WorldWideScience

Sample records for monitoring power level

  1. Power monitors: A framework for system-level power estimation using heterogeneous power models

    NARCIS (Netherlands)

    Bansal, N.; Lahiri, K.; Raghunathan, A.; Chakradhar, S.T.

    2005-01-01

    Paper analysis early in the design cycle is critical for the design of low-power systems. With the move to system-level specifications and design methodologies, there has been significant research interest in system-level power estimation. However, as demonstrated in this paper, the addition of

  2. Power levels in office equipment: Measurements of new monitors and personal computers

    International Nuclear Information System (INIS)

    Roberson, Judy A.; Brown, Richard E.; Nordman, Bruce; Webber, Carrie A.; Homan, Gregory H.; Mahajan, Akshay; McWhinney, Marla; Koomey, Jonathan G.

    2002-01-01

    Electronic office equipment has proliferated rapidly over the last twenty years and is projected to continue growing in the future. Efforts to reduce the growth in office equipment energy use have focused on power management to reduce power consumption of electronic devices when not being used for their primary purpose. The EPA ENERGY STAR[registered trademark] program has been instrumental in gaining widespread support for power management in office equipment, and accurate information about the energy used by office equipment in all power levels is important to improving program design and evaluation. This paper presents the results of a field study conducted during 2001 to measure the power levels of new monitors and personal computers. We measured off, on, and low-power levels in about 60 units manufactured since July 2000. The paper summarizes power data collected, explores differences within the sample (e.g., between CRT and LCD monitors), and discusses some issues that arise in m etering office equipment. We also present conclusions to help improve the success of future power management programs.Our findings include a trend among monitor manufacturers to provide a single very low low-power level, and the need to standardize methods for measuring monitor on power, to more accurately estimate the annual energy consumption of office equipment, as well as actual and potential energy savings from power management

  3. Energy Use and Power Levels in New Monitors and Personal Computers; TOPICAL

    International Nuclear Information System (INIS)

    Roberson, Judy A.; Homan, Gregory K.; Mahajan, Akshay; Nordman, Bruce; Webber, Carrie A.; Brown, Richard E.; McWhinney, Marla; Koomey, Jonathan G.

    2002-01-01

    Our research was conducted in support of the EPA ENERGY STAR Office Equipment program, whose goal is to reduce the amount of electricity consumed by office equipment in the U.S. The most energy-efficient models in each office equipment category are eligible for the ENERGY STAR label, which consumers can use to identify and select efficient products. As the efficiency of each category improves over time, the ENERGY STAR criteria need to be revised accordingly. The purpose of this study was to provide reliable data on the energy consumption of the newest personal computers and monitors that the EPA can use to evaluate revisions to current ENERGY STAR criteria as well as to improve the accuracy of ENERGY STAR program savings estimates. We report the results of measuring the power consumption and power management capabilities of a sample of new monitors and computers. These results will be used to improve estimates of program energy savings and carbon emission reductions, and to inform rev isions of the ENERGY STAR criteria for these products. Our sample consists of 35 monitors and 26 computers manufactured between July 2000 and October 2001; it includes cathode ray tube (CRT) and liquid crystal display (LCD) monitors, Macintosh and Intel-architecture computers, desktop and laptop computers, and integrated computer systems, in which power consumption of the computer and monitor cannot be measured separately. For each machine we measured power consumption when off, on, and in each low-power level. We identify trends in and opportunities to reduce power consumption in new personal computers and monitors. Our results include a trend among monitor manufacturers to provide a single very low low-power level, well below the current ENERGY STAR criteria for sleep power consumption. These very low sleep power results mean that energy consumed when monitors are off or in active use has become more important in terms of contribution to the overall unit energy consumption (UEC

  4. A detector for monitoring the onset of cavitation during therapy-level measurements of ultrasonic power

    Energy Technology Data Exchange (ETDEWEB)

    Hodnett, M; Zeqiri, B [National Physical Laboratory, Queens Road, Teddington, Middlesex, TW11 0LW (United Kingdom)

    2004-01-01

    Acoustic cavitation occurring in the water path between a transducer and the target of a radiation force balance can provide a significant source of error during measurements of ultrasonic power. These problems can be particularly acute at physiotherapy levels (>1 W), and low frequencies ({<=} 1 MHz). The cavitating bubbles can absorb and scatter incident ultrasound, leading to an underestimate in the measured power. For these reasons, International Specification standards demand the use of degassed water. This imposes requirements that may actually be difficult to meet, for example, in the case of hospitals. Also, initially degassed water will rapidly re-gas, increasing the likelihood of cavitation occurring. For these reasons, NPL has developed a device that monitors acoustic emissions generated by bubble activity, for detecting the onset of cavitation during power measurements. A commercially available needle hydrophone is used to detect these emissions. The acoustic signals are then monitored using a Cavitation Detector (CD) unit, comprising an analogue electrical filter that may be tuned to detect frequency components generated by cavitating bubbles, and which provides an indication of when the measured level exceeds a pre-defined threshold. This paper describes studies to establish a suitable detection scheme, the principles of operation of the CD unit, and the performance tests carried out with a range of propagation media.

  5. A detector for monitoring the onset of cavitation during therapy-level measurements of ultrasonic power

    International Nuclear Information System (INIS)

    Hodnett, M; Zeqiri, B

    2004-01-01

    Acoustic cavitation occurring in the water path between a transducer and the target of a radiation force balance can provide a significant source of error during measurements of ultrasonic power. These problems can be particularly acute at physiotherapy levels (>1 W), and low frequencies (≤ 1 MHz). The cavitating bubbles can absorb and scatter incident ultrasound, leading to an underestimate in the measured power. For these reasons, International Specification standards demand the use of degassed water. This imposes requirements that may actually be difficult to meet, for example, in the case of hospitals. Also, initially degassed water will rapidly re-gas, increasing the likelihood of cavitation occurring. For these reasons, NPL has developed a device that monitors acoustic emissions generated by bubble activity, for detecting the onset of cavitation during power measurements. A commercially available needle hydrophone is used to detect these emissions. The acoustic signals are then monitored using a Cavitation Detector (CD) unit, comprising an analogue electrical filter that may be tuned to detect frequency components generated by cavitating bubbles, and which provides an indication of when the measured level exceeds a pre-defined threshold. This paper describes studies to establish a suitable detection scheme, the principles of operation of the CD unit, and the performance tests carried out with a range of propagation media

  6. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

    Purpose: To grasp the margin for the limit value of the power distribution peaking factor inside the reactor under operation by using the reactor power distribution monitor. Constitution: The monitor is composed of the 'constant' file, (to store in-reactor power distributions obtained from analysis), TIP and thermocouple, lateral output distribution calibrating apparatus, axial output distribution synthesizer and peaking factor synthesizer. The lateral output distribution calibrating apparatus is used to make calibration by comparing the power distribution obtained from the thermocouples to the power distribution obtained from the TIP, and then to provide the power distribution lateral peaking factors. The axial output distribution synthesizer provides the power distribution axial peaking factors in accordance with the signals from the out-pile neutron flux detector. These axial and lateral power peaking factors are synthesized with high precision in the three-dimensional format and can be monitored at any time. (Kamimura, M.)

  7. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Kono, Shigehiro.

    1990-01-01

    Among a plurality of power monitoring programs in a reactor power monitoring device, rapid response is required for a scram judging program for the power judging processing of scram signals. Therefore, the scram judging program is stored independently from other power monitoring programs, applied with a priority order, and executed in parallel with other programs, to output scram signals when the detected data exceeds a predetermined value. As a result, the capacity required for the scram judging program is reduced and the processing can be conducted in a short period of time. In addition, since high priority is applied to the scram judging program which is divided into a small capacity, it is executed at higher frequency than other programs when they are executed in parallel. That is, since the entire processings for the power monitoring program are repeated in a short cycle, the response speed of the scram signals required for high responsivity can be increased. (N.H.)

  8. 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 ...

  9. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  10. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Sekimizu, Koichi

    1980-01-01

    Purpose: To improve the performance and secure the safety of a nuclear reactor by rapidly computing and display the power density in the nuclear reactor by using a plurality of processors. Constitution: Plant data for a nuclear reactor containing the measured values from a local power monitor LPRM are sent and recorded in a magnetic disc. They are also sent to a core performance computer in which burn-up degree distribution and the like are computed, and the results are sent and recorded in the magnetic disc. A central processors loads programs to each of the processors and applies data recorded in the magnetic disc to each of the processors. Each of the processors computes the corresponding power distribution in four fuel assemblies surrounding the LPRM string by the above information. The central processor compiles the computation results and displays them on a display. In this way, power distribution in the fuel assemblies can rapidly be computed to thereby secure the improvement of the performance and safety of the reactor. (Seki, T.)

  11. Monitoring Your Blood Sugar Level

    Science.gov (United States)

    ... and NutritionHealth Insurance: Understanding What It CoversHigh Homocysteine Level: How It Affects Your Blood VesselsUnderstanding Your Medical ... Health Resources Healthcare Management Monitoring Your Blood Sugar Level Monitoring Your Blood Sugar Level Share Print What ...

  12. Multiple microprocessor based nuclear reactor power monitor

    International Nuclear Information System (INIS)

    Lewis, P.S.; Ethridge, C.D.

    1979-01-01

    The reactor power monitor is a portable multiple-microprocessor controlled data acquisition device being built for the International Atomic Energy Association. Its function is to measure and record the hourly integrated operating thermal power level of a nuclear reactor for the purpose of detecting unannounced plutonium production. The monitor consists of a 3 He proportional neutron detector, a write-only cassette tape drive and control electronics based on two INTEL 8748 microprocessors. The reactor power monitor operates from house power supplied by the plant operator, but has eight hours of battery backup to cover power interruptions. Both the hourly power levels and any line power interruptions are recorded on tape and in memory. Intermediate dumps from the memory to a data terminal or strip chart recorder can be performed without interrupting data collection

  13. Power consumption monitoring using additional monitoring device

    Energy Technology Data Exchange (ETDEWEB)

    Truşcă, M. R. C., E-mail: radu.trusca@itim-cj.ro; Albert, Ş., E-mail: radu.trusca@itim-cj.ro; Tudoran, C., E-mail: radu.trusca@itim-cj.ro; Soran, M. L., E-mail: radu.trusca@itim-cj.ro; Fărcaş, F., E-mail: radu.trusca@itim-cj.ro [National Institute for Research and Development of Isotopic and Molecular Technologies, 65-103 Donath, 400293 Cluj-Napoca (Romania); Abrudean, M. [Technical University of Cluj-Napoca, Cluj-Napoca (Romania)

    2013-11-13

    Today, emphasis is placed on reducing power consumption. Computers are large consumers; therefore it is important to know the total consumption of computing systems. Since their optimal functioning requires quite strict environmental conditions, without much variation in temperature and humidity, reducing energy consumption cannot be made without monitoring environmental parameters. Thus, the present work uses a multifunctional electric meter UPT 210 for power consumption monitoring. Two applications were developed: software which carries meter readings provided by electronic and programming facilitates remote device and a device for temperature monitoring and control. Following temperature variations that occur both in the cooling system, as well as the ambient, can reduce energy consumption. For this purpose, some air conditioning units or some computers are stopped in different time slots. These intervals were set so that the economy is high, but the work's Datacenter is not disturbed.

  14. Reactor Emergency Action Level Monitor

    International Nuclear Information System (INIS)

    Touchton, R.A.

    1987-01-01

    The Reactor Emergency Action Level Monitor (REALM) Expert System is designed to provide assistance in the identification of a nuclear power plant emergency situation and the determination of its severity. REALM has been developed to operate in a real-time processing environment. REALM embodies a hybrid architecture utilizing both rule-based reasoning and object-oriented programming techniques borrowed from the Artificial Intelligence discipline of Computer Sciences. The rulebase consists of event-based rules and symptom-based rules. The symptom-based rules go beyond the current EAL structure to address the more problematic scenarios and entail a more symbolic representation of the plant information. The results to date have been encouraging that expert system technology can provide improved emergency decision-making capability in nuclear power plants

  15. Radiation monitor system for nuclear power plants

    International Nuclear Information System (INIS)

    Wu Bingzhe; Guo Shusheng

    1990-12-01

    The system has 8 kinds of radiation monitors and 2 stage microcomputers designed for processing the data from each monitor, storaging the information, printing out and displaying on the colour CRT. The function of the system includes high-value alarm, warm alarm and failure alarm, so called t hree-level alarms . Two functions of the alarms are the threshold alarm and the tendency alarm, so that this system is an intelligency system. This system has high reliability and very wide range when LOCA accident takes place. It is aseismic and immune to industrial interference. The system can meet IEC-761-1 standard and is of nuclear safety 3rd class. Also the following monitors were designed: 133 Xe monitor, 131 I monitor, low-level liquid monitor and high radiation γ area monitor. The system can meet the requirements of nuclear power plants

  16. 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.)

  17. Supervisory monitoring system in nuclear power plants

    International Nuclear Information System (INIS)

    Ciftcioglu, O.; Turkcan, E.

    1997-01-01

    Monitoring of a power plant is one of the essential tasks during operation and the computer-based implementations are nowadays seemingly quite mature. However, presently these are still not satisfactory enough to meet the high standards to the licensing requirements and they are mostly not truly integrated to the plant's design-based monitoring system. This is basically due to the robustness problem as the majority of the methods are not robust enough for the monitoring of the safety parameter set in a plant or intelligent supervision. Therefore, a supervisory monitoring system (SMS) in a plant is necessary to supervise the monitoring tasks: determining the objectives to be obtained and finding the means to support them. SMS deals with the changing plant status and the coordination of the information flow among the monitoring subunits. By means of these robustness and consistency in monitoring is achieved. The paper will give the guidelines of knowledge and data management techniques in a framework of robust comprehensive and coordinated monitoring which is presented as supervisory monitoring. Such a high level monitoring serves for consistent and immediate actions in fault situations while this particularly has vital importance in preventing imminent severe accidents next to the issues of recognition of the monitoring procedures for licensing and enhanced plant safety. (author). 8 refs, 5 figs

  18. Monitoring of nuclear power stations

    International Nuclear Information System (INIS)

    Ull, E.; Labudda, H.J.

    1987-01-01

    The purpose of the invention is to create a process for undelayed automated detection and monitoring of accidents in the operation of nuclear power stations. According to the invention, this problem is solved by the relevant local measurements, such as radiation dose, components and type of radiation and additional relevant meteorological parameters being collected by means of wellknown data collection platforms, these being transmitted via transmission channels by means of satellites to suitable worldwide situated receiving stations on the ground, being processed there and being evaluated to recognise accidents. The local data collection platforms are used in the immediate vicinity of the nuclear power station. The use of aircraft, ships and balloons as data collection systems is also intended. (HWJ)

  19. CloudMonitor: Profiling Power Usage

    OpenAIRE

    Smith, James William; Khajeh-Hosseini, Ali; Ward, Jonathan Stuart; Sommerville, Ian

    2012-01-01

    In Cloud Computing platforms the addition of hardware monitoring devices to gather power usage data can be impractical or uneconomical due to the large number of machines to be metered. CloudMonitor, a monitoring tool that can generate power models for software-based power estimation, can provide insights to the energy costs of deployments without additional hardware. Accurate power usage data leads to the possibility of Cloud providers creating a separate tariff for power and therefore incen...

  20. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-09-01

    This is the final report on the INSP project entitled, ``Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant.

  1. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    International Nuclear Information System (INIS)

    GREENE, G.A.; GUPPY, J.G.

    1998-01-01

    This is the final report on the INSP project entitled, ''Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant

  2. 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

  3. Technical support to environmental restoration division for groundwater level monitoring effort at entombed Hallam Nuclear Power Facility. Final report, August 1, 1993--July 31, 1993

    International Nuclear Information System (INIS)

    1994-01-01

    This report provides an interim summary of information from a water-level monitoring program. The information was collected by the US Geological Survey (USGS) over a 6-month period. The monitoring program between the US DOE and the USGS was set up to measure water levels in 16 observation wells at the Hallam Nuclear Facility in Hallam, Nebraska. The summary of USGS data includes: (1) a description of the USGS monitoring program; (2) a description of the collection of continuous water-level data; (3) a description of the collection of monthly water-level data; (4) table of observation well number, latitude, longitude, and depth; (5) table of monthly ground-water levels data; (6) table of recorder wells, rainfall, and barometric pressure values; (7) table of recorder well, rainfall, and barometric pressure daily values; and (8) hydrographs of selected wells. 7 figs., 3 tabs

  4. Microprocessor-based accelerating power level detector

    Energy Technology Data Exchange (ETDEWEB)

    Nagpal, M.; Zarecki, W.; Albrecht, J.C.

    1994-01-01

    An accelerating power level detector was built using state-of-the-art microprocessor technology at Powertech Labs Inc. The detector will monitor the real power flowing in two 300 kV transmission lines out of Kemano Hydroelectric Generating Station and will detect any sudden loss of load due to a fault on either line under certain pre-selected power flow conditions. This paper discusses the criteria of operation for the detector and its implementation details, including digital processing, hardware, and software.

  5. 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

  6. Power distribution monitor in a nuclear reactor

    International Nuclear Information System (INIS)

    Uematsu, Hitoshi

    1983-01-01

    Purpose: To enable accurate monitoring for the reactor power distribution within a short time in a case where abnormality occurs in in-core neutron monitors or in a case where the reactor core state changes after the calibration for the neutron monitors. Constitution: The power distribution monitor comprises a power distribution calculator adapted to be inputted counted values from a reactor core present state data instruments and calculate the neutron flux distribution in the reactor core and the power distribution based on previously incorporated physical models, an RCF calculator adapted to be inputted with the counted values from the in-core neutron monitors and the neutron flux distribution and the power distribution calculated in the power distribution calculator and compensate the counted errors included in the counted values form the in-core neutron monitors and the calculation errors included in the power distribution calculated in the power distribution calculator to thereby calculate the power distribution within the reactor core, and an input/output device for the input of the data required for said power distribution calculator and the display for the calculation result calculated in the RCF calculator. (Ikeda, J.)

  7. radio frequency based radio frequency based water level monitor

    African Journals Online (AJOL)

    eobe

    ABSTRACT. This paper elucidates a radio frequency (RF) based transmission and reception system used to remotely monitor and .... range the wireless can cover but in this prototype, it ... power supply to the system, the sensed water level is.

  8. Cluster processing business level monitor

    International Nuclear Information System (INIS)

    Muniz, Francisco J.

    2017-01-01

    This article describes a Cluster Processing Monitor. Several applications with this functionality can be freely found doing a search in the Google machine. However, those applications may offer more features that are needed on the Processing Monitor being proposed. Therefore, making the monitor output evaluation difficult to be understood by the user, at-a-glance. In addition, such monitors may add unnecessary processing cost to the Cluster. For these reasons, a completely new Cluster Processing Monitor module was designed and implemented. In the CDTN, Clusters are broadly used, mainly, in deterministic methods (CFD) and non-deterministic methods (Monte Carlo). (author)

  9. Cluster processing business level monitor

    Energy Technology Data Exchange (ETDEWEB)

    Muniz, Francisco J., E-mail: muniz@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    This article describes a Cluster Processing Monitor. Several applications with this functionality can be freely found doing a search in the Google machine. However, those applications may offer more features that are needed on the Processing Monitor being proposed. Therefore, making the monitor output evaluation difficult to be understood by the user, at-a-glance. In addition, such monitors may add unnecessary processing cost to the Cluster. For these reasons, a completely new Cluster Processing Monitor module was designed and implemented. In the CDTN, Clusters are broadly used, mainly, in deterministic methods (CFD) and non-deterministic methods (Monte Carlo). (author)

  10. Intelligent Component Monitoring for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Tsoukalas, Lefteri

    2010-01-01

    Reliability and economy are two major concerns for a nuclear power generation system. Next generation nuclear power reactors are being developed to be more reliable and economic. An effective and efficient surveillance system can generously contribute toward this goal. Recent progress in computer systems and computational tools has made it necessary and possible to upgrade current surveillance/monitoring strategy for better performance. For example, intelligent computing techniques can be applied to develop algorithm that help people better understand the information collected from sensors and thus reduce human error to a new low level. Incidents incurred from human error in nuclear industry are not rare and have been proven costly. The goal of this project is to develop and test an intelligent prognostics methodology for predicting aging effects impacting long-term performance of nuclear components and systems. The approach is particularly suitable for predicting the performance of nuclear reactor systems which have low failure probabilities (e.g., less than 10 -6 year -1 ). Such components and systems are often perceived as peripheral to the reactor and are left somewhat unattended. That is, even when inspected, if they are not perceived to be causing some immediate problem, they may not be paid due attention. Attention to such systems normally involves long term monitoring and possibly reasoning with multiple features and evidence, requirements that are not best suited for humans.

  11. Development of nuclear power plant Risk Monitor

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  12. Trends of chemical monitoring in power stations

    International Nuclear Information System (INIS)

    Winkler, R.; Venz, H.

    1983-01-01

    Frequently, the state-of-the-art of chemical monitoring in power plants is still determined by conservative methods. A thorough rationalization requires not only modern analytical procedures, but also the consideration of chemically affected processes in complex process analyses and the combination of automatic analyzers with available process computers. Using some examples, ways of reducing monitoring efforts without impairing safety and economy of nuclear power plant operation are pointed out. (author)

  13. Power distribution monitor for nuclear reactor

    International Nuclear Information System (INIS)

    Nishizawa, Yasuo; Kiguchi, Takashi.

    1974-01-01

    Object: To compare the measured local power region monitor (LPRM) index with the result of a primary calculation to correct the threshold condition for the primary calculation thereby to rapidly grasp and monitor the existing power distribution. Structure: The index of an LPRM disposed in a nuclear reactor is processed in a data processor to remove therefrom a noise, and transmitted to a threshold condition processor to be stored therein. The LPRM index measured by the threshold condition processor is compared with the calculated LPRM value transmitted from the primary processor, whereby the threshold condition is corrected and transmitted to the primary processor. After the completion of calculation, the traversing incore probe (TIP) indexing value is converted to a thermal output distribution or a linear output density distribution and transmitted to an output indicator or an output typewriter. The operator may monitor the existing power distribution by monitoring the output indicator. (Kamimura, M.)

