft integration; and continuing ground demonstration system testing to act as a flight system breadboard and to accumulate life data

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

University role in nuclear power program in developing countries

International Nuclear Information System (INIS)

Notea, A.

1977-01-01

The academic education in nuclear engineering should be considered as a subsystem within the general nuclear program of the country as well as within the educational structure of the university. The academic trained personnel are of major importance as future participants in decisional and planning steps of the program. Hence, the ''production'' of academic manpower in this field should be started at the earliest steps. The nuclear engineering curriculum should be planned in accordance with the objectives stated by the power program and the challenges foreseen. Obviously, the objectives in a developing country are considerably different from those of developed countries highly advanced in the nuclear power field. The paper analyzes possible objectives in a developing country which intends to implement nuclear power program. In view of these objectives curricula planning for the undergraduate and graduate levels are presented and explained. The courses for undergraduates intend to provide basic information to relatively large numbers of students from various faculties, as they are expected to join the program at various constructional stages. Major emphasise is given to graduates as they will act in the cadre of senior engineers and officials of the country. The research works for theses in developed countries may be highly technical, dealing with crumbs of huge development project carried out on national or international level. Such research works are hardly justified in countries not involved in the project. In developing countries the problems to be confronted with are mainly licensing and siting and to much less extent nuclear power technology. Hence the choice of subjects for theses should be coherent with these directions. Obviously, the subjects are bound to the department manpower and budgetary limitations. As a demonstration two fields were analysed under our local constraints and objectives. Subjects suitable for theses are pointed out. The fields dealt

Adaptation and Re-Use of Spacecraft Power System Models for the Constellation Program

Science.gov (United States)

Hojnicki, Jeffrey S.; Kerslake, Thomas W.; Ayres, Mark; Han, Augustina H.; Adamson, Adrian M.

2008-01-01

NASA's Constellation Program is embarking on a new era of space exploration, returning to the Moon and beyond. The Constellation architecture will consist of a number of new spacecraft elements, including the Orion crew exploration vehicle, the Altair lunar lander, and the Ares family of launch vehicles. Each of these new spacecraft elements will need an electric power system, and those power systems will need to be designed to fulfill unique mission objectives and to survive the unique environments encountered on a lunar exploration mission. As with any new spacecraft power system development, preliminary design work will rely heavily on analysis to select the proper power technologies, size the power system components, and predict the system performance throughout the required mission profile. Constellation projects have the advantage of leveraging power system modeling developments from other recent programs such as the International Space Station (ISS) and the Mars Exploration Program. These programs have developed mature power system modeling tools, which can be quickly modified to meet the unique needs of Constellation, and thus provide a rapid capability for detailed power system modeling that otherwise would not exist.

Investment recovery program at Niagara Mohawk Power Corporation

International Nuclear Information System (INIS)

Kotcamp, R.T.

1993-01-01

Niagara Mohawk Power Company's pioneering investment recovery program was initiated in 1984, Its mission is to dispose of company assets classified as obsolete, scrap, surplus, or retired capital equipment that results from company operations or work projects. These assets include items such as scrap wire, pipe, line hardware, transformers, power station equipment, crates of dusty telephone modems and computer monitors, pallets of residential gas and electric meters, a box of toilet paper holders, burned-out light bulbs, chunks of electric cable, brass and copper valves, electric bills from 1952, and a dozen tattered office chairs. It was risky for Niagara Mohawk to commit money to a program that created a scrap company inside a utility and is not the core business. No one regrets the decision to create and expand investment recovery. The program has contributed more than $35,000,000 ($8,140,585 nuclear division) of cash receipts with an additional $5,000,000 of cost avoidance since its inception. The program has credited these dollars back to the operating departments, which has reduced operating costs thereby improving the open-quotes bottom line.close quotes

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

International Nuclear Information System (INIS)

Wakayama, N.

1986-01-01

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

Modeling and prioritizing demand response programs in power markets

International Nuclear Information System (INIS)

Aalami, H.A.; Moghaddam, M. Parsa; Yousefi, G.R.