  14. Nuclear power: levels of safety

    International Nuclear Information System (INIS)

    Lidsky, L.M.

    1988-01-01

    The rise and fall of the nuclear power industry in the United States is a well-documented story with enough socio-technological conflict to fill dozens of scholarly, and not so scholarly, books. Whatever the reasons for the situation we are now in, and no matter how we apportion the blame, the ultimate choice of whether to use nuclear power in this country is made by the utilities and by the public. Their choices are, finally, based on some form of risk-benefit analysis. Such analysis is done in well-documented and apparently logical form by the utilities and in a rather more inchoate but not necessarily less accurate form by the public. Nuclear power has failed in the United States because both the real and perceived risks outweigh the potential benefits. The national decision not to rely upon nuclear power in its present form is not an irrational one. A wide ranging public balancing of risk and benefit requires a classification of risk which is clear and believable for the public to be able to assess the risks associated with given technological structures. The qualitative four-level safety ladder provides such a framework. Nuclear reactors have been designed which fit clearly and demonstrably into each of the possible qualitative safety levels. Surprisingly, it appears that safer may also mean cheaper. The intellectual and technical prerequisites are in hand for an important national decision. Deployment of a qualitatively different second generation of nuclear reactors can have important benefits for the United States. Surprisingly, it may well be the nuclear establishment itself, with enormous investments of money and pride in the existing nuclear systems, that rejects second generation reactors. It may be that we will not have a second generation of reactors until the first generation of nuclear engineers and nuclear power advocates has retired

  15. Monitoring support system for nuclear power plant

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  16. Remote Working Level Monitor. Final report

    International Nuclear Information System (INIS)

    1977-01-01

    The Remote Working Level Monitor (RWLM) is an instrument used to remotely monitor the RN-daughter concentrations and the Working Level (WL). It is an ac powered, microprocessor based instrument which multiplexes two independent detector units to a single central processor unit (CPU). The CPU controls the actuation of the detector units and processes and outputs the data received from these remote detector units. The remote detector units are fully automated and require no manual operation once they are set up. They detect and separate the alpha emitters of RaA and RaC' as well as detecting the beta emitters of RaB and RaC. The resultant pulses from these detected radioisotopes are transmitted to the CPU for processing. The programmed microprocessor performs the mathematical manipulations necessary to output accurate Rn-daughter concentrations and the WL. A special subroutine within the program enables the RWLM to run and output a calibration procedure on command. The data resulting from this request can then be processed in a separate program on most computers capable of BASIC programming. The calibration program results in the derivation of coefficients and beta efficiencies which provides calibrated coefficients and beta efficiencies

  17. Environmental wodking level monitor. Final report

    International Nuclear Information System (INIS)

    Keefe, D; McDowell, W.P.; Groer, P.G.

    1978-01-01

    The Environmental Working Level Monitor (EWLM) is an instrument used to automatically monitor airborne Rn-daughter concentrations and the Working Level (WL). It is an ac powered, microprocessor--based instrument with an external inverter provided for dc operation if desired. The microprocessor's control processor unit (CPU) controls the actuation of the detector assembly and processes its output signals to yield the measurements in the proper units. The detectors are fully automated and require no manual operations once the instrument is programmed. They detect and separate the alpha emitters of RaA and RaC' as well as detecting the beta emitters of RaB and RaC. The resultant pulses from these detected radioisotopes are transmitted to the CPU. The programmed microprocessor performs the mathematical manipulations necessary to output accurate Rn-daughter concentrations and the WL. A special subroutine within the system program enables the EWLM to run a calibration procedure on command which yields calibration data. This data can then be processed in a separate program on most computers capable of BASIC programming. This calibration program results in the derivation of coefficients and beta efficiencies which provides the calibrated coefficients and beta efficiencies required by the main system program to assure proper calibration of the individual EWLM's

  18. The evolution of industrial power monitoring and control systems

    Energy Technology Data Exchange (ETDEWEB)

    Nicholson, K. E.

    1998-04-01

    The evolution of power monitoring and control systems in industrial situations are described. Computer-based PMC (power monitoring and control) systems are discussed in two sections. Section 1 covers the PC/DOS based systems in use up to the 1990s. These systems had multitasking capability, sufficient for scanning a serial line running a multi-drop protocol to field instruments, which in turn were running either proprietary or PLC subsets, maintaining a level of operator display, data logging and query support. Since the mid-1990s the second generation of industrial power monitoring and control systems based on the PC/NT system came into use, driven to market by three factors: (1) availability of low cost PCs, (2) widespread availability of computer networking technologies, and (3) the appearance of the robust, industrially viable NT operating system. Second generation systems are characterized by division into two tiers; a monitoring system focused on remote metering, and a second tier of a modular system capable of fully implementing both power monitoring and supervisory control. Looking toward the future, the requirements for systems is expected to become more unique, driven by the need for information for energy procurement decision making, automatic control for integrating power acquisition from multiple suppliers, power capacity and integrated power and production control planning needs, and power quality and reliability issues. A review of the functionality of PMC systems, and system architectures was also provided. Results of a survey of PMC systems applications were also discussed. 2 refs., 4 tabs., 8 figs.

  19. Monitoring Biological Activity at Geothermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Peter Pryfogle

    2005-09-01

    The economic impact of microbial growth in geothermal power plants has been estimated to be as high as $500,000 annually for a 100 MWe plant. Many methods are available to monitor biological activity at these facilities; however, very few plants have any on-line monitoring program in place. Metal coupon, selective culturing (MPN), total organic carbon (TOC), adenosine triphosphate (ATP), respirometry, phospholipid fatty acid (PLFA), and denaturing gradient gel electrophoresis (DGGE) characterizations have been conducted using water samples collected from geothermal plants located in California and Utah. In addition, the on-line performance of a commercial electrochemical monitor, the BIoGEORGE?, has been evaluated during extended deployments at geothermal facilities. This report provides a review of these techniques, presents data on their application from laboratory and field studies, and discusses their value in characterizing and monitoring biological activities at geothermal power plants.

  20. The use of BEACON monitoring in plant power uprates

    International Nuclear Information System (INIS)

    Miller, Wade

    2003-01-01

    BEACON is the core support software technology that provides Utilities with continuous 3-D core power distribution monitoring, operational analysis capability, and operations support capability. BEACON monitoring delivers quantifiable plant margins for both reload design and plant operations improvement. When linked to Plant Power Upratings, BEACON permits an improvement in fuel cycle economics through higher peaking factors, higher power levels and higher discharge burnups. Operational flexibility of Uprated Plants is enhanced through elimination of axial power shape and core power tilt specifications. Also, the number of flux maps for these plants is reduced and local power is monitored continuously, permitting faster power escalation. Integrated 3-D power distribution analysis capabilities provide core designers with historical margin data that permits a reduction in core follow requirements as well as reduced curve book data related scope. Examples of specific Uprated Plant applications will be discussed. In anticipation of future needs of Uprated Plants, plans to integrate the technology of BEACON with COLSS are being executed. Finally, the capability to monitor Crud Induced Power Shift (axial offset) is also planned for incorporation into BEACON in the near future and will be discussed

  1. Comparison of power curve monitoring methods

    Directory of Open Access Journals (Sweden)

    Cambron Philippe

    2017-01-01

    Full Text Available Performance monitoring is an important aspect of operating wind farms. This can be done through the power curve monitoring (PCM of wind turbines (WT. In the past years, important work has been conducted on PCM. Various methodologies have been proposed, each one with interesting results. However, it is difficult to compare these methods because they have been developed using their respective data sets. The objective of this actual work is to compare some of the proposed PCM methods using common data sets. The metric used to compare the PCM methods is the time needed to detect a change in the power curve. Two power curve models will be covered to establish the effect the model type has on the monitoring outcomes. Each model was tested with two control charts. Other methodologies and metrics proposed in the literature for power curve monitoring such as areas under the power curve and the use of statistical copulas have also been covered. Results demonstrate that model-based PCM methods are more reliable at the detecting a performance change than other methodologies and that the effectiveness of the control chart depends on the types of shift observed.

  2. Market power mitigation, monitoring and surveillance

    International Nuclear Information System (INIS)

    Chandler, H.

    2001-01-01

    This power point presentation described the working of the Independent Market Operator (IMO) in Ontario in terms of its function and structure, competencies, operating principles, and interagency coordination in the electricity sector. An independent market surveillance panel (MSP) appointed by the IMO Board empowers the IMO to monitor, investigate and request information from market participants regarding power system operations, market and strategic development and industrial economics. The six operating principles of the MSP are efficiency, consistency, fairness, transparency, timeliness and confidentiality

  3. Monitoring device for local power peaking coefficients

    International Nuclear Information System (INIS)

    Mihashi, Ishi

    1987-01-01

    Purpose: To determine and monitor the local power peaking coefficients by a method not depending on the combination of fuel types. Constitution: Representative values for the local power distribution can be obtained by determining corresponding burn-up degrees based on the burn-up degree of each of fuel assembly segments obtained in a power distribution monitor and by the interpolation and extrapolation of void coefficients. The typical values are multiplied with compensation coefficients for the control rod effect and coefficients for compensating the effect of adjacent fuel assemblies in a calculation device to obtain typical values for the present local power distribution compensated with all of the effects. Further, the calculation device compares them with typical values of the present local power distribution to obtain an aimed local power peaking coefficient as the maximum value thereof. According to the present invention, since the local power peaking coefficients can be determined not depending on the combination of the kind of fuels, if the combination of fuel assemblies is increased upon fuel change, the amount of operation therefor is not increased. (Kamimura, M.)

  4. Nuclear Reactor Power Monitoring Using Silicon Carbide Semiconductor Radiation Detectors

    International Nuclear Information System (INIS)

    Thomas Blue; Don Miller

    2008-01-01

    To provide a perspective for our accomplishments, all of the sub-tasks in Task 1 (as they were identified in the proposal) are listed, and a brief description of the subtasks is given. Task 1--Define Generation IV Reactor Power Monitoring Requirements. Task 1.1--The power monitoring requirements for the IRIS and GT-MHR will be evaluated. Parameters considered will include maximum power level uncertainty, response time, etc. Task 1.2--The optimum locations for power monitors will be selected for both the IRIS and GT-MHR. Factors to be considered will include the power monitoring requirements defined in Task 1.1 as well as expected detector sensitivity and the presence of gamma ray background. Task 1.3--Other applications and opportunities offered by SiC power monitors will be evaluated. The prospects for on-line fault identification and diagnosis using pulse height and pulse shape analysis will be explored. The use of miniature SiC detectors to define axial, azimuthal, and radial flux profiles will be investigated

  5. Hydrosphere monitoring at nuclear power plant sites

    International Nuclear Information System (INIS)

    Belousova, A.P.; Zakharova, T.V.; Shvets, V.M.

    1993-01-01

    The paper deals with problems related to protection of the environment in areas occupied by nuclear power plants (NPP). NPP construction and operation result in destruction of ecological, geochemical and geological equilibria in and around NPP sites. This process requires monitoring. Recommendations of the International Agency for Atomic Energy (IAAE) suggest monitoring to commence 2-3 years prior to the start of NPP construction. The paper describes the extent of hydrosphere monitoring and guidelines along which monitoring is to be organized. The authors recommend a certain approach toward the planning observation networks and provide description of forecasting subsystem that consist of a data bank, a continuously operating model (COM) and a forecast unit

  6. Monitoring device for the reactor power distribution

    International Nuclear Information System (INIS)

    Uematsu, Hitoshi; Tsuiki, Makoto

    1982-01-01

    Purpose: To enable accurate monitoring for the power distribution in a short time, as well as independent detection for in-core neutron flux detectors in abnormal operation due to failures or like other causes to thereby surely provide reliable substitute values. Constitution: Counted values are inputted from a reactor core present status data detector by a power distribution calculation device to calculate the in-core neutron flux density and the power distribution based on previously stored physical models. While on the other hand, counted value from the in-core neutron detectors and the neutron flux distribution and the power distribution calculated from the power distribution calculation device are inputted from a BCF calculation device to compensate the counting errors incorporated in the counted value from the in-core neutron flux detectors and the calculation errors incorporated in the power distribution calculated in the power distribution calculation device respectively and thereby calculate the power distribution in the reactor core. Further, necessary data are inputted to the power distribution calculation device by an input/output device and the results calculated in the BCF calculation device are displayed. (Aizawa, K.)

  7. Monitoring power breakers using vibro acoustic techniques

    Directory of Open Access Journals (Sweden)

    Horia Balan

    2017-09-01

    Full Text Available Speaking about the commutation’s equipment, it can be said that the best solution in increasing reliability and lowering the maintenance costs is a continuous monitoring of the equipment. However, if the price/quality ratio is considered, it is obvious that, for the moment, the diagnosis can be also an acceptable solution. Nowadays the predictive maintenance for equipment’s diagnosis is currently replacing the preventive diagnosis. An efficient modality of lowering the maintenance costs is to online monitoring the power breakers, during their operation in the power systems. Consequently any connecting/disconnecting operations may be used in diagnosing a power breaker. Thus any supplementary and superfluous tests and/or maintenance maneuvers are avoided. The paper presents the operational maintenance in a power station with three high voltage active breakers, Areva type. The method of establishing the state of a breaker consists in the comparison between the signature of the acoustic signal provided by the manufacturer and the signal issued from the testing operation of the breaker’s state. The software processing procedure and the methodology of determining the faults of the monitored equipment are also developed. All the tests on the circuit breaker are made according the prescriptions of normative.

  8. Monitoring method of an atomic power plant

    International Nuclear Information System (INIS)

    Koba, Akitoshi; Goto, Seiichiro; Ohashi, Hideaki.

    1975-01-01

    Object: To make a monitoring vehicle, which is loaded with various detecting elements, go round along the monorail disposed so as to surround various devices to thereby early discover various abnormal conditions. Structure: The monitoring vehicle is travelled on the monorail disposed so as to surround the periphery of various devices in an atomic power plant so that detection signals from an ITV camera, temperature and radioactive rays and sound detecting elements, and the like are received through a slide contact between the wheel and transmitting and receiving line disposed in the wheel groove to transmit the signals to a central control panel. (Yoshihara, H.)

  9. NOKIA - nuclear power plant monitoring system

    International Nuclear Information System (INIS)

    Anon.

    The monitoring system is described developed specially for the LOVIISA-1 and -2 nuclear power plants with two WWER-440 units. The multiprocessor system of the WWER-440 contains 3 identical main computers. The in core instrumentation is based on stationary self-powered neutron detectors and on thermocouples for measuring the coolant temperature. The system has equipment for the automatic control of the insulation resistance of the self-powered detectors. It is also equipped with a wide range of standard and special programmes. The standard programmes permit the recording of analog and digital data at different frequencies depending on the pre-set requirements. These data are processed and form data files which are accessible from all programmes. The heart of the special programme is a code for the determination of the power distribution in the core of the WWER-440 reactor. The main part of the programme is the algorithm for computing measured neutron fluxes derived from the signals of the self-powered detectors and the algorithm for deriving the global distribution of the neutron flux in the core. The computed power distribution is used for the determination of instantaneous thermal loads and the distribution of burnup in the core. The production programme of the FINNATOM company for nuclear power plants is listed. (B.S.)

  10. The power grid monitoring promotion of Liaoning December 14th accident

    Science.gov (United States)

    Zhou, Zhi; Gao, Ziji; He, Xiaoyang; Li, Tie; Jin, Xiaoming; Wang, Mingkai; Qu, Zhi; Sun, Chenguang

    2018-02-01

    This paper introduces the main responsibilities of power grid monitoring and the accident of Liaoning Power Grid 500kV Xujia transformer substation at December 14th, 2016. This paper analyzes the problems exposed in this accident from the aspects of abnormal information judgment, fault information collection, auxiliary video monitoring, online monitoring of substation equipment, puts forward the corresponding improvement methods and summarizes the methods of improving the professional level of power grid equipment monitoring.

  11. Monitoring device for local power peaking coefficient

    International Nuclear Information System (INIS)

    Mitsuhashi, Ishi

    1987-01-01

    Purpose: To monitor the local power peaking coefficients obtained by the method not depending on the combination of fuel types. Method: A plurality of representative values for the local power distribution determined by the nuclear constant calculation for one fuel assembly are memorized regarding each of the burn-up degree and the void coefficient on every positions and fuel types in fuel rod assemblies. While on the other hand, the representative values for the local power distribution as described above are compensated by a compensation coefficient considering the effect of adjacent segments and a control rod compensation coefficient considering the effect due to the control rod insertion relative to the just-mentioned compensation coefficient. Then, the maximum value among them is selected to determine the local power peaking coefficient at each of the times and each of the segments, which is monitored. According to this system, the calculation and the working required for the fitting work depending on the combination of fuel types are no more required at all to facilitate the maintenance as well. (Horiuchi, T.)

  12. Water level monitoring device in nuclear reactor

    International Nuclear Information System (INIS)

    Miura, Kiyohide; Otake, Tomohiro.

    1988-01-01

    Purpose: To monitor the water level in a pressure vessel of BWR type nuclear reactors at high accuracy by improving the compensation functions. Constitution: In the conventional water level monitor in a nuclear reactor, if the pressure vessel is displaced by the change of the pressure in the reactor or the temperature of the reactor water, the relative level of the reference water head in a condensation vessel is changed to cause deviation between the actual water level and the indicated water level to reduce the monitoring accuracy. According to the invention, means for detecting the position of the reference water head and means for detection the position in the condensation vessel are disposed to the pressure vessel. Then, relative positional change between the condensation vessel and the reference water head is calculated based on detection sinals from both of the means. The water level is compensated and calculated by water level calculation means based on the relative positional change, water level signals from the level gage and the pressure signals from the pressure gage. As a result, if the pressure vessel is displaced due to the change of the temperature or pressure, it is possible to measure the reactor water level accurately thereby remakably improve the reliability for the water level control in the nuclear reactor. (Horiuchi, T.)

  13. Ultra low power signal oriented approach for wireless health monitoring.

    Science.gov (United States)

    Marinkovic, Stevan; Popovici, Emanuel

    2012-01-01

    In recent years there is growing pressure on the medical sector to reduce costs while maintaining or even improving the quality of care. A potential solution to this problem is real time and/or remote patient monitoring by using mobile devices. To achieve this, medical sensors with wireless communication, computational and energy harvesting capabilities are networked on, or in, the human body forming what is commonly called a Wireless Body Area Network (WBAN). We present the implementation of a novel Wake Up Receiver (WUR) in the context of standardised wireless protocols, in a signal-oriented WBAN environment and present a novel protocol intended for wireless health monitoring (WhMAC). WhMAC is a TDMA-based protocol with very low power consumption. It utilises WBAN-specific features and a novel ultra low power wake up receiver technology, to achieve flexible and at the same time very low power wireless data transfer of physiological signals. As the main application is in the medical domain, or personal health monitoring, the protocol caters for different types of medical sensors. We define four sensor modes, in which the sensors can transmit data, depending on the sensor type and emergency level. A full power dissipation model is provided for the protocol, with individual hardware and application parameters. Finally, an example application shows the reduction in the power consumption for different data monitoring scenarios.

  14. Acoustic power delivery to pipeline monitoring wireless sensors.

    Science.gov (United States)

    Kiziroglou, M E; Boyle, D E; Wright, S W; Yeatman, E M

    2017-05-01

    The use of energy harvesting for powering wireless sensors is made more challenging in most applications by the requirement for customization to each specific application environment because of specificities of the available energy form, such as precise location, direction and motion frequency, as well as the temporal variation and unpredictability of the energy source. Wireless power transfer from dedicated sources can overcome these difficulties, and in this work, the use of targeted ultrasonic power transfer as a possible method for remote powering of sensor nodes is investigated. A powering system for pipeline monitoring sensors is described and studied experimentally, with a pair of identical, non-inertial piezoelectric transducers used at the transmitter and receiver. Power transmission of 18mW (Root-Mean-Square) through 1m of a118mm diameter cast iron pipe, with 8mm wall thickness is demonstrated. By analysis of the delay between transmission and reception, including reflections from the pipeline edges, a transmission speed of 1000m/s is observed, corresponding to the phase velocity of the L(0,1) axial and F(1,1) radial modes of the pipe structure. A reduction of power delivery with water-filling is observed, yet over 4mW of delivered power through a fully-filled pipe is demonstrated. The transmitted power and voltage levels exceed the requirements for efficient power management, including rectification at cold-starting conditions, and for the operation of low-power sensor nodes. The proposed powering technique may allow the implementation of energy autonomous wireless sensor systems for monitoring industrial and network pipeline infrastructure. Copyright © 2017 The Authors. Published by Elsevier B.V. All rights reserved.

  15. Condition monitoring and maintenance of nuclear power plant concrete structures

    International Nuclear Information System (INIS)

    Orr, R.; Prasad, N.

    1988-01-01

    Nuclear power plant concrete structures are potentially subject to deterioration due to several environmental conditions, including weather exposure, ground water exposure, and sustained high temperature and radiation levels. The nuclear power plant are generally licensed for a term of 40 years. In order to maximize the return from the existing plants, feasibility studies are in progress for continued operation of many of these plants beyond the original licensed life span. This paper describes a study that was performed with an objective to define appropriate condition monitoring and maintenance procedures. A timely implementation of a condition monitoring and maintenance program would provide a valuable database and would provide justification for extension of the plant's design life. The study included concrete structures such as the containment buildings, interior structures, basemats, intake structures and cooling towers. Age-related deterioration at several operating power plants was surveyed and the potential degradation mechanisms have been identified

  16. A nuclear power plant status monitor

    International Nuclear Information System (INIS)

    Chu, B.B.; Conradi, L.L.; Weinzimmer, F.

    1986-01-01

    Power plant operation requires decisions that can affect both the availability of the plant and its compliance with operating guidelines. Taking equipment out of service may affect the ability of the plant to produce power at a certain power level and may also affect the status of the plant with regard to technical specifications. Keeping the plant at a high as possible production level and remaining in compliance with the limiting conditions for operation (LCOs) can dictate a variety of plant operation and maintenance actions and responses. Required actions and responses depend on the actual operational status of a nuclear plant and its attendant systems, trains, and components which is a dynamic situation. This paper discusses an Electric Power Research Institute (EPRI) Research Project, RP 2508, the objective of which is to combine the key features of plant information management systems with systems reliability analysis techniques in order to assist nuclear power plant personnel to perform their functions more efficiently and effectively. An overview of the EPRI Research Project is provided along with a detailed discussion of the design and operation of the PSM portion of the project

  17. On-line Monitoring System for Power Transformers

    Directory of Open Access Journals (Sweden)

    Alexandru HOTEA

    2016-12-01

    Full Text Available Power transformers are the most important and expensive equipment from the electricity transmission system, so it is very important to know the real state of health of such equipment in every moment. De-energizing the power transformer accidentally due to internal defects can generate high costs. Annual maintenance proved to be ineffective in many cases to determine the internal condition of the equipment degradation due to faults rapidly evolving. An On-line Monitoring System for Power Transformers help real-time condition assessment and to detect errors early enough to take action to eliminate or minimize them. After abnormality detected, it is still important to perform full diagnostic tests to determine the exact condition of the equipment. On-line monitoring systems can help increase the level of availability and reliability of power transformers and lower costs of accidental interruption. This paper presents cases studies on several power transformers equipped with on-line monitoring systems from Transelectrica substation.

  18. Monitoring of Low Levels of Furfural in Power Transformer Oil with a Sensor System Based on a POF-MIP Platform

    Directory of Open Access Journals (Sweden)

    Nunzio Cennamo

    2015-04-01

    Full Text Available In this work an innovative, miniaturized and low cost optical chemical sensor (POF-MIP platform, based on a molecular imprinted polymer (MIP and surface plasmon resonance in a plastic optical fiber (POF, is presented and preliminarily tested for monitoring of furfural (furan-2-carbaldehyde in transformer oil. To this end, the optical platform was coupled to an MIP layer, highly selective for furfural. The ability of the developed sensor to directly detect furfural in the insulating oil was investigated. The detection limit of the sensor has been found to be 9 ppb, with a linear response up to about 30 ppb. However there is a sensible response up to 0.15 ppm. Because of the small linearity range, the Hill equation is suggested for the quantification. The sensor has been effectively tested in real oil samples collected from aged electrical equipment removed from service. The assessed concentration of furfural is in good agreement with that evaluated by a high pressure liquid chromatography (HLPC method, confirming the good selectivity of the proposed sensor.

  19. Monitoring of Low Levels of Furfural in Power Transformer Oil with a Sensor System Based on a POF-MIP Platform

    Science.gov (United States)

    Cennamo, Nunzio; De Maria, Letizia; D’Agostino, Girolamo; Zeni, Luigi; Pesavento, Maria

    2015-01-01

    In this work an innovative, miniaturized and low cost optical chemical sensor (POF-MIP platform), based on a molecular imprinted polymer (MIP) and surface plasmon resonance in a plastic optical fiber (POF), is presented and preliminarily tested for monitoring of furfural (furan-2-carbaldehyde) in transformer oil. To this end, the optical platform was coupled to an MIP layer, highly selective for furfural. The ability of the developed sensor to directly detect furfural in the insulating oil was investigated. The detection limit of the sensor has been found to be 9 ppb, with a linear response up to about 30 ppb. However there is a sensible response up to 0.15 ppm. Because of the small linearity range, the Hill equation is suggested for the quantification. The sensor has been effectively tested in real oil samples collected from aged electrical equipment removed from service. The assessed concentration of furfural is in good agreement with that evaluated by a high pressure liquid chromatography (HLPC) method, confirming the good selectivity of the proposed sensor. PMID:25871719

  20. Monitoring of low levels of furfural in power transformer oil with a sensor system based on a POF-MIP platform.

    Science.gov (United States)

    Cennamo, Nunzio; De Maria, Letizia; D'Agostino, Girolamo; Zeni, Luigi; Pesavento, Maria

    2015-04-13

    In this work an innovative, miniaturized and low cost optical chemical sensor (POF-MIP platform), based on a molecular imprinted polymer (MIP) and surface plasmon resonance in a plastic optical fiber (POF), is presented and preliminarily tested for monitoring of furfural (furan-2-carbaldehyde) in transformer oil. To this end, the optical platform was coupled to an MIP layer, highly selective for furfural. The ability of the developed sensor to directly detect furfural in the insulating oil was investigated. The detection limit of the sensor has been found to be 9 ppb, with a linear response up to about 30 ppb. However there is a sensible response up to 0.15 ppm. Because of the small linearity range, the Hill equation is suggested for the quantification. The sensor has been effectively tested in real oil samples collected from aged electrical equipment removed from service. The assessed concentration of furfural is in good agreement with that evaluated by a high pressure liquid chromatography (HLPC) method, confirming the good selectivity of the proposed sensor.

  1. Environmental monitoring around nuclear power plants of EDF in France

    International Nuclear Information System (INIS)

    Chretien, V.; Hemidy, P.Y.

    2010-01-01

    As part of the regulatory environmental monitoring around its nuclear power plants, EDF carries out every year more than 40.000 measurements. In addition EDF performs more precise radioecological surveys on all its sites. This monitoring shows the minor incidence of EDF's nuclear power plants on the environment and a general decrease of gamma emitters radionuclides in the environment. These results confirm the efforts lead by EDF to minimise its impacts on the environment, linked to an efficient waste management and demonstrate the good operating standards of its plants. On a qualitative viewpoint, significant efforts on both metrology and organization have lead to improved measurements capabilities, in order to achieve NF EN ISO/CEI 17025 standard compliance. More recently, a similar approach has been implemented with sampling methods. While today the level achieved in the number and quality of measurement complies with the objectives of the monitoring of the impact of the nuclear power plants on the environment, the results of this monitoring should be presented to the public with more pedagogy to give an adequate answer to their expectations. The new questions that will undoubtedly be raised by the recent availability of this information on the Internet should reinforce this dialogue and should also be the opportunity to improve the quality of our communication. (author)

  2. Background compensation for a radiation level monitor

    Science.gov (United States)

    Keefe, D.J.

    1975-12-01

    Background compensation in a device such as a hand and foot monitor is provided by digital means using a scaler. With no radiation level test initiated, a scaler is down-counted from zero according to the background measured. With a radiation level test initiated, the scaler is up-counted from the previous down-count position according to the radiation emitted from the monitored object and an alarm is generated if, with the scaler having crossed zero in the positive going direction, a particular number is exceeded in a specific time period after initiation of the test. If the test is initiated while the scale is down-counting, the background count from the previous down- count stored in a memory is used as the initial starting point for the up-count.

  3. Correlation techniques in nuclear power plant monitoring

    International Nuclear Information System (INIS)

    Bastl, W.

    1976-01-01

    Ever increasing effects are recently being made to monitor the mechanical behaviour of the nuclear power plants during operation. For technical as well as economical reasons one is forced to make do with the smallest number of sensors. In order to still obtain efficient control systems, an attempt is made on the one hand to make use of the already existing operational instrumentation, on the other hand to obtain a maximum of information by specific use of few additional sensors. In both cases, correlation analysis plays a large role because an optimum positioning of the sensor is seldom possible and thus, as a rule, the interesting information must be separated from very noisy signals. (orig./LH) [de

  4. Monitoring PWR reactor vessel liquid level with SPNDs during LOCAs

    International Nuclear Information System (INIS)

    Adams, J.P.

    1982-01-01

    Data from in-core self-powered neutron detectors taken during two nuclear loss-of-coolant accident simulations have been correlated with core moderator density changes. The detector current attenuation has been calculated during blowdown and reflood phases of the simulation. Based on these data, it is concluded that these detectors could be used to monitor reactor vessel liquid level during loss-of-coolant accidents in pressurized water reactors

  5. Float level switch for a nuclear power plant containment vessel

    International Nuclear Information System (INIS)

    Powell, J.G.

    1993-01-01

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures

  6. Float level switch for a nuclear power plant containment vessel

    Science.gov (United States)

    Powell, James G.

    1993-01-01

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

  7. Corrosion potential monitoring in nuclear power environments

    International Nuclear Information System (INIS)

    Molander, A.

    2004-01-01

    Full text of publication follows: corrosion monitoring. The corrosion potential is usually an important parameter or even the prime parameter for many types of corrosion processes. One typical example of the strong influence of the corrosion potential on corrosion performance is stress corrosion of sensitized stainless steel in pure high temperature water corresponding to boiling water conditions. The use of in-plant monitoring to follow the effect of hydrogen addition to mitigate stress corrosion in boiling water reactors is now a well-established technique. However, different relations between the corrosion potential of stainless steel and the oxidant concentration have been published and only recently an improved understanding of the electrochemical reactions and other conditions that determine the corrosion potential in BWR systems have been reached. This improved knowledge will be reviewed in this paper. Electrochemical measurements has also been performed in PWR systems and mainly the feedwater system on the secondary side of PWRs. The measurements performed so far have shown that electrochemical measurements are a very sensitive tool to detect and follow oxygen transients in the feedwater system. Also determinations of the minimum hydrazine dosage to the feedwater have been performed. However, PWR secondary side monitoring has not yet been utilized to the same level as BWR hydrogen water chemistry surveillance. The future potential of corrosion potential monitoring will be discussed. Electrochemical measurements are also performed in other reactor systems and in other types of reactors. Experiences will be briefly reviewed. In a BWR on hydrogen water chemistry and in the PWR secondary system the corrosion potentials show a large variation between different system parts. To postulate the material behavior at different locations the local chemical and electrochemical conditions must be known. Thus, modeling of chemical and electrochemical conditions along

  8. COLLABORATIVE MULTI-LEVEL PLAN MONITORING

    Directory of Open Access Journals (Sweden)

    Mohamad K. ALLOUCHE

    2011-01-01

    Full Text Available The recent worldwide connectivity and the net-centricity of military operations (coalition-based operations are witnessing an increasing need for the monitoring of plan execution for enhanced resource management and decision making. Monitoring of ongoing operations is the process of continuous observation recording and reporting. In this process the plan becomes a resource that needs to be managed effi ciently. The centralized approach to plan monitoring soon reaches its limits when plan execution is distributed across different organizations/countries. We propose a new framework that would allow different monitoring nodes distributed across the network. An effi cient propagation mechanism that allows information exchange between the different nodes would also be needed. The main purpose of this mechanism is to present the right information, to the right person, at the right time. To cope with a rapid increase of information fl ow through the network, an effi cient alarm management mechanism allows the presentation of the information with an appropriate level of details.

  9. 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)

  10. A radiation monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Iwai, Masaru; Nakamori, S.; Ikeda, H.; Oda, M.

    1974-01-01

    Safety with respect to radiation is vital factor, particularly in view of the increasing number of nuclear power plants. For this purpose, a radiation monitoring system is provided to perform constant supervision. This article describes the purpose, installation location, specifications and circuitry of a system which is divided into three units: the process monitor, area monitor and off-site monitor. (auth.)

  11. Voices of nuclear power monitors in fiscal 1982

    International Nuclear Information System (INIS)

    1984-01-01

    The system of nuclear power monitors was set up to hear candid opinions, etc. from general people on nuclear power development and utilization, and reflect them to nuclear power administration. As the monitors, 416 persons were selected across the country. The results in fiscal 1982 are described. (1) Questionnaire survey: Of the 416, 314 persons answered the questionnaire conducted in March, 1983, on future energy, nuclear power development, nuclear power safety administration, and nuclear power P.R. activities. (2) Occasional voices of monitors: Of the total 74 opinions, etc. from the monitors in fiscal 1982, 31 concerned the nuclear power P.R. activities, followed by 16 on nuclear power development and utilization, and 12 on nuclear power administration. (Mori, K.)

  12. Axial power monitoring uncertainty in the Savannah River Reactors

    International Nuclear Information System (INIS)

    Losey, D.C.; Revolinski, S.M.

    1990-01-01

    The results of this analysis quantified the uncertainty associated with monitoring the Axial Power Shape (APS) in the Savannah River Reactors. Thermocouples at each assembly flow exit map the radial power distribution and are the primary means of monitoring power in these reactors. The remaining uncertainty in power monitoring is associated with the relative axial power distribution. The APS is monitored by seven sensors that respond to power on each of nine vertical Axial Power Monitor (APM) rods. Computation of the APS uncertainty, for the reactor power limits analysis, started with a large database of APM rod measurements spanning several years of reactor operation. A computer algorithm was used to randomly select a sample of APSs which were input to a code. This code modeled the thermal-hydraulic performance of a single fuel assembly during a design basis Loss-of Coolant Accident. The assembly power limit at Onset of Significant Voiding was computed for each APS. The output was a distribution of expected assembly power limits that was adjusted to account for the biases caused by instrumentation error and by measuring 7 points rather than a continuous APS. Statistical analysis of the final assembly power limit distribution showed that reducing reactor power by approximately 3% was sufficient to account for APS variation. This data confirmed expectations that the assembly exit thermocouples provide all information needed for monitoring core power. The computational analysis results also quantified the contribution to power limits of the various uncertainties such as instrumentation error

  13. 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.

  14. GNSS-Reflectometry based water level monitoring

    Science.gov (United States)

    Beckheinrich, Jamila; Schön, Steffen; Beyerle, Georg; Apel, Heiko; Semmling, Maximilian; Wickert, Jens

    2013-04-01

    Due to climate changing conditions severe changes in the Mekong delta in Vietnam have been recorded in the last years. The goal of the German Vietnamese WISDOM (Water-related Information system for the Sustainable Development Of the Mekong Delta) project is to build an information system to support and assist the decision makers, planners and authorities for an optimized water and land management. One of WISDOM's tasks is the flood monitoring of the Mekong delta. Earth reflected L-band signals from the Global Navigation Satellite System show a high reflectivity on water and ice surfaces or on wet soil so that GNSS-Reflectometry (GNSS-R) could contribute to monitor the water level in the main streams of the Mekong delta complementary to already existing monitoring networks. In principle, two different GNSS-R methods exist: the code- and the phase-based one. As the latter being more accurate, a new generation of GORS (GNSS Occultation, Reflectometry and Scatterometry) JAVAD DELTA GNSS receiver has been developed with the aim to extract precise phase observations. In a two week lasting measurement campaign, the receiver has been tested and several reflection events at the 150-200 m wide Can Tho river in Vietnam have been recorded. To analyze the geometrical impact on the quantity and quality of the reflection traces two different antennas height were tested. To track separately the direct and the reflected signal, two antennas were used. To derive an average height of the water level, for a 15 min observation interval, a phase model has been developed. Combined with the coherent observations, the minimum slope has been calculated based on the Least- Squares method. As cycle slips and outliers will impair the results, a preprocessing of the data has been performed. A cycle slip detection strategy that allows for automatic detection, identification and correction is proposed. To identify outliers, the data snooping method developed by Baarda 1968 is used. In this

  15. Reactor Emergency Action Level Monitor: Knowledge acquisition experiences

    International Nuclear Information System (INIS)

    Touchton, R.A.

    1987-01-01

    This paper presents the Knowledge Acquisition experiences in developing the Reactor Emergency Action Level Monitor (REALM) Expert System Prototype. REALM is an expert system which interprets plant sensor data and provides advice on the proper emergency classification. The REALM project is being funded by the Electric Power Research Institute, Consolidated Edison is serving as the host utility, and the effort is being conducted by Technology Applications, Inc. REALM is being designed to provide expert assistance in the identification of a nuclear power plant emergency situation and the determination of its severity, ultimately operating in a real-time, on-line processing environment. The paper discusses briefly the direct knowledge acquisition techniques used by the project team (who are themselves power industry engineers), to extract relevant knowledge from plant specifications and procedures

  16. Vibration monitoring and fault diagnostics of a thermal power plant

    International Nuclear Information System (INIS)

    Hafeez, T.; Ghani, R.; Chohan, G.Y.; Amir, M.

    2003-01-01

    A thermal power plant was monitored from HP-turbine to the generator end. The vibration data at different plant locations was obtained with the help of a data collector/analyzer. The spectra of-all locations generate the symptoms for different problems of moderate and high vibration levels like bent shaft, misalignment in the exciter rotor and three couplings, mechanical looseness on generator and exciter sides. The possible causes of these faults are discussed on the basis of presented vibration spectra in this paper. The faults were later on rectified on the basis of this diagnostics. (author)

  17. LPGC, Levelized Steam Electric Power Generator Cost

    International Nuclear Information System (INIS)

    Coen, J.J.; Delene, J.G.

    1994-01-01

    1 - Description of program or function: LPGC is a set of nine microcomputer programs for estimating power generation costs for large steam-electric power plants. These programs permit rapid evaluation using various sets of economic and technical ground rules. The levelized power generation costs calculated may be used to compare the relative economics of nuclear and coal-fired plants based on life-cycle costs. Cost calculations include capital investment cost, operation and maintenance cost, fuel cycle cost, decommissioning cost, and total levelized power generation cost. These programs can be used for quick analyses of power generation costs using alternative economic parameters, such as interest rate, escalation rate, inflation rate, plant lead times, capacity factor, fuel prices, etc. The two major types of electric generating plants considered are pressurized-water reactor (PWR) and pulverized coal-fired plants. Data are also provided for the Large Scale Prototype Breeder (LSPB) type liquid metal reactor. Costs for plant having either one or two units may be obtained. 2 - Method of solution: LPGC consists of nine individual menu-driven programs controlled by a driver program, MAINPWR. The individual programs are PLANTCAP, for calculating capital investment costs; NUCLOM, for determining operation and maintenance (O and M) costs for nuclear plants; COALOM, for computing O and M costs for coal-fired plants; NFUEL, for calculating levelized fuel costs for nuclear plants; COALCOST, for determining levelized fuel costs for coal-fired plants; FCRATE, for computing the fixed charge rate on the capital investment; LEVEL, for calculating levelized power generation costs; CAPITAL, for determining capitalized cost from overnight cost; and MASSGEN, for generating, deleting, or changing fuel cycle mass balance data for use with NFUEL. LPGC has three modes of operation. In the first, each individual code can be executed independently to determine one aspect of the total

  18. Discussion on monitoring items of radionuclides in influents from nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Yanxia; Li Jin; Liu Jiacheng; Han Shanbiao; Yu Zhengwei

    2014-01-01

    For the radionuclide monitoring items of effluents from nuclear power plant, this paper makes some comparisons and analysis from three aspects of the international atomic energy general requirements, the routine radionuclide measurement items of China's nuclear power plant and effluents low level radionuclide experimental research results. Finally, it summarizes the necessary items and recommended items of the radionuclide monitoring of effluents from nuclear power plant, which can provide references for the radioactivity monitoring activities of nuclear power plant effluent and the supervisions of regulatory departments. (authors)

  19. Power distribution monitoring and control in the RBMK type reactors

    International Nuclear Information System (INIS)

    Emel'yanov, I.Ya.; Postnikov, V.V.; Volod'ko, Yu.I.

    1980-01-01

    Considered are the structures of monitoring and control systems for the RBMK-1000 reactor including three main systems with high independence: the control and safety system (CSS); the system for physical control of energy distribution (SPCED) as well as the Scala system for centralized control (SCC). Main functions and peculiarities of each system are discussed. Main attention is paid to new structural solutions and new equipment components used in these systems. Described are the RBMK operation software and routine of energy distribution control in it. It is noted that the set of reactor control and monitoring systems has a hierarchical structure, the first level of which includes analog systems (CSS and SPCED) normalizing and transmitting detector signals to the systems of the second level based on computers and realizing computer data processing, data representation to the operator, automatic (through CSS) control for energy distribution, diagnostics of equipment condition and local safety with provision for existing reserves with respect to crisis and thermal loading of fuel assemblies. The third level includes a power computer carrying out complex physical and optimization calculations and providing interconnections with the external computer of power system. A typical feature of the complex is the provision of local automatic safety of the reactor from erroneous withdrawal of any control rod. The complex is designed for complete automatization of energy distribution control in reactor in steady and transient operation conditions

  20. Architectural-level power estimation and experimentation

    Science.gov (United States)

    Ye, Wu

    With the emergence of a plethora of embedded and portable applications and ever increasing integration levels, power dissipation of integrated circuits has moved to the forefront as a design constraint. Recent years have also seen a significant trend towards designs starting at the architectural (or RT) level. Those demand accurate yet fast RT level power estimation methodologies and tools. This thesis addresses issues and experiments associate with architectural level power estimation. An execution driven, cycle-accurate RT level power simulator, SimplePower, was developed using transition-sensitive energy models. It is based on the architecture of a five-stage pipelined RISC datapath for both 0.35mum and 0.8mum technology and can execute the integer subset of the instruction set of SimpleScalar . SimplePower measures the energy consumed in the datapath, memory and on-chip buses. During the development of SimplePower , a partitioning power modeling technique was proposed to model the energy consumed in complex functional units. The accuracy of this technique was validated with HSPICE simulation results for a register file and a shifter. A novel, selectively gated pipeline register optimization technique was proposed to reduce the datapath energy consumption. It uses the decoded control signals to selectively gate the data fields of the pipeline registers. Simulation results show that this technique can reduce the datapath energy consumption by 18--36% for a set of benchmarks. A low-level back-end compiler optimization, register relabeling, was applied to reduce the on-chip instruction cache data bus switch activities. Its impact was evaluated by SimplePower. Results show that it can reduce the energy consumed in the instruction data buses by 3.55--16.90%. A quantitative evaluation was conducted for the impact of six state-of-art high-level compilation techniques on both datapath and memory energy consumption. The experimental results provide a valuable insight for

  1. Mobile radiological monitoring around Nuclear Power Plant site at Tarapur

    International Nuclear Information System (INIS)

    Patil, S.S.; Saindane, S.S.; Sharma, R.; Suri, M.M.K.; Pradeepkumar, K.S.; Sharma, D.N.; Rao, D.D.