2010-01-01

One of the responsibilities of power market regulator is setting rules for selecting and prioritizing demand response (DR) programs. There are many different alternatives of DR programs for improving load profile characteristics and achieving customers' satisfaction. Regulator should find the optimal solution which reflects the perspectives of each DR stakeholder. Multi Attribute Decision Making (MADM) is a proper method for handling such optimization problems. In this paper, an extended responsive load economic model is developed. The model is based on price elasticity and customer benefit function. Prioritizing of DR programs can be realized by means of Technique for Order Preference by Similarity to Ideal Solution (TOPSIS) method. Considerations of ISO/utility/customer regarding the weighting of attributes are encountered by entropy method. An Analytical Hierarchy Process (AHP) is used for selecting the most effective DR program. Numerical studies are conducted on the load curve of the Iranian power grid in 2007. (author)

Coal Power Systems strategic multi-year program plans; TOPICAL

International Nuclear Information System (INIS)

None

2001-01-01

The Department of Energy's (DOE) Office of Fossil Energy (FE), through the Coal and Power Systems (C and PS) program, funds research to advance the scientific knowledge needed to provide new and improved energy technologies; to eliminate any detrimental environmental effects of energy production and use; and to maintain US leadership in promoting the effective use of US power technologies on an international scale. Further, the C and PS program facilitates the effective deployment of these technologies to maximize their benefits to the Nation. The following Strategic Plan describes how the C and PS program intends to meet the challenges of the National Energy Strategy to: (1) enhance American's energy security; (2) improve the environmental acceptability of energy production and use; (3) increase the competitiveness and reliability of US energy systems; and (4) ensure a robust US energy future. It is a plan based on the consensus of experts and managers from FE's program offices and the National Energy Technology Laboratory (NETL)

Power ramp tests of MOX fuel rods. HBWR irradiation with the instrument rig, IFA-591

International Nuclear Information System (INIS)

Ozawa, Takayuki; Abe, Tomoyuki

2006-03-01

Plutonium-uranium mixed oxide (MOX) fuel rods of instrumental rig IFA-591 were ramped in HBWR to study the Advanced Thermal Reactor (ATR) MOX fuel behavior during transient operation and to determine a failure threshold of the MOX fuel rods. Eleven segments were base-irradiated in ATR 'FUGEN' up to 18.4 GWd/t. Zirconium liner claddings were adopted for four segments of them. As the results of non-destructive post irradiation examinations (PIEs) after the base-irradiation and before the ramp tests, no remarkable behavior affecting the integrity of fuel assembly and fuel rod was confirmed. All segments to be used for the ramp tests, which consisted of the multi-step ramp tests and the single-step ramp tests, had instrumentations for in-pile measurements of cladding elongation or plenum pressure, and heated up to the maximum linear power of 58.3-68.4 kW/m without failure. The major results of ramp tests are as follows: There is no difference in PCMI behaviors between two type rods of Zry-2 and Zirconium liner claddings from the in-pile measurements of cladding elongation and plenum pressure. The computations of cladding elongation and inner pressure gave slightly lower elongation and pressure than the in-pile measurements during the ramp-test. However, the cladding relaxation during the power hold was in good agreement, and the fission gas release behavior during cooling down could be evaluated by taking into account the relaxation of contact pressure between pellet and cladding. Although the final power during IFA-591 ramp tests reached the higher linear power than the failure threshold power of UO 2 fuel rods, no indication of fuel failure was observed during the ramp tests. The cladding relaxation due to the creep deformation of the MOX pellets at high temperature could be confirmed at the power steps during the multi-ramp test. The fission gas release due to the emancipation from PCMI stress was observed during the power decreasing. The burn-up dependence could be

2014 Water Power Program Peer Review: Hydropower Technologies, Compiled Presentations (Presentation)

Energy Technology Data Exchange (ETDEWEB)

2014-02-01

This document represents a collection of all presentations given during the EERE Wind and Water Power Program's 2014 Hydropower Peer Review. The purpose of the meeting was to evaluate DOE-funded hydropower and marine and hydrokinetic R&D projects for their contribution to the mission and goals of the Water Power Program and to assess progress made against stated objectives.