    2008-01-01

    Real time mobile radiological monitoring around nuclear facilities is required for establishing background radiation dose rate data and to detect any increase in the radiation level which is attributable to the atmospheric releases from Nuclear facilities. Mobile radiation survey using mobile monitoring systems was carried out in the Emergency Planning Zone around Tarapur Atomic Power station during plant operation, taking the wind direction also into consideration. For identifying the potential difficulties during an emergency scenario and to understand the variation of the measured values several systems/instruments were used simultaneously for mapping the dose rates. As demonstrated during this monitoring programme, 40mm x 40mm NaI(Tl) detector based Portable Mobile Gamma Spectrometry System (PMGSS) which is attached with a GPS can acquire and store large amount of gamma spectra tagged with positional coordinates and can enhance the capacity of decision makers during any accidental situation. The average of dose rates measured from various locations around Tarapur Atomic Power Station is 70 - 80 nGy.h -1 . The higher dose rate in the range of 110-125 nGy.h -1 measured at one of the location is due to higher concentration of natural radioactivity mainly by 40 K which was confirmed by the gamma spectrometric measurement. (author)

  2. Determing and monitoring of maximum permissible power for HWRR-3

    International Nuclear Information System (INIS)

    Jia Zhanli; Xiao Shigang; Jin Huajin; Lu Changshen

    1987-01-01

    The operating power of a reactor is an important parameter to be monitored. This report briefly describes the determining and monitoring of maximum permissiable power for HWRR-3. The calculating method is described, and the result of calculation and analysis of error are also given. On-line calculation and real time monitoring have been realized at the heavy water reactor. It provides the reactor with a real time and reliable supervision. This makes operation convenient and increases reliability

  3. Automatic acoustic and vibration monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Tothmatyas, Istvan; Illenyi, Andras; Kiss, Jozsef; Komaromi, Tibor; Nagy, Istvan; Olchvary, Geza

    1990-01-01

    A diagnostic system for nuclear power plant monitoring is described. Acoustic and vibration diagnostics can be applied to monitor various reactor components and auxiliary equipment including primary circuit machinery, leak detection, integrity of reactor vessel, loose parts monitoring. A noise diagnostic system has been developed for the Paks Nuclear Power Plant, to supervise the vibration state of primary circuit machinery. An automatic data acquisition and processing system is described for digitalizing and analysing diagnostic signals. (R.P.) 3 figs

  4. Events as Power Source: Wireless Sustainable Corrosion Monitoring

    OpenAIRE

    Sun, Guodong; Qiao, Guofu; Zhao, Lin; Chen, Zhibo

    2013-01-01

    This study presents and implements a corrosion-monitoring wireless sensor platform, EPS (Events as Power Source), which monitors the corrosion events in reinforced concrete (RC) structures, while being powered by the micro-energy released from the corrosion process. In EPS, the proposed corrosion-sensing device serves both as the signal source for identifying corrosion and as the power source for driving the sensor mote, because the corrosion process (event) releases electric energy; this is ...

  5. Low-level radioactive gas monitor for natural gas operations

    International Nuclear Information System (INIS)

    Armstrong, F.E.

    1969-11-01

    A portable radioactivity detection system for monitoring the tritium content of natural gas under field conditions has been developed. The sensing device employed is a complex proportional counting assembly operated without the use of massive shielding previously employed with such low-level radiation detectors. The practical limit of detection for the system is a tritium content of 10 -9 microcurie per cc of natural gas. All components of the system are packaged in three waterproof cases weighing slightly less than 30 kg each. Power requirement is 500 watts of 120 volt, 60 Hz current. Operation is fully automatic with a printed record produced at predetermined time intervals

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  7. A Two-Level Sound Classification Platform for Environmental Monitoring

    Directory of Open Access Journals (Sweden)

    Stelios A. Mitilineos

    2018-01-01

    Full Text Available STORM is an ongoing European research project that aims at developing an integrated platform for monitoring, protecting, and managing cultural heritage sites through technical and organizational innovation. Part of the scheduled preventive actions for the protection of cultural heritage is the development of wireless acoustic sensor networks (WASNs that will be used for assessing the impact of human-generated activities as well as for monitoring potentially hazardous environmental phenomena. Collected sound samples will be forwarded to a central server where they will be automatically classified in a hierarchical manner; anthropogenic and environmental activity will be monitored, and stakeholders will be alarmed in the case of potential malevolent behavior or natural phenomena like excess rainfall, fire, gale, high tides, and waves. Herein, we present an integrated platform that includes sound sample denoising using wavelets, feature extraction from sound samples, Gaussian mixture modeling of these features, and a powerful two-layer neural network for automatic classification. We contribute to previous work by extending the proposed classification platform to perform low-level classification too, i.e., classify sounds to further subclasses that include airplane, car, and pistol sounds for the anthropogenic sound class; bird, dog, and snake sounds for the biophysical sound class; and fire, waterfall, and gale for the geophysical sound class. Classification results exhibit outstanding classification accuracy in both high-level and low-level classification thus demonstrating the feasibility of the proposed approach.

  8. The development of gate monitor for low level radioactive waste

    International Nuclear Information System (INIS)

    Fujisawa, Morio; Watanabe, Michito; Kato, Tatsuo

    1994-01-01

    Low-level radioactive waste (LLW) generated from nuclear power plants in Japan, have been deposited in the yard of each power plant. At present, it is stored in about 500,000 drum cans (200l each). These drum cans are carried to Mutsu-ogawara Port by special transport ships and then transferred to Rokkasho LLW transport trucks (special vehicles) for storage. The gate monitor is used to automatically measure the dose rate on the vehicles loaded with transport vessels from a remote location, to ensure the safe transportation from Mutsu-ogawara Port the Burying Center. It is a new system which has been developed for effective measurement of dose rate on a number of transport vessels in a short time. This system is the first in the world for measuring dose rate on vehicles. Such a system cannot be found in any country of the world. (author)

  9. Voices of nuclear-power monitors in fiscal 1981

    International Nuclear Information System (INIS)

    1983-01-01

    The system of ''nuclear-power monitors'', started in fiscal 1977, is for the purpose of hearing the opinions of general people on nuclear power development and utilization and reflecting the results to the governmental nuclear power administration. The number of monitors in fiscal 1981 is a total of 504. The results in the fiscal year are described: (1) Questionnaire survey: The survey was made from March 10 to 25, 1982. Of the total, 355 (70.4%) answered the questions concerning the following matters: the future of energy, the development of nuclear power, the administration of nuclear power safety, and nuclear power public relations. (2) Voices (opinion) sent by the monitors: Of the total 150 items sent from September, 1981, to March, 1982, 48 concerned public relations, 26 were about the development and utilization and 25 were about the safety. (Mori, K.)

  10. Smart Sensor ASIC for Nuclear Power Monitoring

    International Nuclear Information System (INIS)

    Kerwin, David B.; Merkel, Kenneth G.; Rouxel, Olivier

    2013-06-01

    Mixed-signal integrated circuits are used in a variety of applications where ionizing radiation is present, including satellites, space vehicles, nuclear reactor monitoring, medical imaging, and cancer therapy. While total ionizing radiation is present in each of these environments, the type of radiation (e.g. heavy ions vs. high-energy x-rays) and other environmental factors present unique challenges to the mixed-signal designer. This paper discusses a Smart Sensor radiation hardened, mixed-signal, application specific integrated circuit (ASIC) specifically designed for sensor monitoring in a nuclear reactor environment. Results after exposure to gamma rays, neutrons, and temperatures up to 200 deg. C are reported. (authors)

  11. Environmental radiation monitoring system in nuclear power station

    International Nuclear Information System (INIS)

    Matsuoka, Sadazumi; Tadachi, Katsuo; Endo, Mamoru; Yuya, Hiroshi

    1983-01-01

    At the time of the construction of nuclear power stations, prior to their start of operation, the state of environmental radiation must be grasped. After the start of the power stations, based on those data, the system of environmental radiation monitoring is established. Along with the construction of Kashiwazaki-Kariwa Nuclear Power Station, The Tokyo Electric Power Co., Inc. jointly with Fujitsu Ltd. has developed a high-reliability, environmental radiation monitoring system, and adopted ''optical data highways'' using optical fiber cables for communication. It consists of a central monitoring station and 11 telemeter observation points, for collecting both radiation and meteorological data. The data sent to the central station through the highways are then outputted on a monitoring panel. They are analyzed with a central processor, and the results are printed out. (Mori, K.)

  12. Monitoring of occupational exposure at nuclear power plants

    International Nuclear Information System (INIS)

    1997-01-01

    The regulations concerning the monitoring of radiation doses of nuclear power plant workers and the reporting of radiation doses to the Finnish Centre for Radiation and Nuclear Safety (STUK) are specified in the guide. (10 refs.)

  13. Monitoring, control and protection of interconnected power systems

    CERN Document Server

    Häger, Ulf; Voropai, Nikolai

    2014-01-01

    This book presents new tools and methods for monitoring, control and protection of large scale power systems, adapting Smart Grid technologies based on wide area data exchange in combination with modern measurement devices and advanced network controllers.

  14. Autonomous Monitoring Aerial Robot System for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji H.; Gu, Beom W; Thai, Van X.; Rim, C. T. [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    In this paper, autonomous monitoring aerial robot system (AMARS), which includes omnidirectional wireless charging platform, aerial robot, landing coils and a battery management board, is proposed to guarantee automatic monitoring of NPPs. The prototype of the system is fabricated, and omnidirectional charging of the system is experimentally validated with 1 C charging state. AR(Aerial Robots)s are essential for NPP accident management because human cannot access to the accident site due to the risks of unexpected explosions, collapses, and high level of radioactive contaminants. Moreover, ARs can support operators to manage normal operation of NPPs built in harsh environment of high temperature and humidity such as UAE Barakah NPP. Because these ARs usually have very low energy capacity, however, the operation time of ARs is less than 30 minutes and should be recharged regularly by human powers, which makes it impossible to monitor NPPs by ARs automatically. In this paper, the concept of AMARS has been proposed and its performance was successfully verified with a fabricated prototype. The charging state of the on board battery in AR was measured as 0.5 C with the induced voltage of 18.6 V, which is well matched to the designed induced voltage when the AR was placed on the edge of the wireless charging platform.

  15. Low Power Design with High-Level Power Estimation and Power-Aware Synthesis

    CERN Document Server

    Ahuja, Sumit; Shukla, Sandeep Kumar

    2012-01-01

    Low-power ASIC/FPGA based designs are important due to the need for extended battery life, reduced form factor, and lower packaging and cooling costs for electronic devices. These products require fast turnaround time because of the increasing demand for handheld electronic devices such as cell-phones, PDAs and high performance machines for data centers. To achieve short time to market, design flows must facilitate a much shortened time-to-product requirement. High-level modeling, architectural exploration and direct synthesis of design from high level description enable this design process. This book presents novel research techniques, algorithms,methodologies and experimental results for high level power estimation and power aware high-level synthesis. Readers will learn to apply such techniques to enable design flows resulting in shorter time to market and successful low power ASIC/FPGA design. Integrates power estimation and reduction for high level synthesis, with low-power, high-level design; Shows spec...

  16. Process control and monitoring system: Thermal Power Plant Gacko

    International Nuclear Information System (INIS)

    Jeremovic, Dragan; Skoko, Maksim; Gjokanovic, Zdravko

    2004-01-01

    DCS Ovation system, manufactured by Westinghouse, USA, is described in this paper. Emphasize on concept of realization and basic characteristic in Thermal Power Plant Gacko is given in this paper. The most important, noticed by now, comparative effects and performances of new monitoring and control system according to classical monitoring and control system of 300 MW units Thermal Power Plant Gacko in Gacko, are given in the conclusion. (Author)

  17. Diagnostic and monitoring systems in nuclear power plants

    International Nuclear Information System (INIS)

    Wehling, H.J.; Jax, P.; Streicher, V.

    1987-01-01

    Monitoring systems are important for the availability of nuclear power plants. A survey is given about such systems designed and constructed by the Kraftwerk Union AG Erlangen (Federal Republic of Germany) in order to assure the mechanical integrity of reactor cooling systems. Three monitoring systems based on microprocessors are presented: KUES (acoustic detection of loose parts), SUES (vibration), and FAMOS (fatigue)

  18. Analysis of Trinity Power Metrics for Automated Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Michalenko, Ashley Christine [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-07-28

    This is a presentation from Los Alamos National Laboraotyr (LANL) about the analysis of trinity power metrics for automated monitoring. The following topics are covered: current monitoring efforts, motivation for analysis, tools used, the methodology, work performed during the summer, and future work planned.

  19. Power plant cable condition monitoring and testing at Georgia Power

    International Nuclear Information System (INIS)

    Champion, T.C.

    1988-01-01

    Georgia Power's Research Center has been heavily involved in the evaluation of electrical insulating materials and cables since its inception more than 17 years ago. For the past ten years that expertise has been applied to cables used in generation plants. This paper discusses the results of two test programs. The first is a quality control inspection on 169 samples of new power generation cables. The second is a material degradation evaluation on four short cable samples removed from a coal fired plant during an equipment upgrade. The new material evaluation was performed to identify the cause of a high failure rate upon initial hi-pot testing of newly installed cables. The material degradation evaluation was performed to evaluate the need for replacement of existing cables during an equipment upgrade. Results of the evaluations have led to development of a detailed proposal for a program to evaluate cable degradation and remaining life for cables used in power generation facilities

  20. Power Monitoring Using the Raspberry Pi

    Science.gov (United States)

    Snyder, Robin M.

    2014-01-01

    The Raspberry Pi is a credit card size low powered compute board with Ethernet connection, HDMI video output, audio, full Linux operating system run from an SD card, and more, all for $45. With cables, SD card, etc., the cost is about $70. Originally designed to help teach computer science principles to low income children and students, the Pi has…

  1. Radioactivity monitoring programme of Krsko nuclear power plant

    International Nuclear Information System (INIS)

    Miklavzic, U.; Martincic, R.; Kanduc, M.; Lulic, S.; Kovac, J.; Breznik, B.

    1996-01-01

    As a successor to the preoperational surveillance programme, the regular offsite radioactivity monitoring programme (RMP) of the Krsko Nuclear Power Plant (NPP) was implemented in 1982, when the power plant formally commenced operating. Observations collected during the first years of its operation were later also the basis for setting up the official 'Regulatory guide on monitoring of nuclear installations', issued not earlier than in 1986. The basic criterion which governed the selection of measuring methods, sampling techniques and locations, was the extent to which the data obtained could serve for the realistic assessment of the committed dose to a member of the population, and later on to members of a representative (critical) group. To be able to differentiate the radioactivity released through the liquid and gaseous effluents of the NPP from other radiation sources (natural radioactivity, global contamination), and especially because of the varying radiotoxicity of different radionuclides, in principle monitoring in the environment, as at the source, had to provide activity data for each individual radionuclide appearing in the effluents. Therefore, as early as 1982 the programme attributed the main weight to high resolution gamma spectrometry, combined with specific radiochemical analytical methods (e.g. 90 Sr/ 89 Sr, 3 H, 14 C, alpha spectrometry of Pu isotopes) which together made feasible determination of individual specific activities of the most significant man-made and natural radionuclides. By weighting the specific activities of the radionuclides identified and measured in the media surveyed by dose factors for intake, the quantity 'B' - the so-called 'radiological burden', was calculated and introduced in the yearly-summary tables. Expressed in relative units, from which the committed dose could be readily calculated, the burden B very lucidly disclosed the relative importance of different artificial pollutants and natural radioactivity present in

  2. Emergency protection and nuclear power station remote monitoring

    International Nuclear Information System (INIS)

    Nowak, K.; Wolf, H.

    1986-01-01

    The States of the Federal Republic of Germany are planning emergency protection measures for the environment of nuclear power stations based on their statutory duty of care. In this connection the paper explains to what extent remote monitoring of nuclear power stations practised by the Federal Supervisory Authorities may support the design and implementation of emergency protection measures. (orig.) [de

  3. 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

  4. The cyclical monitoring system for digital power supplies at SSRF

    International Nuclear Information System (INIS)

    Tang Junlong; Li Deming; Shen Tianjian

    2009-01-01

    Based on available digital PS testing system and long-distance monitoring hardwares, the cyclical monitoring system for digital power supplies (PS) was developed at SSRF. Two models, i.e.long-distance cyclical monitoring and local cyclical monitoring, were established. The software developed in LabVIEW language was applied to the two models without any user interface modification. The user interface is simple. The system is suitable for debugging the digital PSs during long-distance monitoring and examining the performance. The long-distance model imitates the digital PSs' status for fault analysis and communication between the digital PS and the centre control room. The local model simultaneously examines stability of 18 new PSs for 24 h, monitors the PS controller, and detects malfunction. Parameters and status of the controller can be stored in Excel or Text file. The two models have been used at SSRF for monitoring the digital PSs. (authors)

  5. 42 CFR 403.754 - Monitoring expenditure level.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 2 2010-10-01 2010-10-01 false Monitoring expenditure level. 403.754 Section 403..., Conditions of Participation, and Payment § 403.754 Monitoring expenditure level. (a) Tracking expenditures... between the trigger level and Medicare expenditures for a FFY results in a carry forward that either...

  6. Risk monitor riskangel for risk-informed applications in nuclear power plants

    International Nuclear Information System (INIS)

    Wang, Fang; Wang, Jiaqun; Wang, Jin; Li, Yazhou; Hu, Liqin; Wu, Yican

    2016-01-01

    Highlights: • A general risk monitor riskangel with high-speed cutsets generator engine. • Benchmarks of actual nuclear power plant (NPP) instantaneous risk models. • Applications in daily operation, maintenance plan and component out of service. - Abstract: This paper studied the requirements of risk monitor software and its applications as a plant specific risk monitor, which supports risk-informed configuration risk management for the two CANDU 6 units at the Third Qinshan nuclear power plant (TQNPP) in China. It also describes the regulatory prospective on risk-informed Probabilistic Safety Assessment (PSA) applications and the use of risk monitor at operating nuclear power plants, high level technical and functional requirements for the development of CANDU specific risk monitor software, and future development trends.

  7. Efficient species-level monitoring at the landscape scale

    Science.gov (United States)

    Barry R. Noon; Larissa L. Bailey; Thomas D. Sisk; Kevin S. McKelvey

    2012-01-01

    Monitoring the population trends of multiple animal species at a landscape scale is prohibitively expensive. However, advances in survey design, statistical methods, and the ability to estimate species presence on the basis of detection­nondetection data have greatly increased the feasibility of species-level monitoring. For example, recent advances in monitoring make...

  8. Application of Equipment Monitoring Technology in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kang, H. T.; Lee, J. K.; Lee, K. D.; Jo, S. H.

    2012-01-01

    The major goal of nuclear power industries during the past 10 years is to increase reliability and utility capacity factor. As the capacitor factor, however, crept upward. it became harder to attain next percentage of improvement. Therefore other innovative technologies are required. By the technologies applied to the fossil power plants, equipment health monitoring was performed on equipment to maintain it in operable condition and contributed on improving their reliability a lot. But the equipment monitoring may be limited to the observation of current system states in nuclear power plant. Monitoring of current system states is being augmented with prediction of future operating states and predictive diagnosis of future failure states. Such predictive diagnosis is motivated by the need for nuclear power plants to optimize equipment performance and reduce costs and unscheduled downtime. This paper reviews the application of techniques that focus on improving reliability in nuclear power plant by monitoring and predicting equipment health and suggests how possible to support on-line monitoring

  9. Grid Monitoring and Advanced Control of Distributed Power Generation Systems

    DEFF Research Database (Denmark)

    Timbus, Adrian Vasile

    . As an example, the latest published grid codes stress the ability of distributed generators, especially wind turbines, to stay connected during short grid disturbances and in addition to provide active/reactive power control at the point of common coupling. Based on the above facts, the need for improving...... reported in some countries creating concerns about power system stability. This leads to a continuous evolution of grid interconnection requirements towards a better controllability of generated power and an enhanced contribution of distributed power generation systems to power system stability...... and adding more features to the control of distributed power generation systems (DPGS) arises. As a consequence, this thesis focuses on grid monitoring methods and possible approaches in control in order to obtain a more reliable and  exible power generation system during normal and faulty grid conditions...

  10. Vibration control and monitoring in nuclear power plants

    International Nuclear Information System (INIS)

    Theodor, P.

    1989-01-01

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

  11. Application of fatigue monitoring system in PWR nuclear power plant

    International Nuclear Information System (INIS)

    Piao Lei

    2014-01-01

    Fatigue failure is one form of equipment failure of nuclear power plant, influencing equipment lifetime and lifetime extension. Fatigue monitoring system can track real thermal transient at fatigue sensitive components, establish a basis for fatigue analyses based on realistic operating loads, identify unexpected operational transients, optimize the plant behavior by improved operating modes, provide supporting data for lifetime management, enhance security of plant and reduce economical loss. Fatigue monitoring system has been applied in many plants and is required to be applied in Generation-III nuclear power plant. It is necessary to develop the fatigue monitoring system with independent intellectual property rights and improve the competitiveness of domestic Generation-III nuclear power technology. (author)

  12. Standalone, battery powered radiation monitors for accelerator electronics

    CERN Document Server

    Wijnands, T; Spiezia, G

    2009-01-01

    A technical description of the design of a new type of radiation monitors is given. The key point in the design is the low power consumption inferior to 17 mW in radiation sensing mode and inferior to 0.3 mW in standby mode. The radiation monitors can operate without any external power or signal cabling and measure and store radiation data for a maximum period of 800 days. To read the radiation data, a standard PC can be connected via a USB interface to the device at any time. Only a few seconds are required to read out a single monitor. This makes it possible to survey a large network of monitoring devices in a short period of time, for example during a stop of the accelerator.

  13. The system of the measurement of reactor power and the monitoring of core power distribution

    International Nuclear Information System (INIS)

    Li Xianfeng

    1999-01-01

    The author mainly describes the measurement of the reactor power and the monitoring of the core power distribution in DAYA BAY nuclear power plant, introduces the calibration for the measurement system. Ex-core nuclear instrumentation system (RPN) and LOCA surveillance system (LSS) are the most important system for the object. they perform the measurement of the reactor power and the monitoring of the core power distribution on-line and timely. They also play the important roles in the reactor control and the reactor protection. For the same purpose there are test instrumentation system (KME) and in-core instrumentation system (RIC). All of them work together ensuring the exact measurement and effective monitoring, ensuring the safety of the reactor power plant

  14. Centralized operation and monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

    1988-01-01

    According to the prospect of long term energy demand, in 2000, the nuclear power generation facilities in Japan are expected to take 15.9% of the total energy demand. From this fact, it is an important subject to supply nuclear power more stably, and in the field of instrumentation and control, many researches and developments and the incessant effort of improvement have been continued. In the central operation and monitoring system which is the center of the stable operation of nuclear power plants, the man-machine technology aiding operators by electronic and computer application technologies has been positively developed and applied. It is considered that hereafter, for the purpose of rationally heightening the operation reliability of the plants, the high quality man-machine system freely using the most advanced technologies such as high reliability digital technology, optical information transmission, knowledge engineering and so on is developed and applied. The technical trend of operation and monitoring system, the concept of heightening operation and monitoring capability, the upgrading of operation and monitoring system, and the latest operation, monitoring and control systems for nuclear power plants and waste treatment facilities are described. (K.I.)

  15. Modern handling and monitoring concepts for nuclear power plants

    International Nuclear Information System (INIS)

    Hofmann, H.; Lochner, K.H.

    1989-01-01

    Advanced microprocessor technology offers new means and methods also to power plant operation to improve the man-machine interface by using VDU's for process control, thus enhancing plant safety and reliability. A future control-room concept involving operation and monitoring to be effected by means of VDU's exclusively, calls for a detailed knowledge of the requirements which are made by the process and the operator on the system, and for the application of a very powerful microprocessor technology. Visualization of operating and monitoring processes matched to the needs of operators should be possible at high functionality and display quality without substantial restrictions caused by the device technology used. (orig.) [de

  16. An ultralow power wireless intraocular pressure monitoring system

    International Nuclear Information System (INIS)

    Liu Demeng; Mei Niansong; Zhang Zhaofeng

    2014-01-01

    This paper describes an ultralow power wireless intraocular pressure (IOP) monitoring system that is dedicated to sensing and transferring intraocular pressure of glaucoma patients. Our system is comprised of a capacitive pressure sensor, an application-specific integrated circuit, which is designed on the SMIC 180 nm process, and a dipole antenna. The system is wirelessly powered and demonstrates a power consumption of 7.56 μW at 1.24 V during continuous monitoring, a significant reduction in active power dissipation compared to existing work. The input RF sensitivity is −13 dBm. A significant reduction in input RF sensitivity results from the reduction of mismatch time of the ASK modulation caused by FM0 encoding. The system exhibits an average error of ± 1.5 mmHg in measured pressure. Finally, a complete IOP system is demonstrated in the real biological environment, showing a successful reading of the pressure of an eye. (semiconductor integrated circuits)

  17. Events as Power Source: Wireless Sustainable Corrosion Monitoring

    Directory of Open Access Journals (Sweden)

    Guodong Sun

    2013-12-01

    Full Text Available This study presents and implements a corrosion-monitoring wireless sensor platform, EPS (Events as Power Source, which monitors the corrosion events in reinforced concrete (RC structures, while being powered by the micro-energy released from the corrosion process. In EPS, the proposed corrosion-sensing device serves both as the signal source for identifying corrosion and as the power source for driving the sensor mote, because the corrosion process (event releases electric energy; this is a novel idea proposed by this study. For accumulating the micro-corrosion energy, we integrate EPS with a COTS (Commercial Off-The-Shelf energy-harvesting chip that recharges a supercapacitor. In particular, this study designs automatic energy management and adaptive transmitted power control polices to efficiently use the constrained accumulated energy. Finally, a set of preliminary experiments based on concrete pore solution are conducted to evaluate the feasibility and the efficacy of EPS.

  18. Events as power source: wireless sustainable corrosion monitoring.

    Science.gov (United States)

    Sun, Guodong; Qiao, Guofu; Zhao, Lin; Chen, Zhibo

    2013-12-17

    This study presents and implements a corrosion-monitoring wireless sensor platform, EPS (Events as Power Source), which monitors the corrosion events in reinforced concrete (RC) structures, while being powered by the micro-energy released from the corrosion process. In EPS, the proposed corrosion-sensing device serves both as the signal source for identifying corrosion and as the power source for driving the sensor mote, because the corrosion process (event) releases electric energy; this is a novel idea proposed by this study. For accumulating the micro-corrosion energy, we integrate EPS with a COTS (Commercial Off-The-Shelf) energy-harvesting chip that recharges a supercapacitor. In particular, this study designs automatic energy management and adaptive transmitted power control polices to efficiently use the constrained accumulated energy. Finally, a set of preliminary experiments based on concrete pore solution are conducted to evaluate the feasibility and the efficacy of EPS.

  19. Self-Powered WSN for Distributed Data Center Monitoring

    Directory of Open Access Journals (Sweden)

    Davide Brunelli

    2016-01-01

    Full Text Available Monitoring environmental parameters in data centers is gathering nowadays increasing attention from industry, due to the need of high energy efficiency of cloud services. We present the design and the characterization of an energy neutral embedded wireless system, prototyped to monitor perpetually environmental parameters in servers and racks. It is powered by an energy harvesting module based on Thermoelectric Generators, which converts the heat dissipation from the servers. Starting from the empirical characterization of the energy harvester, we present a power conditioning circuit optimized for the specific application. The whole system has been enhanced with several sensors. An ultra-low-power micro-controller stacked over the energy harvesting provides an efficient power management. Performance have been assessed and compared with the analytical model for validation.

  20. Monitoring for materials fatigue in nuclear power plant

    International Nuclear Information System (INIS)

    Bartonicek, J.; Hienstorfer, W.

    1991-01-01

    The pressurizer surge line in unit 1 of the GKN nuclear power station belongs to the safety-relevant systems that have been monitored since the year 1987. The results of this in-service monitoring period show this component part experiences temperature fluctuations that have not been specified in the design documents of GKN 1. The in-service monitoring revealed both local and global temperature changes in the entire surge line, so that the resulting real stresses affecting the surge line can be derived and incorporated in a realistic fatigue analysis. (orig.) [de

  1. Power monitoring and control for large scale projects: SKA, a case study

    Science.gov (United States)

    Barbosa, Domingos; Barraca, João. Paulo; Maia, Dalmiro; Carvalho, Bruno; Vieira, Jorge; Swart, Paul; Le Roux, Gerhard; Natarajan, Swaminathan; van Ardenne, Arnold; Seca, Luis

    2016-07-01

    Large sensor-based science infrastructures for radio astronomy like the SKA will be among the most intensive datadriven projects in the world, facing very high demanding computation, storage, management, and above all power demands. The geographically wide distribution of the SKA and its associated processing requirements in the form of tailored High Performance Computing (HPC) facilities, require a Greener approach towards the Information and Communications Technologies (ICT) adopted for the data processing to enable operational compliance to potentially strict power budgets. Addressing the reduction of electricity costs, improve system power monitoring and the generation and management of electricity at system level is paramount to avoid future inefficiencies and higher costs and enable fulfillments of Key Science Cases. Here we outline major characteristics and innovation approaches to address power efficiency and long-term power sustainability for radio astronomy projects, focusing on Green ICT for science and Smart power monitoring and control.

  2. Monitoring of emissions and immissions from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, H J [Rheinisch-Westfaelisches Elektrizitaetswerk A.G., Biblis (Germany, F.R.). Betriebsverwaltung

    1977-02-01

    The measurement of the emission and immission of radionuclides from nuclear power stations has already been established with the inception of the peaceful uses of atomic energy. Since then it has been a firm feature of the monitoring of effects of nuclear power plants on the environment. The considerations and procedures on which the measurement programs are based are described. The ecological behaviour of radionuclides is illustrated with the aid of examples.

  3. Cutting device for spent local power range monitor

    International Nuclear Information System (INIS)

    Watanabe, Shigeru; Tsuji, Teruaki.

    1976-01-01

    Purpose: To prevent radioactive contamination of the reactor water and simplify the operation of transferring the spent local power range monitor to a pool and preparation of the space for storing the monitor in the pool by arranging it such that the monitor is cut in the reactor water and that its cut end is closed in the reactor water. Constitution: A device for clamping a spent local power range monitor disposed within the reactor core and for cutting the monitor such that the content will not be exposed are supported by support means such that they are spaced apart in the vertical direction, and the support means is suspended in the reactor water such that it is movable relative to the monitor. Thus, there is no need to mount the cutter in any separately provided support means, and there is no possibility of exposure of the content since the cut end of the monitor is closed by the outer frame. It is therefore possible to prevent contamination of the reactor water. (Horiuchi, T.)

  4. Microcontroller based multi-channel ultrasonic level monitoring system

    International Nuclear Information System (INIS)

    Ambastha, K.P.; Chaudhari, Y.V.; Singh, Inder Jeet; Chadda, V.K.

    2004-01-01

    Microcontroller based Multi-channel Ultrasonic Level Monitoring System developed by Computer Division is based on echo ranging techniques to monitor level. The transmitter directs an ultrasonic burst towards the liquid, which gets reflected from the top of the liquid surface. The time taken for ultrasound to travel from the transmitter to the top of liquid surface is measured and used to calculate the liquid level. The system provides for temperature compensation for accurate measurement as the ultrasound velocity depends on the ambient temperature. It can measure liquid level up to 5 meters. A single monitor can be used to measure level in 6 tanks. PC connectivity has been provided via RS 232 and RS 485 for remote operation and data logging of level. A GUI program developed using LABVIEW package displays level on PC monitor. The program provides for pictorial as well as numerical display for level and temperature in the front panel on the PC monitor. A user can monitor level for any or all tanks from the PC. One unit is installed at CIRUS for measuring level in Acid/ Alkali tanks and one is installed at APSARA for measuring water level in the reactor pool. (author)

  5. Assessing Power Monitoring Approaches for Energy and Power Analysis of Computers

    OpenAIRE

    El Mehdi Diouria, Mohammed; Dolz Zaragozá, Manuel Francisco; Glückc, Olivier; Lefèvre, Laurent; Alonso, Pedro; Catalán Pallarés, Sandra; Mayo, Rafael; Quintana Ortí, Enrique S.

    2014-01-01

    Large-scale distributed systems (e.g., datacenters, HPC systems, clouds, large-scale networks, etc.) consume and will consume enormous amounts of energy. Therefore, accurately monitoring the power dissipation and energy consumption of these systems is more unavoidable. The main novelty of this contribution is the analysis and evaluation of different external and internal power monitoring devices tested using two different computing systems, a server and a desktop machine. Furthermore, we prov...

  6. Monitoring levels of preservative sensitivity in Europe

    DEFF Research Database (Denmark)

    Wilkinson, J D; Shaw, S; Andersen, Klaus Ejner

    2002-01-01

    A 10-year multicentre analysis of the frequency of sensitivity to common preservatives collected in 16 centres in 11 countries has shown stable but persisting high levels of sensitivity to formaldehyde and 5-chloro-2-methyl-4-isothiazolin-3-one + 2-methyl-4-isothiazolin-3-one (MCI/MI). It has also...

  7. Development of an Ion Chamber for Monitoring the Containment of a Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Song, Tae-Yung; Kim, Han-Soo; Park, Se-Hwan; Ha, Jang-Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-05-15

    Nuclear power plants need many different types of radiation detectors for different purposes. Neutron detectors are installed inside and outside of the core to check the neutron flux. Scintillation detectors are used to check the fission products included in the liquids and gases of plant system. Geiger-Mueller counters are used for the area radiation monitoring. In addition to the above-mentioned detectors, ion chambers are installed to monitor radiation level of the containment. A few ion chambers are located within the reactor containment to monitor radiation level of an accident case. Therefore, the ion chamber should be capable of monitoring high level radiation dose up to 10{sup 7} R/h. Korea Atomic Energy Research Institute (KAERI) developed an ion chamber for monitoring the radiation dose inside the containment.

  8. Management of the high-level nuclear power facilities

    International Nuclear Information System (INIS)

    Preda, Marin

    2003-05-01

    This thesis approaches current issues in the management of the high power nuclear facilities and as such it appears to be important particularly for nuclear power plant operation topics. Of special interest are the failure events entailing possible catastrophic situations. The contents is structured onto ten chapters. The first chapter describes the operation regimes of the nuclear high power facilities. Highlighted here are the thesis scope and the original features of the work. The second chapter deals with operational policies developed in order to ensure the preventive maintenance of the nuclear installations. Also managing structures are described devoted to practical warranting the equipment safety function of non-classical power stations. In the third chapter cases of nuclear accidents are analyzed especially stressing the probabilistic risk and the operation regimes having in view the elimination of catastrophic events. In the fourth and fifth chapters the control of nuclear radiation emission is treated focusing the quality issue of nuclear installations required to avoid hazardous effects at level of nuclear reactor operation stage. At the same time set of operational measures is given here for preventing risks, catastrophes and chaotic situations. The chapter five presents both theoretical and practical approaches of the nuclear reactor core management concerning particularly the fuel testing, the water primary system and the quality of the involved equipment. In the sixth and seventh chapters issues of risk-quality correlations are approached as well as the structure of expert systems for monitoring the operational regimes of nuclear facilities. The efficiency of the power systems with nuclear injection is discussed and some original ideas developed in this work are evidenced in the eighth and ninth chapters. Presented are here both the operational principles and models of raising the efficiency of the interconnected nuclear stations and prices' policy

  9. Monitor and control device in a nuclear power plant

    International Nuclear Information System (INIS)

    Neda, Toshikatsu.

    1980-01-01

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

  10. Vibration monitoring of pressure vessel in Atucha-1 power plant

    International Nuclear Information System (INIS)

    Belinco, C.; Pastorini, A.; Martin Ghiselli, A.; Sacchi, M.

    1994-01-01

    The Vibration Monitoring Systems are described to obtain information about the mechanical state of different components in the main coolant system of nuclear power plants to ensure that changes in the mechanical integrity of this components are detected at an early point in time, even during operation. 9 figs

  11. User guide to power management for PCs and monitors

    Energy Technology Data Exchange (ETDEWEB)

    Nordman, B.; Piette, M.A.; Kinney, K.; Webber, C. [Lawrence Berkeley National Lab., CA (United States). Environmental Energy Technologies Div.

    1997-01-01

    Power management of personal computers (PCs) and monitors has the potential to save significant amounts of electricity as well as deliver other economic and environmental benefits. The Environmental Protection Agency`s ENERGY STAR{reg_sign} program has transformed the PC market so that equipment capable of power management is now widely available. However, previous studies have found that many Energy Star compliant computer systems are not accomplishing energy savings. The principal reasons for this are systems not being enabled for power management or a circumstance that prevents power management from operating. This guide is intended to provide information to computer support workers to increase the portion of systems that successfully power manage. The guide introduces power management concepts and the variety of benefits that power management can bring. It then explains how the parts of a computer system work together to enter and leave power management states. Several common computer system types are addressed, as well as the complications that networks bring to power management. Detailed instructions for checking and configuring several system types are provided, along with trouble shooting advice. The guide concludes with a discussion of how to purchase Energy Star compliant systems and future directions for power management of PCs and related equipment.

  12. Workshop on power plant cable condition monitoring: Proceedings

    International Nuclear Information System (INIS)

    Del Valle, L.

    1988-07-01

    A three-day workshop on cable condition monitoring was held in San Francisco on Fegruary 16--18, 1988. The workshop was cosponsored by the Nuclear Power, Electrical Systems, and Coal Combustion Systems Divisions of the Electric Power Research Institute. The primary objective of the workshop was to identify the state-of-the-art for cable condition monitoring. Twenty-five technical papers as well as EPRI research programs were presented at the technical sessions. Four working group sessions and one general session were held on each of two days. Each group session provided a forum for participants to exchange ideas and to discuss in more depth research for cable condition monitoring, existing and innovative testing technology, and utility and NRC needs for testing. Recommendations from the working groups were summarized and presented at the end of the workshop

  13. Negotiation and Monitoring of Service Level Agreements

    Science.gov (United States)

    Quillinan, Thomas B.; Clark, Kassidy P.; Warnier, Martijn; Brazier, Frances M. T.; Rana, Omer

    Service level agreements (SLAs) provide a means to define specific Quality of Service (QoS) guarantees between providers and consumers of services. Negotiation and definition of these QoS characteristics is an area of significant research. However, defining the actions that take place when an agreement is violated is a topic of more recent focus. This paper discusses recent advances in this field and propose some additional features that can help both consumers and producers during the enactment of services. These features include the ability to (re)negotiate penalties in an agreement, and specifically focuses on the renegotiation of penalties during enactment to reflect ongoing violations.

  14. Concept of voltage monitoring for a nuclear power plant emergency power supply system (PWR 1300 MWe)

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1988-01-01

    Voltage monitoring concept for a Nuclear Power Plant Emergency Power Supply Systems (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and 3 NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  15. Real Time Monitoring and Wear Out of Power Modules

    DEFF Research Database (Denmark)

    Ghimire, Pramod

    the expected lifetime of converters. Real time monitoring of power modules is very important together with a smart control and a driving technique in a converter. This ensures to operate the device within a safe operating area and also to protect from a catastrophic failure. Furthermore, the inherent physical...... and in a mission-profile oriented advanced power cycling test. The measurement technique is implemented in a full scale converter under field oriented test conditions. Initially, a real time measurement technique and it's implementation in a converter are introduced. A full scale converter is also used......Power electronic devices have a wide range of applications from very low to high power at constantly varying load conditions. Irrespective of the harsh operating loads, including both internal and external, an improvement in a performance such as efficiency, power density, reliability and cost...

  16. Calibration of radiation monitors at nuclear power plants

    International Nuclear Information System (INIS)

    Boudreau, L.; Miller, A.D.; Naughton, M.D.

    1994-03-01

    This work was performed to provide guidance to the utilities in the primary and secondary calibration of the radiation monitoring systems (RMS) installed in nuclear power plants. These systems are installed in nuclear power plants to monitor ongoing processes, identify changing radiation fields, predict and limit personnel radiation exposures and measure and control discharge of radioactive materials to the environment. RMS are checked and calibrated on a continuing basis to ensure their precision and accuracy. This report discusses various approaches towards primary and secondary calibrations of the RMS equipment in light of accepted practices at typical power plants and recent interpretations of regulatory guidance. Detailed calibration techniques and overall system responses, trends, and practices are discussed. Industry, utility, and regulatory sources were contacted to create an overall consensus of the most reasonable approaches to optimizing the performance of this equipment

  17. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-12-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations.

  18. New technologies in nuclear power plant monitoring and diagnosis

    International Nuclear Information System (INIS)

    Turkcan, E.; Verhoef, J.P.; Ciftcioglu, O.

    1996-01-01

    Several representative new technologies being introduce for monitoring and diagnosis in nuclear power plants (NPP) are presented in this paper. In Sec. 2, the Kalman filtering is briefly described and it relevance to conventional time series analysis methods are emphasized. In this respect, its NPP monitoring and fault diagnosis implementations are given and the important features are pointed out. In Sec. 3, the NN technology is briefly described and the scope is focused on the NPP monitoring and fault diagnosis implementations. In Sec. 4, the wavelet technology is briefly described and the utilization of this technology in Nuclear Technology is exemplified. In this respect, also the prospective role of this technology for real-time monitoring and fault diagnosis is revealed. (author). 33 refs, 6 figs

  19. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations

  20. New technologies in nuclear power plant monitoring and diagnosis

    Energy Technology Data Exchange (ETDEWEB)

    Turkcan, E; Verhoef, J P [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Ciftcioglu, O [Istanbul Technical Univ., Istanbul (Turkey). Nuclear Power Dept.

    1997-12-31

    Several representative new technologies being introduce for monitoring and diagnosis in nuclear power plants (NPP) are presented in this paper. In Sec. 2, the Kalman filtering is briefly described and it relevance to conventional time series analysis methods are emphasized. In this respect, its NPP monitoring and fault diagnosis implementations are given and the important features are pointed out. In Sec. 3, the NN technology is briefly described and the scope is focused on the NPP monitoring and fault diagnosis implementations. In Sec. 4, the wavelet technology is briefly described and the utilization of this technology in Nuclear Technology is exemplified. In this respect, also the prospective role of this technology for real-time monitoring and fault diagnosis is revealed. (author). 33 refs, 6 figs.

  1. Threshold self-powered gamma detector for use as a nuclear reactor power monitor

    International Nuclear Information System (INIS)

    LeVert, F.E.

    1977-01-01

    A study of a threshold self-powered gamma detector for use as a nuclear reactor power monitor was conducted. Measurements were performed to ascertain whether certain detector material arrangements could be used to obtain significant discrimination against low energy gammas. Results indicating agreement between detector response and reactor power output are presented. Evidence of rejection of low energy gammas by the detector is presented. The simplicity of construction and ruggedness of the detector are also discussed

  2. Portable Water Level Monitoring System via SMS

    Directory of Open Access Journals (Sweden)

    Jomar S. Vitales

    2015-11-01

    Full Text Available Damages and lives taken by the typhoon Ondoy and other super typhoons brought the researchers to think and develop a device that warns people an hour or more than an hour before the devastating phenomena. In this project the researchers have thought of using text messaging in which the country’s leading means of communication. The development of the project was guided by the Engineering Design Cycle of Dr. Allan Cheville in his book entitled “Rocket Engineering”. The researchers have identified and used the needed materials which are suited in the intended function of the project. The project was already evaluated and had gathered a favorable response from the knowledgeable respondents in the field where the design project is intended to use. The project has a high acceptability level in the respondents’ point of view. The researchers are highly recommending the implementation of the project for a better testing in the incoming rainy season and also recommending to be placed in the Pantalan Bridge in Pantalan, Nasugbu, Batangas, Philippines. The researchers are also suggesting another study for a better water proof casing of the project.