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)

Bibliography of the Maryland Power Plant Research Program, Thirteenth Edition

International Nuclear Information System (INIS)

McLean, R.I.

1992-02-01

The Power Plant Siting Act of 1971 (Sec. 3-303) established the Power Plant Research Program to insure that demands for electric power would be met in a timely manner at a reasonable cost while assuring that the associated environmental impact would be acceptable. The scope of the Program extends to estimating the impact of proposed new generating facilities, evaluating the acceptability of proposed transmission line routes, assessing the impact of existing generation facilities, and investigating generic issues related to power plant site evaluation and associated environmental and land use considerations. The bibliography is a compilation of all the studies performed for and or by the Power Plant and Environmental Review Division since its inception. Reports published by the Division considered to be of general interest are routinely made available through the National Technical Information Service. Those reports so registered may be identified by the NTIS accession number immediately following the citation in the bibliography

Red Cloud’s War: A Failure to Effectively Coordinate the Instruments of National Power

Science.gov (United States)

2016-06-10

to the campaign and the political climate in the United States in 1868, and was facilitated by the progress of the transcontinental railroad. The...categorizing the instruments of national power that a state or government has at its disposal for the formulation, influence , and execution of its...and economic measures to influence and coerce both state and non-state actors is not new. Thucydides wrote about diplomacy, economics, and military

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

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

International Nuclear Information System (INIS)

Chadha, J.A.; Pachner, J.

1989-06-01

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

A Case Study of an Instrumental Music Program and Its Influence on the Culture of a School

Science.gov (United States)

Womack, Anthony Terence

2017-01-01

The purpose of this case study was to examine how participation in a school-based instrumental music program contributed to the culture of a suburban high school. The questions guiding the research were: (1) How and why are multiple music programs supported by staff, students, parents and the community at this school? (2) What are the benefits of…

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

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

Semi-custom integrated circuit amplifier and level discriminator for nuclear and space instruments

International Nuclear Information System (INIS)

Hahn, S.F.; Cafferty, M.M.

1991-01-01

This paper reports on the development an extra fast current feedback amplifier and a level discriminator employing a dielectrically-isolated bipolar, semi-custom Application Specific Integrated Circuit (ASIC) process. These devices are specifically designed for instruments aboard spacecrafts or in portable packages requiring low power and weight. The amplifier adopts current feedback for a unity-gain bandwidth of 90 MHz while consuming 50 mW. The level discriminator uses a complementary output driver for balanced positive and negative response times. The power consumption of these devices can be programmed by external resistors for optimal speed and power trade-off

Semi-custom integrated circuit amplifier and level discriminator for nuclear and space instruments

International Nuclear Information System (INIS)

Hahn, S.F.; Cafferty, M.M.

1990-01-01

This paper reports an extra fast current feedback amplifier and a level discriminator developed employing a dielectrically isolated bipolar, semi-custom Application Specific Integrated Circuit (ASIC) process. These devices are specifically designed for instruments aboard spacecrafts or in portable packages requiring low power and weight. The amplifier adopts current feedback for a unity- gain bandwidth of 90 MHz while consuming 50 mW. The level discriminator uses a complementary output driver for balanced positive and negative response times. The power consumption of these devices can be programmed by external resistors for optimal speed and power trade-off

76 FR 23795 - Low-Power Television and Translator Upgrade Program: Notice of Final Closing Date

Science.gov (United States)

2011-04-28

.... 110418247-1247-01] Low-Power Television and Translator Upgrade Program: Notice of Final Closing Date AGENCY... receipt of applications for the Low-Power Television and Translator Upgrade Program (Upgrade Program) will... Rules to Establish Rules for Digital Low Power Television, Television Translator, and Television Booster...

Audit program for physical security systems at nuclear power plants

International Nuclear Information System (INIS)

Minichino, C.

1982-01-01

Licensees of nuclear power plants conduct audits of their physical security systems to meet the requirements of 10 CFR 73, Physical Protection of Plants and Materials. Section 73.55, Requirements for physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage, requires that the security programs be reviewed at least every 12 months, that the audit be conducted by individuals independent of both security management and security supervision, and that the audit program review all aspects of the physical security system: hardware, personnel, and operational and maintenance procedures. This report contains information for the Nuclear Regulatory Commission (NRC) and for the licensees of nuclear power reactors who carry out these comprehensive audits. Guidance on the overall management of the audit function includes organizational structure and issues concerning the auditors who perform the review: qualifications, independence, due professional care, and standards. Guidance in the audit program includes purpose and scope of the audit, planning, techniques, post-audit procedures, reporting, and follow-up

The Texts of the Instruments relating to a Project for a Joint Agency-Norwegian Program of Research with the Zero Power Reactor 'NORA'

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-06-22

The text of the Supply Agreement between the Agency and the Governments of Norway and of the United States of America, and the text of the related Project Agreement between the Agency and the Government of Norway concerning an Agency project for cooperation in carrying out a joint program of research in reactor physics with the zero power reactor 'NORA', are reproduced in this document for the information of all Members of the Agency.

The Texts of the Instruments relating to a Project for a Joint Agency-Norwegian Program of Research with the Zero Power Reactor 'NORA'

International Nuclear Information System (INIS)

1961-01-01

The text of the Supply Agreement between the Agency and the Governments of Norway and of the United States of America, and the text of the related Project Agreement between the Agency and the Government of Norway concerning an Agency project for cooperation in carrying out a joint program of research in reactor physics with the zero power reactor 'NORA', are reproduced in this document for the information of all Members of the Agency

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

The Wound CARE Instrument: the process for developing standards for wound management education and programming.

Science.gov (United States)

Orsted, Heather L; Woodbury, M Gail; Stevenson, Kimberly

2012-06-01

This article describes the collaborative process undertaken by the Canadian Association for Enterostomal Therapy and the Canadian Association of Wound Care in an effort to improve the quality of wound prevention and management education and programming. The end result of this process is the Wound CARE Instrument which promotes an interprofessional, collaborative appraisal process to support the development, adoption or adaption of wound management educational events and programs. © 2011 The Authors. © 2011 Blackwell Publishing Ltd and Medicalhelplines.com Inc.

Bruce Power's nuclear pressure boundary quality assurance program requirements, implementation and transition

International Nuclear Information System (INIS)

Krane, J.C.

2009-01-01

The development of a full scope nuclear pressure boundary quality assurance program in Canada requires extensive knowledge of the structure and detailed requirements of codes and standards published by the Canadian Standards Association (CSA) and American Society of Mechanical Engineers (ASME). Incorporation into company governance documents and implementation of these requirements while managing the transition to more recent revisions of these codes and standards represents a significant challenge for Bruce Power, Canada's largest independent nuclear operator. This paper explores the key developments and innovative changes that are used to ensure successful regulatory compliance and effective implementation of the Bruce Power Pressure Boundary Quality Assurance Program. Challenges and mitigating strategies to sustain this large compliance based program at Bruce Power's 8 unit nuclear power plant site will also be detailed. (author)

Internal Dosimetry for Nuclear Power Program

International Nuclear Information System (INIS)

Wo, Y.M.

2011-01-01

Internal dosimetry which refers to dosage estimation from internal part of an individual body is an important and compulsory component in order to ensure the safety of the personnel involved in operational of a Nuclear Power Program. Radionuclides particle may deposit in the human being through several pathways and release wave and/or particle radiation to irradiate that person and give dose to body until it been excreted or completely decayed from the body. Type of radionuclides of concerning, monitoring program, equipment's and technique used to measure the concentration level of such radionuclides and dose calculation will be discussed in this article along with the role and capability of Malaysian Nuclear Agency. (author)

Safety Evaluation of Kartini Reactor Based on Instrumentation System Design

International Nuclear Information System (INIS)