  3. The Relationship with Self Esteem Between Self Monitoring Levels of Sub Elite In - Door Soccer Players

    Directory of Open Access Journals (Sweden)

    Mehmet Behzat T U R A N

    2015-07-01

    Full Text Available The aim of this study was to investigate the relationship with self - esteem between self monitoring levels of sub - elite in - door soccer players. For this aim, 86 male and 91 female athletes at the ages of 18 – 28 years were participated in this study voluntarily. The participants were studying at 7 different universities that join ed the in - door soccer championship of Turkish University Sport Federati on. The Socio - demographic data form, Self - monitoring Scale , and Coopersmith Self - Esteem Inventory were performed by the participants. The d ata was analyzed by using IBM SPSS (version 20.0. The Spearman Correlation parameter calculated in order to comment the relationship with data, Multiple regret ion analysis were performed for the predictive power of self - esteem for self monitoring levels of the participants. According to the analysis, a negative relationship was found among self - esteem, self - monitoring total score , and extraversion levels . A nd it was found that self - esteem levels predictived self monitoring levels substantially. It was found that the s elf - monitoring and extraversion affected self - esteem negatively, it was thought that highly self - esteem ed athletes have a tendency to see themselves as superior than the other athletes, ignore the extraneous criticism. No matter what self - esteem levels is that extraversion and acting altitute (attitude ? has not change. Consequently, self - esteem has revers e relationship with self - monitoring properties since trainers and teachers both is raised self - esteem and is helped self - monitoring themselves.

  4. Research on intelligent monitor for 3D power distribution of reactor core

    International Nuclear Information System (INIS)

    Xia, Hong; Li, Bin; Liu, Jianxin

    2014-01-01

    Highlights: • Core power distribution of ex-core measurement system has been reconstructed. • Building up an artificial intelligence model for 3-D core power distribution. • Error of the experiments has been reduced to 0.76%. • Methods for improving the accuracy of the model have been obtained. - Abstract: A real-time monitor for 3D reactor power distribution is critical for nuclear safety and high efficiency of NPP’s operation as well as for optimizing the control system, especially when the nuclear power plant (NPP) works at a certain power level or it works in load following operation. This paper was based on analyzing the monitor for 3D reactor power distribution technologies used in modern NPPs. Furthermore, considering the latest research outcomes, the paper proposed a method based on using an ex-core neutron detector system and a neural network to set up a real time monitor system for reactor’s 3D power distribution supervision. The results of the experiments performed on a reactor simulation machine illustrated that the new monitor system worked very well for a certain burn-up range during the fuel cycle. In addition, this new model could reduce the errors associated with the fitting of the distribution effectively, and several optimization methods were also obtained to improve the accuracy of the simulation model

  5. UARS Particle Environment Monitor (PEM) Level 3TP V001

    Data.gov (United States)

    National Aeronautics and Space Administration — The Particle Environment Monitor (PEM) Level 3TP data product consists of daily, 65.536 second and 2.048 interval time-ordered, vertical profiles of electron and...

  6. Architectures of Remote Monitoring Systems for a Nuclear Power Plant

    International Nuclear Information System (INIS)

    Choi, Yoo Rark; Lee, Jae Cheol; Kim, Jae Hee

    2006-01-01

    Aina(Artificial Intelligence for Nuclear Applications) have developed remote monitoring systems since the 1990's. We have been interested in the safety of reactor vessel, steam generator, pipes, valves and pumps. We have developed several remote inspection systems and will develop some remote care systems for a nuclear power plant. There were critical problems for building remote monitoring systems for mass data processing and remote user interface techniques in the middle of the 1990's. The network capacity wasn't sufficient to transfer the monitoring data to a remote computer. Various computer operating systems require various remote user interfaces. Java provides convenient and powerful interface facilities and the network transfer speed was increased greatly in the 2000's. Java is a good solution for a remote user interface but it can't work standalone in remote monitoring applications. The restrictions of Java make it impossible to build real time based applications. We use Java and a traditional language to improve this problem. We separate the remote user interface and the monitoring application

  7. Tools for monitoring and diagnosis of power Transformers

    International Nuclear Information System (INIS)

    Borsi, H.; Gockenbach, E.

    1999-05-01

    For an optimised maintenance as well as damage prevention and a prediction of further life expectancy the knowledge of the insulation condition of power transformers can be estimated using monitoring systems. In this paper a monitoring method based on a new system for an on-line measurement of P D and undissolved gases on transformers is presented. A modular structured system is introduced which is able to analyse the statistical characteristics of broadband measured P D-pulses by using digital signal processing. Furthermore a new developed electronic Buchholzrelay for the detection of undissolved gases will be described which allows a diagnosis of the insulation and a protection of the transformer

  8. Westinghouse power distribution monitoring experience at Duke Power's McGuire Unit 1

    International Nuclear Information System (INIS)

    Grobmyer, L.R.; Cash, M.T.; Kitlan, M.S.; Impink, A.J. Jr.

    1987-01-01

    In the evolution of the Westinghouse methodology of assuring safe core power distributions, emphasis was placed on analysis and not on continuous detailed core monitoring. Power distribution monitoring is currently achieved by periodic surveillances using the movable in-core detector system (MIDS) and by continuous observations of the two-section excore power range detectors. Control of the power distribution is regulated by limits on the indications from these systems, by limits on control rod insertion, and by operational constraints on the position indication systems. As more plants come on line and as more utilities take over the fuel design function for themselves, the desire for better core monitoring becomes evident. Also, the need and desire by the utilities to have more control over their operating margin has motivated the industry to offer and/or upgrade core monitoring systems. Westinghouse and Duke Power are participants in a joint development program to finalize the development of the core on-line surveillance monitoring and operations system (COSMOS). This final stage of development consists of prototype field trials at the McGuire Nuclear Plant. The purpose of the prototype program is to determine how well the design objectives are met and how to improve the system based on the operating experience at McGuire. Another purpose of this prototype program is to generate the necessary experience and information to develop a topical report for the US Nuclear Regulatory Commission to obtain a licensing basis for technical specification relaxation

  9. 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

  10. Electrical power distribution control methods, electrical energy demand monitoring methods, and power management devices

    Science.gov (United States)

    Chassin, David P [Pasco, WA; Donnelly, Matthew K [Kennewick, WA; Dagle, Jeffery E [Richland, WA

    2011-12-06

    Electrical power distribution control methods, electrical energy demand monitoring methods, and power management devices are described. In one aspect, an electrical power distribution control method includes providing electrical energy from an electrical power distribution system, applying the electrical energy to a load, providing a plurality of different values for a threshold at a plurality of moments in time and corresponding to an electrical characteristic of the electrical energy, and adjusting an amount of the electrical energy applied to the load responsive to an electrical characteristic of the electrical energy triggering one of the values of the threshold at the respective moment in time.

  11. Nuclear power and low level radiation hazards

    International Nuclear Information System (INIS)

    Myers, D.K.; Newcombe, H.B.

    1979-03-01

    Even in the future, nuclear power is expected to contribute less than 1/10th of the present total population exposure to man-made radiation. By the best estimates available, the current health risks of nuclear power generation appear to be much less than those associated with the major alternative sources of energy, with the exception of natural gas which is about equally safe. Uncertainties concerning the radiation risks from nuclear power, from medical x-rays and from the effects of reduced ventillation to conserve heat appear to be less than those associated with estimates of risks from the use of coal and various other sources of energy. This is in part because of the large amount of effort devoted to studies of radiation effects. The benefits in terms of current life expectancy associated with any of the conventional or unconventional methods of power production appear to greatly outweigh the associated current health hazards. (author)

  12. Advanced targeted monitoring of high temperature components in power plants

    Energy Technology Data Exchange (ETDEWEB)

    Roos, E.; Maile, K.; Jovanovic, A. [MPA Stuttgart (Germany)

    1998-12-31

    The article presents the idea of targeted monitoring of high-temperature pressurized components in fossil-fueled power plants, implemented within a modular software system and using, in addition to pressure and temperature data, also displacement and strain measurement data. The concept has been implemented as a part of a more complex company-oriented Internet/Intranet system of MPA Stuttgart (ALIAS). ALIAS enables to combine smoothly the monitoring results with those of the off-line analysis, e. g. sensitivity analyses, comparison with preceding experience (case studies), literature search, search in material databases -(experimental and standard data), nonlinear FE-analysis, etc. The concept and the system have been implemented in real plant conditions several power plants in Germany and Europe: one of these applications and its results are described more in detail in the presentation. (orig.) 9 refs.

  13. Advanced targeted monitoring of high temperature components in power plants

    Energy Technology Data Exchange (ETDEWEB)

    Roos, E; Maile, K; Jovanovic, A [MPA Stuttgart (Germany)

    1999-12-31

    The article presents the idea of targeted monitoring of high-temperature pressurized components in fossil-fueled power plants, implemented within a modular software system and using, in addition to pressure and temperature data, also displacement and strain measurement data. The concept has been implemented as a part of a more complex company-oriented Internet/Intranet system of MPA Stuttgart (ALIAS). ALIAS enables to combine smoothly the monitoring results with those of the off-line analysis, e. g. sensitivity analyses, comparison with preceding experience (case studies), literature search, search in material databases -(experimental and standard data), nonlinear FE-analysis, etc. The concept and the system have been implemented in real plant conditions several power plants in Germany and Europe: one of these applications and its results are described more in detail in the presentation. (orig.) 9 refs.

  14. Technology and Power. A Foucauldian Analysis of Electronic Monitoring Discourses

    OpenAIRE

    Anna Vitores; Miquel Domènech

    2007-01-01

    The article aims to show the importance of FOUCAULT within social studies of science and technology. It also illustrates how a Foucauldian analysis can be useful for studies of science, technology and society focused on power effects. To accomplish these objectives we analyze the emergence of a specific techno-scientific innovation: the electronic monitoring of offenders. We map the discontinuities and discourse dispersions linked to those practices that constitute different materializations ...

  15. A Digital Power Quality Monitoring Equipment Designed for Digital Substation

    Science.gov (United States)

    Li, Wei; Wang, Xin; Geng, Jiewen

    2018-01-01

    Taking into account both current status and development trend of digital substation, this paper proposed a design of a new multi-channelled digital power quality monitoring equipment with high compatibility. The overall functional structure, hardware architecture, software architecture, interface architecture and some key techniques such as IEC 61850 modelling of transient event and harmonic measurement method under the condition of non-synchronous sampling are described in this paper.

  16. Power distribution monitoring and control in 500 MWe PHWR

    International Nuclear Information System (INIS)

    Kumar, A.

    1996-01-01

    The 500 MWe Indian Pressurized Heavy Water Reactor (PHWR) is expected to be commissioned in a few years. It has a relatively large sized core with complex material distribution in comparison to the currently operating 220 MWe PHWRs. The resulting neutronically loosely coupled system demands continuous control of the core power distribution. This paper gives a brief description and analysis of the reactor monitoring and control system proposed for this reactor. (author). 11 refs, 8 figs, 3 tabs

  17. New reactor safety circuit for low-power-level operation

    International Nuclear Information System (INIS)

    McDowell, W.P.; Keefe, D.J.; Rusch, G.K.

    1978-01-01

    In the operation of nuclear reactors at low-power levels, one of the primary instrumentation problems is that the statistical fluctuations of reactor neutron population are accentuated by conventional log-count-rate and differentiating circuits and can cause frequent spurious scrams unless long time constants are incorporated in the circuit. Excessive time constants may introduce undesirable delay in the circuit response to legitimate scram signals. The paper develops the concept of a count doubling-time monitor which generates a scram signal if the number of counts from a pulse type neutron detector doubles in a given period of time. The paper demonstrates the theoretical relation between count doubling time and asymptomatic periods. A practical circuit to implement the function is described

  18. Development of Core Monitoring System for Nuclear Power Plants (I)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.H.; Kim, Y.B.; Park, M.G; Lee, E.K.; Shin, H.C.; Lee, D.J. [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    1997-12-31

    1.Object and Necessity of the Study -The main objectives of this study are (1)conversion of APOLLO version BEACON system to HP-UX version core monitoring system, (2)provision of the technical bases to enhance the in-house capability of developing more advanced core monitoring system. 2.Results of the Study - In this study, the revolutionary core monitoring technologies such as; nodal analysis and isotope depletion calculation method, advanced schemes for power distribution control, and treatment of nuclear databank were established. The verification and validation work has been successfully performed by comparing the results with those of the design code and measurement data. The advanced graphic user interface and plant interface method have been implemented to ensure the future upgrade capability. The Unix shell scripts and system dependent software are also improved to support administrative functions of the system. (author). 14 refs., 112 figs., 52 tabs.

  19. Converter Monitoring Unit for Retrofit of Wind Power Converters

    DEFF Research Database (Denmark)

    Rannestad, Bjorn; Maarbjerg, Anders Eggert; Frederiksen, Kristian

    2018-01-01

    A Converter Monitoring Unit (CMU), which will enable condition monitoring of wind turbine converters is presented in this paper. Reducing the cost of corrective maintenance by means of condition monitoring is a way of lowering Operation & Maintenance (O&M) costs for wind turbine systems....... The CMU must be able to detect a broad range of failure modes related to Insulated Gate Bipolar Transistor (IGBT) power modules and associated gate drives. IGBT collector-emitter on-state voltage (vceon) and current (ic) is sampled in the CMU and used for detection of emerging failures. A new method...... for compensation of unwanted inductive voltage drop in the vceon measurement path is presented, enabling retrofitting of CMUs in existing wind turbines. Finally, experimental results obtained on a prototype CMU are presented. Experimentally the vceon dependency to IGBT junction temperature and deterioration...

  20. Accounting for complementarity to maximize monitoring power for species management.

    Science.gov (United States)

    Tulloch, Ayesha I T; Chadès, Iadine; Possingham, Hugh P

    2013-10-01

    To choose among conservation actions that may benefit many species, managers need to monitor the consequences of those actions. Decisions about which species to monitor from a suite of different species being managed are hindered by natural variability in populations and uncertainty in several factors: the ability of the monitoring to detect a change, the likelihood of the management action being successful for a species, and how representative species are of one another. However, the literature provides little guidance about how to account for these uncertainties when deciding which species to monitor to determine whether the management actions are delivering outcomes. We devised an approach that applies decision science and selects the best complementary suite of species to monitor to meet specific conservation objectives. We created an index for indicator selection that accounts for the likelihood of successfully detecting a real trend due to a management action and whether that signal provides information about other species. We illustrated the benefit of our approach by analyzing a monitoring program for invasive predator management aimed at recovering 14 native Australian mammals of conservation concern. Our method selected the species that provided more monitoring power at lower cost relative to the current strategy and traditional approaches that consider only a subset of the important considerations. Our benefit function accounted for natural variability in species growth rates, uncertainty in the responses of species to the prescribed action, and how well species represent others. Monitoring programs that ignore uncertainty, likelihood of detecting change, and complementarity between species will be more costly and less efficient and may waste funding that could otherwise be used for management. © 2013 Society for Conservation Biology.

  1. Wide Area Measurement Based Security Assessment & Monitoring of Modern Power System: A Danish Power System Case Study

    DEFF Research Database (Denmark)

    Rather, Zakir Hussain; Chen, Zhe; Thøgersen, Paul

    2013-01-01

    Power System security has become a major concern across the global power system community. This paper presents wide area measurement system (WAMS) based security assessment and monitoring of modern power system. A new three dimensional security index (TDSI) has been proposed for online security...... monitoring of modern power system with large scale renewable energy penetration. Phasor measurement unit (PMU) based WAMS has been implemented in western Danish Power System to realize online security monitoring and assessment in power system control center. The proposed security monitoring system has been...

  2. Use of a microprocessor in a remote working level monitor

    International Nuclear Information System (INIS)

    Keffe, D.J.; McDowell, W.P.; Groer, P.G.

    1975-01-01

    A remote working level monitor was designed to measure short-lived radon-daughter concentrations in sealed chambers having potentially high radiation levels (up to 2000 WL). The system is comprised of surface barrier detectors, multiplexer and buffers, microprocessor and teletype

  3. Threshold self-powered gamma detector for use as a monitor of power in a nuclear reactor

    Science.gov (United States)

    LeVert, Francis E.; Cox, Samson A.

    1978-01-01

    A self-powered gamma monitor for placement near the core of a nuclear reactor comprises a lead prism surrounded by a coaxial thin nickel sheet, the combination forming a collector. A coaxial polyethylene electron barrier encloses the collector and is separated from the nickel sheet by a vacuum region. The electron barrier is enclosed by a coaxial stainless steel emitter which, in turn, is enclosed within a lead casing. When the detector is placed in a flux of gamma rays, a measure of the current flow in an external circuit between emitter and collector provides a measure of the power level of the reactor.

  4. Threshold self-powered gamma detector for use as a monitor of power in a nuclear reactor

    International Nuclear Information System (INIS)

    LeVert, F.E.; Cox, S.A.

    1978-01-01

    A self-powered gamma monitor for placement near the core of a nuclear reactor comprises a lead prism surrounded by a coaxial thin nickel sheet, the combination forming a collector. A coaxial polyethylene electron barrier encloses the collector and is separated from the nickel sheet by a vacuum region. The electron barrier is enclosed by a coaxial stainless steel emitter which, in turn, is enclosed within a lead casing. When the detector is placed in a flux of gamma rays, a measure of the current flow in an external circuit between emitter and collector provides a measure of the power level of the reactor

  5. Type GQS-1 high pressure steam manifold water level monitoring system

    International Nuclear Information System (INIS)

    Li Nianzu; Li Beicheng; Jia Shengming

    1993-10-01

    The GQS-1 high pressure steam manifold water level monitoring system is an advanced nuclear gauge that is suitable for on-line detecting and monitor in high pressure steam manifold water level. The physical variable of water level is transformed into electrical pulses by the nuclear sensor. A computer is equipped for data acquisition, analysis and processing and the results are displayed on a 14 inch color monitor. In addition, a 4 ∼ 20 mA output current is used for the recording and regulation of water level. The main application of this gauge is for on-line measurement of high pressure steam manifold water level in fossil-fired power plant and other industries

  6. Simulation Based Data Reconciliation for Monitoring Power Plant Efficiency

    International Nuclear Information System (INIS)

    Park, Sang Jun; Heo, Gyun Young

    2010-01-01

    Power plant efficiency is analyzed by using measured values, mass/energy balance principles, and several correlations. Since the measured values can have uncertainty depending on the accuracy of instrumentation, the results of plant efficiency should definitely have uncertainty. The certainty may occur due to either the randomness or the malfunctions of a process. In order to improve the accuracy of efficiency analysis, the data reconciliation (DR) is expected as a good candidate because the mathematical algorithm of the DR is based on the first principles such as mass and energy balance considering the uncertainty of instrumentation. It should be noted that the mass and energy balance model for analyzing power plant efficiency is equivalent to a steady-state simulation of a plant system. Therefore the DR for efficiency analysis necessitates the simulation which can deal with the uncertainty of instrumentation. This study will propose the algorithm of the simulation based DR which is applicable to power plant efficiency monitoring

  7. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

    International Nuclear Information System (INIS)

    2002-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000

  8. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

    International Nuclear Information System (INIS)

    2001-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999

  9. Study on intermediate frequency power supply automatic monitor system

    International Nuclear Information System (INIS)

    Wang Yuntong; Xu Bin

    2007-06-01

    A new design project of the automatic monitor system for the intermediate frequency power supply system by using the communication server is put for- ward and the realizing principle method and the key technique are clarified in detail. This system made use of the conversion function with the series communication server's control, realized the data collecting function by the double machine backup and redundancy. The new network system adopted the photoelectric-insulated-communication connect device and the diagnosis technique, increased the anti-interference ability, the communication adopted the technique by the alarm information sending out in first and circularly repeating, the slowly speed is overcame in the original monitor network system, and strengthened the celerity of the monitor system and the reliability of the alarm report. After the new monitor system running, the result shows that the functions is more perfect than the original monitor system, the usage is more convenient, have the higher and dependable stability, the report of alarm is more quickly, and is convenient for the analysis after the trouble, at the same time, the system still have the strong ability and value to expand. (authors)

  10. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-12-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999.

  11. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-12-31

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000.

  12. Monitoring of raptors and their contamination levels in Norway.

    Science.gov (United States)

    Gjershaug, Jan Ove; Kålås, John Atle; Nygård, Torgeir; Herzke, Dorte; Folkestad, Alv Ottar

    2008-09-01

    This article summarizes results from raptor monitoring and contamination studies in Norway of the golden eagle, gyrfalcon, white-tailed sea eagle, osprey, peregrine, and merlin. Golden eagle and gyrfalcon populations have been monitored since 1990 as part of the "Monitoring Programme for Terrestrial Ecosystems" (TOV). No long-term trend in the population size or productivity of golden eagle has been shown in any of the 5 study areas. The reproductive output of gyrfalcon is monitored in 3 areas. It is positively correlated with the populations of its main prey species, the rock ptarmigan and the willow ptarmigan. The white-tailed sea eagle population has been monitored since 1974 by the Norwegian Ornithological Society, and the population is increasing. The levels of pesticides and polychlorinated biphenyls are low in the eggs of both the golden eagle and the gyrfalcon, but elevated levels and effects on reproduction have been indicated for a coastal subpopulation of golden eagle. The pollutant levels in white-tailed sea eagle are lower than in the Baltic population of sea eagles, and shell thinning was never severe overall, but individual eggs have contained pollutant concentrations above critical levels. The levels of pollutants in the bird-eating falcons, peregrine, and merlin were higher than in other species. New emerging pollutants, like brominated diphenylethers and perfluorinated organic compounds, could be detected in all species. By incorporating available published and unpublished data, we were able to produce time trends for pollutants and shell thickness over 4 decades.