Tjipta Suhaemi; Djen Djen Dj; Itjeu K; Johnny S; Setyono

2003-01-01

The safety of Kartini reactor has been evaluated based on instrumentation system aspect. The Kartini reactor is designed by BATAN. Design power of the reactor is 250 kW, but it is currently operated at 100 kW. Instrumentation and control system function is to monitor and control the reactor operation. Instrumentation and control system consists of safety system, start-up and automatic power control, and process information system. The linear power channel and logarithmic power channel are used for measuring power. There are 3 types of control rod for controlling the power, i.e. safety rod, shim rod, and regulating rod. The trip and interlock system are used for safety. There are instrumentation equipment used for measuring radiation exposure, flow rate, temperature and conductivity of fluid The system of Kartini reactor has been developed by introducing a process information system, start-up system, and automatic power control. It is concluded that the instrumentation of Kartini reactor has followed the requirement and standard of IAEA. (author)

Atomic absorption instrument functional description

International Nuclear Information System (INIS)

Bystroff, R.I.; Boyle, W.G. Jr.; Barton, G.W. Jr.

1976-01-01

This report describes a proposed system for automating atomic absorption analysis. The system consists of two atomic absorption instruments and an automatic sampler that can be attached to either instrument. A computer program controls the sampling and gathers data. The program then uses the data to perform bookkeeping, data processing, and report writing

The multispectral instrument of the Sentinel2 program

Science.gov (United States)

Cazaubiel, V.; Chorvalli, Vincent; Miesch, Christophe

2017-11-01

The Sentinel-2 program will provide a permanent record of comprehensive data to help inform the agricul-tural sector (utilisation, coverage), forestry industry (population, damage, forest fires), disaster control (management, early warning) and humanitarian relief programmes. Sentinel-2 will also be able to observe natural disasters such as floods, volcanic eruptions, subsidence and landslides. In the Sentinel-2 mission programme, Astrium in Friedrichshafen is responsible for the satellite's system design and platform, as well as for satellite integration and testing. Astrium Toulouse will supply the Multi-Spectral imaging Instrument (MSI), and Astrium Spain will be in charge of the satellite's structure and will produce its thermal equipment and cable harness. The industrial core team also comprises Jena Optronik (Germany), Boostec (France), Sener and GMV (Spain). Sentinel-2 is intended to image the Earth's landmasses from its orbit for at least 7.25 years. In addition, its onboardresources will be designed so that the mission can be prolonged by an extra five years. From 2012 onwards, the 1.1-metric-ton satellite will circle the Earth in a sun-synchronous, polar orbit at an altitude of 786kilometres, fully covering the planet's landmasses in just ten days. The multi-spectral instrument (MSI) will generate optical images in 13 spectral channels in the visible and shortwave infrared range down to a resolution of 10 metres with an image width of 290 kilometres. The instrument is composed of two main parts: • The telescope assembly , combining in one instrument both VNIR and SWIR channels, is mounted on the upper plate of the Bus • The Video and Compression Electronic Units mounted inside the Bus. This telescope is based on a Three Mirror Anastigmat optical concept. This three mirror optical combination is corrected from spherical aberration, coma and astigmatism. It provides a large field of view with very good optical quality. The telescope mirrors and

Space Power Program Semiannual Progress Report for period ending June 30, 1963

Energy Technology Data Exchange (ETDEWEB)

Miller, A. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

1963-10-11

This is a report of progress on the Oak Ridge National Laboratory's research and development program on nuclear power plants for electrical power production in space vehicles. The work is carried out under AEG Reactor Experiments, Fuels, and Materials, and Reactor Component programs. Research and development work is under way on the stainless steel boiling-potassium reactor and the Medium Power Reactor Experiment, boiling alkali metal heat transfer, high-temperature and refractory alloys, fuel material, and space reactor shielding, particularly in connection with SNAP 2, 8, 10, and 50. Many of these OREL efforts are directed toward the development of a specific type of power plant, but they also furnish a significant contribution of scientific and engineering information needed in other programs on advanced SNAP systems. Progress on research and development directly related to the Medium Power Reactor Experiment (MPRE) is presented mostly in Part I of this report. Progress on the MPRE will, in the future, be reported on a quarterly basis. The form of the reporting will alternate from MPRE Quarterly Progress Reports to Space Power Semiannual Progress Reports.

Status of safeguards instrumentation

International Nuclear Information System (INIS)

Higinbotham, W.A.

The International Atomic Energy Agency is performing safeguards at some nuclear power reactors, 50 bulk processing facilities, and 170 research facilities. Its verification activities require the use of instruments to measure nuclear materials and of surveillance instruments to maintain continuity of knowledge of the locations of nuclear materials. Instruments that are in use and under development to measure weight, volume, concentration, and isotopic composition of nuclear materials, and the major surveillance instruments, are described in connection with their uses at representative nuclear facilities. The current status of safeguards instrumentation and the needs for future development are discussed

Application of LabVIEW in SSRF digital power supply development

International Nuclear Information System (INIS)

Tang Junlong; Chen Huanguang; Ke Xinhua; Chinese Academy of Science, Beijing; Xu Ruinian; Li Deming

2007-01-01

During development of the Shanghai Synchrotron Radiation Facility (SSRF) digital power supply, a digital pulse-width modulator (PWM) directly controls the power circuit insulated gate bipolar transistor (IGBT). A program in LabVIEW language has been developed to perform computer control and monitor for the digital PS via serial communication (RS232). The program provides a friendly user interface to the digital PS that makes it easy to observe its behavior and modify its parameters. Another program, also in LabVIEW language, has been developed to test long term stability of the digital power supply and store the experimental data via extremely precise Keithley instrument and computer. The experimental data are stored in an Excel file which can be processed and analyzed in the future. (authors)

Improving the reliability of Class 1E power distribution to instrumentation and control cabinets on nuclear power plants in the USA. Final report

International Nuclear Information System (INIS)

Brennen, M.B.

1995-09-01

This study was conducted to explore nontraditional electric power distribution concepts to improve the reliability of uninterruptible power to vital Instrumentation and Control (I and C) cabinets in future US nuclear power plants. The study incorporated comparative technical and economic evaluations of existing and nontraditional uninterruptible power supply (UPS) concepts. All nontraditional distribution concepts were based on available or already emerging components or semiconductor devices. Another purpose of the study was to reduce the cost and complexity of present power distribution and to lower maintenance, replacement, degradation and fault location requirements. The possible reduction of distribution losses, especially during operation under battery power, was also evaluated. The study indicates that direct current distribution at 48 or 125 Vdc levels would have more than an order of magnitude improvement over the reliability of present alternating current supplies at comparable cost. Furthermore, losses under battery power could be reduced significantly with respect to present distribution losses. An inherent advantage of DC distribution is that power transfer from the failed power bus to an operational bus occurs naturally and instantaneously via two simple and reliable semiconductor diodes. AC distribution, on the other hand, requires complex synchronization, decision making and gated semiconductor switching devices for power bus transfer all of which could be eliminated. Some of the concepts presented may also be applied to make existing vital (Class 1E) uninterruptible power supplies in US nuclear plants more reliable

Instrumentation and control in the Canadian nuclear power program -1989 status

International Nuclear Information System (INIS)

Lepp, R.M.

1990-01-01

Canada currently has 18 CANDU Pressurized Heavy Water Reactors in operation and 4 under construction, for an installed nuclear capacity of 15,500 MWe. Most of the reactors are in the province of Ontario where 50% of the electricity is nuclear generated. Atomic Energy of Canada is developing the CANDU-3, a 450 MWe reactor incorporating the latest available technologies, including distributed control. The three Canadian Utilities with CANDU reactors have made a major commitment to full-scope training simulators. In Canada there is a growing commitment to developing major improvements to the interface between the control systems, the field equipment and the operating staff. The development program underway makes extensive use of information technology, particularly expert systems and interactive media tools. Out of this will come an advanced CANDU control concept that should further improve the reliability and availability of CANDU stations. (author). 3 refs

Absolute measurement of LDR brachytherapy source emitted power: Instrument design and initial measurements.