  13. Sodium fast reactor power monitoring using gamma spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R.; Normand, S.; Barbot, L.; Domenech, T.; Kondrasovs, V.; Corre, G.; Frelin, A.M. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, CEA - Saclay DRT/LIST/DETECS/SSTM, Batiment 516 - P.C. no 72, Gif sur Yvette, F-91191 (France); Montagu, T.; Dautremer, T.; Barat, E. [CEA, LIST, Laboratoire Processus Stochastiques et Spectres (France); Ban, G. [ENSICAEN (France)

    2009-06-15

    This work deals with the use of high flux gamma spectrometry to monitor the fourth generation of sodium fast reactor (SFR) power. The simulation study part of this work has shown that power monitoring in a short time response and with a good accuracy is possible. An experimental test is under preparation at the French SFR Phenix experimental reactor to validate simulation studies. First, physical calculations have been done to correlate gamma activity to the released thermal power. Gamma emitter production rate in the reactor core was calculated with technical and nuclear data as the sodium velocity, the atomic densities, Phenix neutron spectrum and incident neutron cross-sections of reactions producing gamma emitters. A thermal hydraulic transfer function was used for modeling primary sodium flow in our calculations. For the power monitoring problematic, use of a short decay period gamma emitter will allow to have a very fast response system without cumulative effect. We have determined that the best tagging agent is 20F which emits 1634 keV energy photons with a decay period of 11 s. The gamma spectrum was determined by flux point and a pulse high tally MCNP5.1.40 simulation and shown the possibility to measure the signal of this radionuclide. The experiment will be set during the reactor 'end life testing'. The Delayed Neutron Detection (DND) room has been chosen as the best available location on Phenix reactor to measure this kind of radionuclide due to a short transit time from reactor core to measurement sample. This location is optimum for global power measurement because homogenized sampling in the reactor hot pool. The main spectrometer is composed of a coaxial high purity germanium diode (HPGe) coupled with a transistor reset preamplifier. The HPGe diode signal will be processed by the Adonis digital signal processing due to high flux and fast activity measurement. Post-processing softwares will be used to limit statistical problems of the

  14. Varying ultrasound power level to distinguish surgical instruments and tissue.

    Science.gov (United States)

    Ren, Hongliang; Anuraj, Banani; Dupont, Pierre E

    2018-03-01

    We investigate a new framework of surgical instrument detection based on power-varying ultrasound images with simple and efficient pixel-wise intensity processing. Without using complicated feature extraction methods, we identified the instrument with an estimated optimal power level and by comparing pixel values of varying transducer power level images. The proposed framework exploits the physics of ultrasound imaging system by varying the transducer power level to effectively distinguish metallic surgical instruments from tissue. This power-varying image-guidance is motivated from our observations that ultrasound imaging at different power levels exhibit different contrast enhancement capabilities between tissue and instruments in ultrasound-guided robotic beating-heart surgery. Using lower transducer power levels (ranging from 40 to 75% of the rated lowest ultrasound power levels of the two tested ultrasound scanners) can effectively suppress the strong imaging artifacts from metallic instruments and thus, can be utilized together with the images from normal transducer power levels to enhance the separability between instrument and tissue, improving intraoperative instrument tracking accuracy from the acquired noisy ultrasound volumetric images. We performed experiments in phantoms and ex vivo hearts in water tank environments. The proposed multi-level power-varying ultrasound imaging approach can identify robotic instruments of high acoustic impedance from low-signal-to-noise-ratio ultrasound images by power adjustments.

  15. BARC-risk monitor- a tool for operational safety assessment in nuclear power plants

    International Nuclear Information System (INIS)

    Vinod, Gopika; Saraf, R.K.; Babar, A.K.; Hadap, Nikhil

    2000-12-01

    Probabilistic safety assessment has become a key tool as on today to identify and understand nuclear power plant vulnerabilities. As a result of the availability of these PSA studies, there is a desire to use them to enhance plant safety and to operate the nuclear stations in the most efficient manner. Risk monitor is a PC based tool, which computes the real time safety level and assists plant personnel to manage day-to-day activities. Risk monitor is a PC based user friendly software tool used for modification and re-analysis of a nuclear power plant. Operation of risk monitor is based on PSA methods for assisting in day to day applications. Risk monitoring programs can assess the risk profile and are used to optimise the operation of nuclear power plants with respect to a minimum risk level over the operating time. This report presents the background activities of risk monitor, its application areas and also gives the status of such tools in international scenarios. The software is based on the PSA model of Kaiga generating station and would be applicable to similar design configuration. (author)

  16. Advanced Detection Technology of Trace-level Borate for SG Leakage Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seban; Kang, Dukwon; Kim, Seungil; Kim, Hyunki; Heo, Jun; Sung, Jinhyun [Radiation Eng. Center, Shihung (Korea, Republic of); Lee, Dongbum [Academic Support Dept., Seoul (Korea, Republic of)

    2013-05-15

    Many studies have been reported for monitoring technology of steam generator, however, all of these methods have their own limitations. The leakage monitoring technology of steam generator of PWR has also got a limit due to the adoption of specific radionuclides (N-16, Ar-41, H-3, Xe, etc.) generated by nuclear fission, which are available only when reactor output is 20% or more. Most of domestic NPPs apply the N-16 technique for monitoring tube leakage but it has some problem that it is difficult to calculate the leakage rate because neutron flux are not completely formed during low power operation. For example, tube leakage of steam generator occurred in the Uljin nuclear power plant in 2002 during coast down operation for periodic plant maintenance. This plant could not prevent a rupture accident in advance because N-16 method is not possible the leak monitoring less than 20% reactor power. The development of excellent alternative monitoring technology that can monitor the real-time leakage is required under a variety of operating conditions like start-up and abnormal conditions of NPPs. This study was performed to lay a foundation in monitoring the leakage of steam generator coping with the lower output and low power operational condition using trace level of boron which is non-radioactive nuclide to inject control neutron injection. In this study, non-radioactive nuclide boron ion, which existed in the secondary system water, as leakage monitoring indicator was investigated for the separation of complex cation and anion phase. Borate was detected by using borate concentrator column coupled with the ion-exclusion column analytical column, revealing the problem of overlapped peak between fluoride and boron ions. Meanwhile, ion-exchange column could confirm the possibility as a leakage monitoring indicator of steam generator, despite the peak of glycolic acid salts was slightly overlapped. It will be needed for further research regarding the selectivity of the

  17. Advanced Detection Technology of Trace-level Borate for SG Leakage Monitoring

    International Nuclear Information System (INIS)

    Lee, Seban; Kang, Dukwon; Kim, Seungil; Kim, Hyunki; Heo, Jun; Sung, Jinhyun; Lee, Dongbum

    2013-01-01

    Many studies have been reported for monitoring technology of steam generator, however, all of these methods have their own limitations. The leakage monitoring technology of steam generator of PWR has also got a limit due to the adoption of specific radionuclides (N-16, Ar-41, H-3, Xe, etc.) generated by nuclear fission, which are available only when reactor output is 20% or more. Most of domestic NPPs apply the N-16 technique for monitoring tube leakage but it has some problem that it is difficult to calculate the leakage rate because neutron flux are not completely formed during low power operation. For example, tube leakage of steam generator occurred in the Uljin nuclear power plant in 2002 during coast down operation for periodic plant maintenance. This plant could not prevent a rupture accident in advance because N-16 method is not possible the leak monitoring less than 20% reactor power. The development of excellent alternative monitoring technology that can monitor the real-time leakage is required under a variety of operating conditions like start-up and abnormal conditions of NPPs. This study was performed to lay a foundation in monitoring the leakage of steam generator coping with the lower output and low power operational condition using trace level of boron which is non-radioactive nuclide to inject control neutron injection. In this study, non-radioactive nuclide boron ion, which existed in the secondary system water, as leakage monitoring indicator was investigated for the separation of complex cation and anion phase. Borate was detected by using borate concentrator column coupled with the ion-exclusion column analytical column, revealing the problem of overlapped peak between fluoride and boron ions. Meanwhile, ion-exchange column could confirm the possibility as a leakage monitoring indicator of steam generator, despite the peak of glycolic acid salts was slightly overlapped. It will be needed for further research regarding the selectivity of the

  18. Towards upper power levels: thermonuclear fusion

    International Nuclear Information System (INIS)

    Vedel, Jean

    1983-01-01

    This paper is a brief introduction to the use of power lasers to achieve controlled thermonuclear fusion. After shortly describing thermonuclear fusion and the conditions of temperature, density and duration required it is showed how the laser enables such conditions to be created. The neodymium-doped glass laser NOVA that is being installed at the Livermore laboratory in the USA is described; at the time of its completion in 1984, this laser will be the most powerful in the world. In comparison, the OCTAL laser in operation at the Limeil establishment ''Centre d'Etudes'' of ''Commissariat Francais a l'Energie Atomique'' (the French atomic energy authority) is more modest; it is presented here [fr

  19. High power beam profile monitor with optical transition radiation

    International Nuclear Information System (INIS)

    Denard, J.C.; Piot, P.; Capek, K.; Feldl, E.

    1997-01-01

    A simple monitor has been built to measure the profile of the high power beam (800 kW) delivered by the CEBAF accelerator at Jefferson Lab. The monitor uses the optical part of the forward transition radiation emitted from a thin carbon foil. The small beam size to be measured, about 100 μm, is challenging not only for the power density involved but also for the resolution the instrument must achieve. An important part of the beam instrumentation community believes the radiation being emitted into a cone of characteristic angle 1/γ is originated from a region of transverse dimension roughly λγ; thus the apparent size of the source of transition radiation would become very large for highly relativistic particles. This monitor measures 100 μm beam sizes that are much smaller than the 3.2 mm λγ limit; it confirms the statement of Rule and Fiorito that optical transition radiation can be used to image small beams at high energy. The present paper describes the instrument and its performance. The authors tested the foil in, up to 180 μA of CW beam without causing noticeable beam loss, even at 800 MeV, the lowest CEBAF energy

  20. Low level neutron monitoring using high pressure 3He detectors

    International Nuclear Information System (INIS)

    Pszona, S.

    1995-01-01

    Three detectors, two spherical proportional counters and an ionisation chamber, all filled with 3 He to pressures of 160 kPa, 325 kPa and 1 MPa respectively have been experimentally studied with respect to their use for low level neutron monitoring. The ambient dose equivalent responses and the energy resolutions of these detectors have been determined. It is shown that spectral analysis of the signals from these detectors not only gives high sensitivity with regard to ambient dose equivalent but also improves the quality of the measurements. A special instrumentation for low level neutron monitoring is described in which a quality control method has been implemented. (Author)

  1. Thermoelectric powered wireless sensors for spent fuel monitoring

    International Nuclear Information System (INIS)

    Carstens, T.; Corradini, M.; Blanchard, J.; Ma, Z.

    2011-01-01

    This paper describes using thermoelectric generators to power wireless sensors to monitor spent nuclear fuel during dry-cask storage. OrigenArp was used to determine the decay heat of the spent fuel at different times during the service life of the dry-cask. The Engineering Equation Solver computer program modeled the temperatures inside the spent fuel storage facility during its service life. The temperature distribution in a thermoelectric generator and heat sink was calculated using the computer program Finite Element Heat Transfer. From these temperature distributions the power produced by the thermoelectric generator was determined as a function of the service life of the dry-cask. In addition, an estimation of the path loss experienced by the wireless signal can be made based on materials and thickness of the structure. Once the path loss is known, the transmission power and thermoelectric generator power requirements can be determined. This analysis estimates that a thermoelectric generator can produce enough power for a sensor to function and transmit data from inside the dry-cask throughout its service life. (authors)

  2. Solar powered wrist worn acquisition system for continuous photoplethysmogram monitoring.

    Science.gov (United States)

    Dieffenderfer, James P; Beppler, Eric; Novak, Tristan; Whitmire, Eric; Jayakumar, Rochana; Randall, Clive; Qu, Weiguo; Rajagopalan, Ramakrishnan; Bozkurt, Alper

    2014-01-01

    We present a solar-powered, wireless, wrist-worn platform for continuous monitoring of physiological and environmental parameters during the activities of daily life. In this study, we demonstrate the capability to produce photoplethysmogram (PPG) signals using this platform. To adhere to a low power budget for solar-powering, a 574 nm green light source is used where the PPG from the radial artery would be obtained with minimal signal conditioning. The system incorporates two monocrystalline solar cells to charge the onboard 20 mAh lithium polymer battery. Bluetooth Low Energy (BLE) is used to tether the device to a smartphone that makes the phone an access point to a dedicated server for long term continuous storage of data. Two power management schemes have been proposed depending on the availability of solar energy. In low light situations, if the battery is low, the device obtains a 5-second PPG waveform every minute to consume an average power of 0.57 mW. In scenarios where the battery is at a sustainable voltage, the device is set to enter its normal 30 Hz acquisition mode, consuming around 13.7 mW. We also present our efforts towards improving the charge storage capacity of our on-board super-capacitor.

  3. Integrated online condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Hashemian, Hashem M.

    2010-01-01

    Online condition monitoring or online monitoring (OLM) uses data acquired while a nuclear power is operating to continuously assess the health of the plant's sensors, processes, and equipment; to measure the dynamic performance of the plant's process instrumentation; to verify in-situ the calibration of the process instrumentation; to detect blockages, voids, and leaks in the pressure sensing lines; to identify core flow anomalies; to extend the life of neutron detectors and other sensors; and to measure the vibration of reactor internals. Both the steady-state or DC output of plant sensors and their AC signal or noise output can be used to assess sensor health, depending on whether the application is monitoring a rapidly changing (e.g., core barrel motion) or a slowly changing (e.g., sensor calibration) process. The author has designed, developed, installed, and tested OLM systems (comprised of software/hardware-based data acquisition and data processing modules) that integrate low-frequency (1 mHz to 1 Hz) techniques such as RTD cross-calibration, pressure transmitter calibration monitoring, and equipment condition monitoring and high-frequency (1 Hz to 1 kHz) techniques such as the noise analysis technique. The author has demonstrated the noise analysis technique's effectiveness for measuring the dynamic response-time of pressure transmitters and their sensing lines; for performing predictive maintenance on reactor internals; for detecting core flow anomalies; and for extending neutron detector life. Integrated online condition monitoring systems can combine AC and DC data acquisition and signal processing techniques, can use data from existing process sensors during all modes of plant operation, including startup, normal operation, and shutdown; can be retrofitted into existing PWRs, BWRs, and other reactor types and will be integrated into next-generation plants. (orig.)

  4. Integrated online condition monitoring system for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hashemian, Hashem M. [Analysis and Measurement Services Corporation, Knoxville, TN (United States). AMS Technology Center

    2010-09-15

    Online condition monitoring or online monitoring (OLM) uses data acquired while a nuclear power is operating to continuously assess the health of the plant's sensors, processes, and equipment; to measure the dynamic performance of the plant's process instrumentation; to verify in-situ the calibration of the process instrumentation; to detect blockages, voids, and leaks in the pressure sensing lines; to identify core flow anomalies; to extend the life of neutron detectors and other sensors; and to measure the vibration of reactor internals. Both the steady-state or DC output of plant sensors and their AC signal or noise output can be used to assess sensor health, depending on whether the application is monitoring a rapidly changing (e.g., core barrel motion) or a slowly changing (e.g., sensor calibration) process. The author has designed, developed, installed, and tested OLM systems (comprised of software/hardware-based data acquisition and data processing modules) that integrate low-frequency (1 mHz to 1 Hz) techniques such as RTD cross-calibration, pressure transmitter calibration monitoring, and equipment condition monitoring and high-frequency (1 Hz to 1 kHz) techniques such as the noise analysis technique. The author has demonstrated the noise analysis technique's effectiveness for measuring the dynamic response-time of pressure transmitters and their sensing lines; for performing predictive maintenance on reactor internals; for detecting core flow anomalies; and for extending neutron detector life. Integrated online condition monitoring systems can combine AC and DC data acquisition and signal processing techniques, can use data from existing process sensors during all modes of plant operation, including startup, normal operation, and shutdown; can be retrofitted into existing PWRs, BWRs, and other reactor types and will be integrated into next-generation plants. (orig.)

  5. Technology and Power. A Foucauldian Analysis of Electronic Monitoring Discourses

    Directory of Open Access Journals (Sweden)

    Anna Vitores

    2007-05-01

    Full Text Available The article aims to show the importance of FOUCAULT within social studies of science and technology. It also illustrates how a Foucauldian analysis can be useful for studies of science, technology and society focused on power effects. To accomplish these objectives we analyze the emergence of a specific techno-scientific innovation: the electronic monitoring of offenders. We map the discontinuities and discourse dispersions linked to those practices that constitute different materializations of this electronic device. Because we start from questions concerning power technologies, rather than simply analyzing the ideologies and knowledges that legitimate electronic monitoring and its technical reliability, we attend to the assemblage of discourses, rhetorics, vocabularies, techniques and procedures by which knowledge is intertwined and joins with the exercise of power. In this way, we show how one of FOUCAULT's technologies of power—disciplinary technology—is articulated, nourished and contradicted by other emergent logics drawing on new forms of regulation and social control. URN: urn:nbn:de:0114-fqs070225

  6. Monitoring of geological repositories for high level radioactive waste

    International Nuclear Information System (INIS)

    2001-04-01

    Geological repositories for disposal of high level radioactive waste are designed to provide isolation of the waste from human environment for many thousands of years. This report discusses the possible purposes for monitoring geological repositories at the different stages of a repository programme, the use that may be made of the information obtained and the techniques that might be applied. This report focuses on the different objectives that monitoring might have at various stages of a programme, from the initiation of work on a candidate site, to the period after repository closure. Each objective may require somewhat different types of information, or may use the same information in different ways. Having evaluated monitoring requirements, the report concludes with a brief evaluation of available monitoring techniques

  7. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

    International Nuclear Information System (INIS)

    1996-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

  8. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

  9. International remote monitoring project Argentina Nuclear Power Station Spent Fuel Transfer Remote Monitoring System

    International Nuclear Information System (INIS)

    Schneider, S.; Lucero, R.; Glidewell, D.

    1997-01-01

    The Autoridad Regulataria Nuclear (ARN) and the United States Department of Energy (DOE) are cooperating on the development of a Remote Monitoring System for nuclear nonproliferation efforts. A Remote Monitoring System for spent fuel transfer will be installed at the Argentina Nuclear Power Station in Embalse, Argentina. The system has been designed by Sandia National Laboratories (SNL), with Los Alamos National Laboratory (LANL) and Oak Ridge National Laboratory (ORNL) providing gamma and neutron sensors. This project will test and evaluate the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguards efficiency. This paper provides a description of the monitoring system and its functions. The Remote Monitoring System consists of gamma and neutron radiation sensors, RF systems, and video systems integrated into a coherent functioning whole. All sensor data communicate over an Echelon LonWorks Network to a single data logger. The Neumann DCM 14 video module is integrated into the Remote Monitoring System. All sensor and image data are stored on a Data Acquisition System (DAS) and archived and reviewed on a Data and Image Review Station (DIRS). Conventional phone lines are used as the telecommunications link to transmit on-site collected data and images to remote locations. The data and images are authenticated before transmission. Data review stations will be installed at ARN in Buenos Aires, Argentina, ABACC in Rio De Janeiro, IAEA Headquarters in Vienna, and Sandia National Laboratories in Albuquerque, New Mexico. 2 refs., 2 figs

  10. Operational margin monitoring system for boiling water reactor power plants

    International Nuclear Information System (INIS)

    Fukutomi, S.; Takigawa, Y.

    1992-01-01

    This paper reports on an on-line operational margin monitoring system which has been developed for boiling water reactor power plants to improve safety, reliability, and quality of reactor operation. The system consists of a steady-state core status prediction module, a transient analysis module, a stability analysis module, and an evaluation and guidance module. This system quantitatively evaluates the thermal margin during abnormal transients as well as the stability margin, which cannot be evaluated by direct monitoring of the plant parameters, either for the current operational state or for a predicted operating state that may be brought about by the intended operation. This system also gives operator guidance as to appropriate or alternate operations when the operating state has or will become marginless

  11. Automation of technical specification monitoring for nuclear power plants

    International Nuclear Information System (INIS)

    Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

    1986-01-01

    The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)

  12. Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program

    International Nuclear Information System (INIS)

    McGuire, L.L.

    1991-01-01

    The Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program serves two purposes. The first is to track temperature trends during normal plant operation in areas where suspected deviations from established environmental profiles exist. This includes the use of Resistance Temperature Detectors, Recorders, and Temperature Dots for evaluation of equipment qualified life for comparison with tested parameters and the established Environmental Design Profile. It also may be used to determine the location and duration of steam leaks for effect on equipment qualified life. The second purpose of this program is to aid HVAC design engineers in determining the source of heat outside anticipated design parameters. Resistance Temperature Detectors, Recorders, and Temperature Dots are also used for this application but the results may include design changes to eliminate the excess heat or provide qualified equipment (cable) to withstand the elevated temperature, splitting of environmental zones to capture accurate temperature parameters, or continued environmental monitoring for evaluation of equipment located in hot spots

  13. Environmental radiation monitoring during visits of nuclear powered warships to Australian ports: requirements, arrangements and procedures

    International Nuclear Information System (INIS)

    1988-05-01

    The Commonwealth Government has determined conditions to be met when nuclear powered warships visit Australian ports. These conditions include a requirement that appropriate State/Territory and Commonwealth authorities provide a radiation monitoring program to determine whether any radioactivity has been discharged or accidently released from a nuclear powered warship in port; to determine actual or potential levels of any consequent exposure to radiation of members of the public; and to provide this information within a timescale that allows remedial action to be taken. Part 1 of this document sets out the requirements of a radiation monitoring program capable of meeting these objectives. The fundamental arrangements and procedures for implementing the requirements are presented at Part 2 and provide a basis for the development of fully detailed, port specific, radiation monitoring programs

  14. Pre operational background radiation monitoring around Kudankulam Nuclear Power Project site - a decade long experience

    International Nuclear Information System (INIS)

    Vijayakumar, B.; George, Thomas; Sundara Rajan, P.; Selvi, B.S.; Balamurugan, M.; Pandit, G.G.; Ravi, P.M.; Tripathi, R.M.