Science.gov (United States)

Malin, Martha J; Palmer, Benjamin R; DeWerd, Larry A

2016-02-01

Energy-based source strength metrics may find use with model-based dose calculation algorithms, but no instruments exist that can measure the energy emitted from low-dose rate (LDR) sources. This work developed a calorimetric technique for measuring the power emitted from encapsulated low-dose rate, photon-emitting brachytherapy sources. This quantity is called emitted power (EP). The measurement methodology, instrument design and performance, and EP measurements made with the calorimeter are presented in this work. A calorimeter operating with a liquid helium thermal sink was developed to measure EP from LDR brachytherapy sources. The calorimeter employed an electrical substitution technique to determine the power emitted from the source. The calorimeter's performance and thermal system were characterized. EP measurements were made using four (125)I sources with air-kerma strengths ranging from 2.3 to 5.6 U and corresponding EPs of 0.39-0.79 μW, respectively. Three Best Medical 2301 sources and one Oncura 6711 source were measured. EP was also computed by converting measured air-kerma strengths to EPs through Monte Carlo-derived conversion factors. The measured EP and derived EPs were compared to determine the accuracy of the calorimeter measurement technique. The calorimeter had a noise floor of 1-3 nW and a repeatability of 30-60 nW. The calorimeter was stable to within 5 nW over a 12 h measurement window. All measured values agreed with derived EPs to within 10%, with three of the four sources agreeing to within 4%. Calorimeter measurements had uncertainties ranging from 2.6% to 4.5% at the k = 1 level. The values of the derived EPs had uncertainties ranging from 2.9% to 3.6% at the k = 1 level. A calorimeter capable of measuring the EP from LDR sources has been developed and validated for (125)I sources with EPs between 0.43 and 0.79 μW.

Radiation protection instrument 1993

International Nuclear Information System (INIS)

1993-04-01

The Radiation Protection Instrument, 1993 (Legislative Instrument 1559) prescribes the powers and functions of the Radiation Protection Board established under the Ghana Atomic Energy Commission by the Atomic Energy Commission (Amendment) Law, 1993 (P.N.D.C. Law 308). Also included in the Legislative Instrument are schedules on control and use of ionising radiation and radiation sources as well as procedures for notification, licensing and inspection of ionising radiation facilities. (EAA)

Risk management in power generation and trading planning with financial instruments; Risikomanagement fuer Stromerzeugungs- und Handelsunternehmen mit Finanzinstrumenten

Energy Technology Data Exchange (ETDEWEB)

Blaesig, B.; Huebner, M.; Hinueber, G.; Haubrich, H.J. [Technische Hochschule Aachen (Germany). Lehrstuhl und Inst. fuer Elektrische Anlagen und Energiewirtschaft

2006-04-15

Volatile prices in the electric power trade and varying customers' acceptance increasingly set the companies under competitive pressure and cause planning uncertainties on the producer side. In order to justice to the changed requirements in the energy economy, new methods for a systematic risk management must be developed within planning. On the basis of power generation planning and a commercial planning the authors of the contribution under consideration report on the development of a risk management with financial instruments.

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

Modernization of instrumentation and control systems in nuclear power plants. Working materials. Proceedings of a specialists` meeting held in Garching, Germany, 4-7 July 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The Specialists` Meeting on ``Modernization of Instrumentation and Control Systems in Nuclear Power Plants`` was organized by the IAEA (jointly by Division of Nuclear Power and Division of Nuclear Safety) in co-operation with Institute for Safety Technology (ISTec) and held in Garching, Germany from 4 to 7 July 1995 (The Meeting Chairman - Dr. W. Bastl). The meeting brought together experts on power plant operation with experts on application of today`s instrumentation and control technology. In this way, a match was made between those knowing the industry needs and requirements and those knowing the potentials of the technology. Refs, figs and tabs.

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)

78 FR 9936 - Federal Housing Administration (FHA): PowerSaver Home Energy Retrofit Loan Pilot Program...

Science.gov (United States)

2013-02-12

... Administration (FHA): PowerSaver Home Energy Retrofit Loan Pilot Program: Extension of Pilot Program AGENCY...: On March 31, 2011, HUD published a notice that announced HUD's FHA Home Energy Retrofit Loan Pilot Program (Retrofit Pilot Program) known as FHA PowerSaver, which is a pilot program conducted for loans...

VIRUS instrument enclosures

Science.gov (United States)

Prochaska, T.; Allen, R.; Mondrik, N.; Rheault, J. P.; Sauseda, M.; Boster, E.; James, M.; Rodriguez-Patino, M.; Torres, G.; Ham, J.; Cook, E.; Baker, D.; DePoy, Darren L.; Marshall, Jennifer L.; Hill, G. J.; Perry, D.; Savage, R. D.; Good, J. M.; Vattiat, Brian L.

2014-08-01

The Visible Integral-Field Replicable Unit Spectrograph (VIRUS) instrument will be installed at the Hobby-Eberly Telescope† in the near future. The instrument will be housed in two enclosures that are mounted adjacent to the telescope, via the VIRUS Support Structure (VSS). We have designed the enclosures to support and protect the instrument, to enable servicing of the instrument, and to cool the instrument appropriately while not adversely affecting the dome environment. The system uses simple HVAC air handling techniques in conjunction with thermoelectric and standard glycol heat exchangers to provide efficient heat removal. The enclosures also provide power and data transfer to and from each VIRUS unit, liquid nitrogen cooling to the detectors, and environmental monitoring of the instrument and dome environments. In this paper, we describe the design and fabrication of the VIRUS enclosures and their subsystems.

Utilization of logistic computer programs in the power plant piping industry

International Nuclear Information System (INIS)

Motzel, E.

1982-01-01

Starting from the general situation of the power plant piping industry, the utilization of computer programs as well as the specific magnitude of complexity connected with the project realisation, the necessity for using logistic computer programs especially in case of nuclear power plants is explained. The logistic term as well as the logistic data are described. At the example of the nuclear power plant KRB II, Gundremmingen, Block B/C the practical use of such programs is shown. The planning, scheduling and supervision is carried out computer-aided by means of network-technique. The material management, prefabrication, installation including management of certificates for welding and testing activities is planned and controlled by computer programs as well. With the piping systems installed a complete erection work documentation is available which also serves as base for the billing versus the client. The budgeted costs are continuously controlled by means of a cost control program. Summing-up the further development in controlling piping contracts computer-supported is described with regard to software, hardware and the organisation structure. Furthermore the concept of a self-supporting field computer is introduced for the first time. (orig.) [de

A flameless catalytic combustion-based thermoelectric generator for powering electronic instruments on gas pipelines

International Nuclear Information System (INIS)

Xiao, Heng; Qiu, Kuanrong; Gou, Xiaolong; Ou, Qiang

2013-01-01

Highlights: ► MPPT is used to improve the feature that TEG output is sensitive to load variation. ► The improved feature makes TEG suitable to power electronic device on gas pipeline. ► Test shows heat transfer uniformity plays an important role in improving TEG output. ► It can get an optimized TEG by uniformly filling a thermal insulation material. - Abstract: This paper presents a flameless catalytic combustion-based thermoelectric power generator that uses commercial thermoelectric modules. The structure of the thermoelectric generator (TEG) is introduced and the power performance is measured based on a designed circuit system. The open circuit voltage of the TEG is about 7.3 V. The maximum power output can reach up to 6.5 W when the load resistance matches the TEG internal resistance. However, the system output is sensitive to load variation. To improve this characteristic, maximum power point tracking technique is used and results in an open circuit voltage of 13.8 V. The improved characteristic makes the TEG system a good charger to keep the lead acid battery fully charged so as to meet the needs of electronic instruments on gas pipelines. In addition, the combustion features have been investigated based on the temperature measurement. Test results show that the uniformity of combustion heat transfer process and the combustion chamber structure play important roles in improving system power output. It can get an optimized TEG system (maximum power output: 8.3 W) by uniformly filling a thermal insulation material (asbestos) to avoid a non-uniform combustion heat transfer process

NASA's Radioisotope Power Systems Program Overview - A Focus on RPS Users

Science.gov (United States)

Hamley, John A.; McCallum, Peter W.; Sandifer, Carl E., II; Sutliff, Thomas J.; Zakrajsek, June F.

2016-01-01