    2014-01-01

    Pre-operational environmental background radiation monitoring around nuclear power plants is very important to understand baseline values existing in the site and also to identify any hot spots of naturally occurring high background radiation areas and their sources. These baseline measurements will act as a benchmark for future comparison after the reactors go into operation. The radiation measurements are continued during the operational phase of the plant and the results are compared to see whether there is any impact of the operation of the plant on the environment. A comprehensive background radiation monitoring plan has been in vogue at site from 2004 to meet this objective. This paper describes the different monitoring strategies adopted around Kudankulam Nuclear Power Project site and throws light on the pre operational background radiation levels in the environment

  15. International Remote Monitoring Project Embalse Nuclear Power Station, Argentina Embalse Remote Monitoring System

    International Nuclear Information System (INIS)

    Schneider, Sigfried L.; Glidewell, Donnie D.; Bonino, Anibal; Bosler, Gene; Mercer, David; Maxey, Curt; Vones, Jaromir; Martelle, Guy; Busse, James; Kadner, Steve; White, Mike; Rovere, Luis

    1999-01-01

    The Autoridad Regulatoria Nuclear of Argentina (ARN), the International Atomic Energy Agency (IAEA), ABACC, the US Department of Energy, and the US Support Program POTAS, cooperated in the development of a Remote Monitoring System for nuclear nonproliferation efforts. This system was installed at the Embalse Nuclear Power Station last year to evaluate the feasibility of using radiation sensors in monitoring the transfer of spent fuel from the spent fuel pond to dry storage. The key element in this process is to maintain continuity of knowledge throughout the entire transfer process. This project evaluated the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguard efficiency. New technology has been developed to enhance the design of the system to include storage capability on board sensor platforms. This evaluation has led to design enhancements that will assure that no data loss will occur during loss of RF transmission of the sensors

  16. A real time status monitor for transistor bank driver power limit resistor in boost injection kicker power supply

    Energy Technology Data Exchange (ETDEWEB)

    Mi, J.; Tan, Y.; Zhang, W.

    2011-03-28

    For years suffering of Booster Injection Kicker transistor bank driver regulator troubleshooting, a new real time monitor system has been developed. A simple and floating circuit has been designed and tested. This circuit monitor system can monitor the driver regulator power limit resistor status in real time and warn machine operator if the power limit resistor changes values. This paper will mainly introduce the power supply and the new designed monitoring system. This real time resistor monitor circuit shows a useful method to monitor some critical parts in the booster pulse power supply. After two years accelerator operation, it shows that this monitor works well. Previously, we spent a lot of time in booster machine trouble shooting. We will reinstall all 4 PCB into Euro Card Standard Chassis when the power supply system will be updated.

  17. Environment monitoring and residents health condition monitoring of nuclear power plant Bohunice region

    International Nuclear Information System (INIS)

    Letkovicova, M.; Rehak, R.; Stehlikova, B.; Celko, M.; Hraska, S.; Klocok, L.; Kostial, J.; Prikazsky, V.; Vidovic, J.; Zirko, M.; Beno, T.; Mitosinka, J.

    1998-01-01

    The report contents final environment evaluation and selected characteristic of residents health physics of nuclear power plant Bohunice region. Evaluated data were elaborated during analytical period 1993-1997.Task solving which results are documented in this final report was going on between 1996- 1998. The report deals in individual stages with the following: Information obtaining and completing which characterize demographic situation of the area for the 1993-1997 period; Datum obtaining and completing which contain selected health physics characteristics of the area residents; Database structures for individual data archiving from monitoring and collection; Brief description of geographic information system for graphic presentation of evaluation results based on topographic base; Digital mapping structure description; Results and evaluation of radionuclide monitoring in environment performed by Environmental radiation measurements laboratory by the nuclear power plant Bohunice for the 1993-1997 period. Demographic situation evaluation and selected health physics characteristics of the area of nuclear power plant residents for the 1993-1997 period are summarized in the final part of the document. Monitoring results and their evaluation is processed in graph, table, text description and map output forms. Map outputs are processed in the geographic information system Arc View GIS 3.0a environment

  18. Integrating working level monitor EML Type TF-11

    International Nuclear Information System (INIS)

    Latner, N.; Watnick, S.; Graveson, R.T.

    1981-01-01

    A time-integrating working level radiation monitor is described. The purpose of the instrument is the evaluation of the alpha emission from radon and its daughter products. It has been designed to be virtually silent in operation, making it suitable for residential studies

  19. Radiation levels from computer monitor screens within Benue State ...

    African Journals Online (AJOL)

    Investigation of possible presence of soft X-ray levels from Computer Screens at distances of 0.5m and 1.0m was carried out within Benue State University, Makurdi, using ten different monitor models. Radiation measurement was carried out using a portable digital radiation meter, INSPECTOR 06250 (SE international Inc.

  20. Mortality monitoring design for utility-scale solar power facilities

    Science.gov (United States)

    Huso, Manuela; Dietsch, Thomas; Nicolai, Chris

    2016-05-27

    IntroductionSolar power represents an important and rapidly expanding component of the renewable energy portfolio of the United States (Lovich and Ennen, 2011; Hernandez and others, 2014). Understanding the impacts of renewable energy development on wildlife is a priority for the U.S. Fish and Wildlife Service (FWS) in compliance with Department of Interior Order No. 3285 (U.S. Department of the Interior, 2009) to “develop best management practices for renewable energy and transmission projects on the public lands to ensure the most environmentally responsible development and delivery of renewable energy.” Recent studies examining effects of renewable energy development on mortality of migratory birds have primarily focused on wind energy (California Energy Commission and California Department of Fish and Game, 2007), and in 2012 the FWS published guidance for addressing wildlife conservation concerns at all stages of land-based wind energy development (U.S. Fish and Wildlife Service, 2012). As yet, no similar guidelines exist for solar development, and no published studies have directly addressed the methodology needed to accurately estimate mortality of birds and bats at solar facilities. In the absence of such guidelines, ad hoc methodologies applied to solar energy projects may lead to estimates of wildlife mortality rates that are insufficiently accurate and precise to meaningfully inform conversations regarding unintended consequences of this energy source and management decisions to mitigate impacts. Although significant advances in monitoring protocols for wind facilities have been made in recent years, there remains a need to provide consistent guidance and study design to quantify mortality of bats, and resident and migrating birds at solar power facilities (Walston and others, 2015).In this document, we suggest methods for mortality monitoring at solar facilities that are based on current methods used at wind power facilities but adapted for the

  1. The Power of Cross-Level Partnerships.

    Science.gov (United States)

    Youngerman, Stephanie

    1998-01-01

    Much credit for the tangible feeling of caring at an Idaho elementary school is due to partnerships that faculty, families, and students have forged across grade levels. These cross-grade buddy systems have put the brakes on bullies, fostered student friendships, and resolved personality conflicts among staff members. (MLH)

  2. Efficient diagnostic methods for nuclear power plant monitoring

    International Nuclear Information System (INIS)

    Sunder, R.

    1997-01-01

    There are systems for operational monitoring of vibrations, valves, solid-borne sound, leaks, and embrittlement. The paper focuses on vibration monitoring of pressurized components and systems in PWRs and BWRs. Other than with conventional systems, the task is not to globally monitor the vibration level, but the frequency-selective information is used as a sensitive information source, the level of vibrations being of secondary significance. The essential feature therefore is the comprehensive and selective scanning of individual frequency components in the recorded vibration spectra, which in some cases can be less than a millesimal millimeter. Upon identification of the various vibration components - from so-called baseline analyses using correlation methods - vibration analysis is done by only one step, comparing a defined reference state with the actual vibration state of the monitored system component. In the event of detected deviations, information on the causes of vibrations - essentially component-related structural resonances - will give the relevant cause-effect relationship. The paper uses some practical examples to illustrate that reliable diagnoses are achieved by the above-mentioned frequency-selective technique. It is important, however, to carry out a sufficiently reliable statistical verification of diagnostic data by means of vibration trending. This is ensured with the digital systems and their high data acquisition rates. (orig./CB) [de

  3. A survey of fatigue monitoring in the nuclear power industry

    International Nuclear Information System (INIS)

    Ware, A.G.

    1991-01-01

    The original design of nuclear power plants addressed fatigue concerns by including calculations of projected fatigue usage for specific components; the calculations were based on estimates of the number and severity of expected transients over the 40-year design life of the plants. In some cases, the transients occurring in the plants are not as severe as was anticipated in the original design analyses, while in other cases events have occurred that were not anticipated in the design basis documents. Field failures caused by fatigue have identified some of those cases. In response, several organizations in the United States and overseas have developed fatigue monitoring programs to more accurately estimate the fatigue usage. One basic approach consists of reconstructing the fatigue usage to date based on the transients recorded in the operating history instead of those projected in the design documents. Another approach includes monitoring the plant instrumentation to determine actual values for parameters such as temperature and pressure and using the measured values in the fatigue usage calculations instead of the values projected in the design documents. The use of existing plant instrumentation to measure temperature, pressure, flow rate, etc., along with the incorporation of conservative assumptions, had generally proven adequate for estimating fatigue usage; however, in some cases additional instrumentation installed for local monitoring can provide a more accurate estimate, especially where thermal stratification is known to occur. Fatigue monitoring can aid in identifying fatigue concerns not anticipated in the original design and for reducing the excessive conservatism in some of the original design calculations so that the fatigue lives of these components can be justified as they age. Fatigue monitoring can also assist efforts to reduce ongoing fatigue usage through design modifications and operating procedure changes

  4. Reactive Power Impact on Lifetime Prediction of Two-level Wind Power Converter

    DEFF Research Database (Denmark)

    Zhou, Dao; Blaabjerg, Frede; Lau, M.

    2013-01-01

    The influence of reactive power injection on the dominating two-level wind power converter is investigated and compared in terms of power loss and thermal behavior. Then the lifetime of both the partial-scale and full-scale power converter is estimated based on the widely used Coffin-Manson model...

  5. A noise reconfigurable current-reuse resistive feedback amplifier with signal-dependent power consumption for fetal ECG monitoring

    NARCIS (Netherlands)

    Song, Shuang; Rooijakkers, M.J.; Harpe, P.; Rabotti, C.; Mischi, M.; Van Roermund, A.H.M.; Cantatore, E.

    2016-01-01

    This paper presents a noise-reconfigurable resistive feedback amplifier with current-reuse technique for fetal ECG monitoring. The proposed amplifier allows for both tuning of the noise level and changing the power consumption according to the signal properties, minimizing the total power

  6. Development of full power risk monitoring system for UCN 3 and 4 nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Seung Hwan; Jang, Seung Chul; Kim, Kil Yoo; Han, Sang Hoon; Jung, Won Dae

    2002-03-01

    This report describes full power risk monitoring system (DynaRM) of NPPs which evaluates the current plant risk and monitor the risk change caused by the configuration change due to preventive maintenance or periodic maintenance activities. In order to calculate the core damage frequency, the inoperable equipment's basic event should be submitted to a quantification engine. DynaRM uses a risk monitor model converted from PSA model as the quantification engine, which can respond fast for the various equipment configuration changes. DynaRM is developed to solve these kinds of problems and difficulties. The main two key features of DynaRM are real time risk monitoring and real time maintenance plan decision supporting. With DynaRM, the plant risk can be calculated automatically only with out of service equipment information and equipment maintenance scheduling is easy by modifying the detail schedule plan. We have developed the DynaRM for the Korean standard nuclear power plant and it is currently using at Ulchin 3,4 NPP. The adaptation for the other NPPs is also easy with a little modification since DynaRM was developed by considering it to be used in the other NPPs. Moreover, we also expect DynaRM will be a good advisory tool for the plant risk monitoring and maintenance scheduling

  7. Analysis of superconducting microstrip resonator at various microwave power levels

    International Nuclear Information System (INIS)

    Srivastava, G.P.; Jacob, M.V.; Jayakumar, M.; Bhatnagar, P.K.; Kataria, N.D.

    1997-01-01

    The real and imaginary parts of the surface impedance of YBCO superconductors have been studied at different microwave power levels. Using the relations for the critical current density and the grain boundary resistance, a relation for calculating the power dependence of the surface resistance has been obtained. Also, a relation to find the resonant frequency of a superconducting microstrip resonator at various input power levels has been derived. Measurements have been carried out on various microstrip resonators to study the variation of surface resistance and resonant frequency at different rf power levels. The experimental results are in good agreement with theoretical results. copyright 1997 American Institute of Physics

  8. University students' understanding level about words related to nuclear power

    International Nuclear Information System (INIS)

    Oiso, Shinichi; Watabe, Motoki

    2012-01-01

    The authors conducted a survey of university students' understanding level about words related to nuclear power before and after Fukushima Daiichi Power Plant accident, and analyzed the difference between before and after the accident. The results show that university students' understanding level improved after the accident, especially in the case of reported words by mass media. Understanding level of some nuclear power security words which were not reported so much by mass media also improved. That may be caused by rising of people's concern about nuclear power generation after the accident, and there is a possibility that the accident motivated people to access such words via internet, journals, etc. (author)

  9. An Intelligent Sensor for the Ultra-High-Frequency Partial Discharge Online Monitoring of Power Transformers

    Directory of Open Access Journals (Sweden)

    Jian Li

    2016-05-01

    Full Text Available Ultra-high-frequency (UHF partial discharge (PD online monitoring is an effective way to inspect potential faults and insulation defects in power transformers. The construction of UHF PD online monitoring system is a challenge because of the high-frequency and wide-frequency band of the UHF PD signal. This paper presents a novel, intelligent sensor for UHF PD online monitoring based on a new method, namely a level scanning method. The intelligent sensor can directly acquire the statistical characteristic quantities and is characterized by low cost, few data to output and transmit, Ethernet functionality, and small size for easy installation. The prototype of an intelligent sensor was made. Actual UHF PD experiments with three typical artificial defect models of power transformers were carried out in a laboratory, and the waveform recording method and intelligent sensor proposed were simultaneously used for UHF PD measurement for comparison. The results show that the proposed intelligent sensor is qualified for the UHF PD online monitoring of power transformers. Additionally, three methods to improve the performance of intelligent sensors were proposed according to the principle of the level scanning method.

  10. Challenges with Tertiary-Level Mechatronic Fluid Power

    DEFF Research Database (Denmark)

    Dransfield, Peter; Conrad, Finn

    1996-01-01

    As authors we take the view that mechatronics, as it relates to fluid power, has three levels which we designate as primary, secondary and tertiary. A brief review of the current status of fluid power, hydraulic and pneumatic, and of electronic control of it is presented and discussed. The focus...... is then on tertiary-level mechatronic fluid power and the challenges to it being applied successfully....

  11. Market power monitoring and mitigation in the US wholesale power markets

    Energy Technology Data Exchange (ETDEWEB)

    Helman, Udi [Federal Energy Regulatory Commission, 888 First Street, N.E., Washington, DC 20426 (United States)

    2006-05-15

    Under current statutory requirements, the Federal Energy Regulatory Commission (FERC) must ensure that prices in US wholesale power markets are 'just and reasonable'. This has been interpreted by the agency and the courts as requiring the monitoring and mitigation of undue market power. This paper focuses on generation market power. Prior to electricity sector restructuring, wholesale bilateral power trading took place among vertically integrated monopoly utilities trading at the margin or between small independent producers and the utilities. Under those conditions, the authorization of trading at market prices, called 'market-based rates', required only that the generation supplier pass a simple market share screen for market power. As restructuring unfolded, and market conditions changed, there has been a steady evolution in FERC's market power mitigation rules, encompassing (a) changes in the market power assessment required for granting market-based rates and related methods for merger approval, and (b) development and refinement of new techniques for screening and mitigating offers into the organized day-ahead and real-time markets operated by Independent System Operators (ISOs) and Regional Transmission Organizations (RTOs). This paper reviews these changes to date, as FERC continues to clarify its approved rules and procedures. It also examines recent methods for quantitative market power analysis that could augment current procedures or supplant them, as found appropriate. (author)

  12. Online Monitoring of Large Centrifugal Pumps in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Emmanuel, Efenji A.; Faragalla, Mohamed M.; Awwal, Arigi M.; Lee, Yong-kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    Online Monitoring detects and diagnoses incipient faults, performs predictive maintenance, and can estimate the Remaining Useful Life (RUL) of Active and Passive Components before they fail. In an effort towards assisting Utility Partners to be proactive in the management of their Assets, the Electric Power Research Institute (EPRI) collaborated with the Idaho National Laboratory (INL) to develop a Fleet-Wide Prognostic and Health Monitoring (FW-PHM) Software Suite. The FW-PHM is a web based diagnostic tools and databases designed for use in commercial NPP. The AFS development process as designed by EPRI can be adapted to Large Centrifugal Pumps (LCP) in Nuclear Power Plants (NPP). For the purpose of this endeavor, the set of LCP considered are Safety Class-Motor Driven-Vertical Centrifugal Pumps for primary flow which includes Safety Injection, Containment Spray, and Residual Heat Removal. Fault Signatures of the LCP for OLM has been developed following the INCOSE V-model systems development approach. The fault types, fault features, and their detection methods and effectiveness for the LCP were established by diligently following the guidelines recommended by EPRI. An optimization of the FS for OLM has been suggested for implementation. As a way of extending this work, a Cost-Benefit Analysis between OLM and the conventional Periodic Maintenance for the LCP in NPP is proposed.

  13. Online Monitoring of Large Centrifugal Pumps in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Emmanuel, Efenji A.; Faragalla, Mohamed M.; Awwal, Arigi M.; Lee, Yong-kwan

    2016-01-01

    Online Monitoring detects and diagnoses incipient faults, performs predictive maintenance, and can estimate the Remaining Useful Life (RUL) of Active and Passive Components before they fail. In an effort towards assisting Utility Partners to be proactive in the management of their Assets, the Electric Power Research Institute (EPRI) collaborated with the Idaho National Laboratory (INL) to develop a Fleet-Wide Prognostic and Health Monitoring (FW-PHM) Software Suite. The FW-PHM is a web based diagnostic tools and databases designed for use in commercial NPP. The AFS development process as designed by EPRI can be adapted to Large Centrifugal Pumps (LCP) in Nuclear Power Plants (NPP). For the purpose of this endeavor, the set of LCP considered are Safety Class-Motor Driven-Vertical Centrifugal Pumps for primary flow which includes Safety Injection, Containment Spray, and Residual Heat Removal. Fault Signatures of the LCP for OLM has been developed following the INCOSE V-model systems development approach. The fault types, fault features, and their detection methods and effectiveness for the LCP were established by diligently following the guidelines recommended by EPRI. An optimization of the FS for OLM has been suggested for implementation. As a way of extending this work, a Cost-Benefit Analysis between OLM and the conventional Periodic Maintenance for the LCP in NPP is proposed

  14. Long distance high power optical laser fiber break detection and continuity monitoring systems and methods

    Science.gov (United States)

    Rinzler, Charles C.; Gray, William C.; Faircloth, Brian O.; Zediker, Mark S.

    2016-02-23

    A monitoring and detection system for use on high power laser systems, long distance high power laser systems and tools for performing high power laser operations. In particular, the monitoring and detection systems provide break detection and continuity protection for performing high power laser operations on, and in, remote and difficult to access locations.

  15. Level monitoring system with pulsating sensor—Application to online level monitoring of dashpots in a fast breeder reactor

    Energy Technology Data Exchange (ETDEWEB)

    Malathi, N.; Sahoo, P., E-mail: sahoop@igcar.gov.in; Ananthanarayanan, R.; Murali, N. [Real Time Systems Division, Electronics, Instrumentation and Radiological Safety Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603102 (India)

    2015-02-15

    An innovative continuous type liquid level monitoring system constructed by using a new class of sensor, viz., pulsating sensor, is presented. This device is of industrial grade and it is exclusively used for level monitoring of any non conducting liquid. This instrument of unique design is suitable for high resolution online monitoring of oil level in dashpots of a sodium-cooled fast breeder reactor. The sensing probe is of capacitance type robust probe consisting of a number of rectangular mirror polished stainless steel (SS-304) plates separated with uniform gaps. The performance of this novel instrument has been thoroughly investigated. The precision, sensitivity, response time, and the lowest detection limit in measurement using this device are <0.01 mm, ∼100 Hz/mm, ∼1 s, and ∼0.03 mm, respectively. The influence of temperature on liquid level is studied and the temperature compensation is provided in the instrument. The instrument qualified all recommended tests, such as environmental, electromagnetic interference and electromagnetic compatibility, and seismic tests prior to its deployment in nuclear reactor. With the evolution of this level measurement approach, it is possible to provide dashpot oil level sensors in fast breeder reactor for the first time for continuous measurement of oil level in dashpots of Control and Safety Rod Drive Mechanism during reactor operation.

  16. Models for thermal and mechanical monitoring of power transformers

    Energy Technology Data Exchange (ETDEWEB)

    Vilaithong, Rummiya

    2011-07-01

    At present, for economic reasons, there is an increasing emphasis on keeping transformers in service for longer than in the past. A condition-based maintenance using an online monitoring and diagnostic system is one option to ensure reliability of the transformer operation. The key parameters for effectively monitoring equipment can be selected by failure statistics and estimated failure consequences. In this work, two key aspects of transformer condition monitoring are addressed in depth: thermal behaviour and behaviour of on-load tap changers. In the first part of the work, transformer thermal behaviour is studied, focussing on top-oil temperatures. Through online comparison of a measured value of the top-oil temperature and its calculated value, some rapidly developing failures in power transformers such as malfunction of the cooling unit may be detected. Predictions of top-oil temperature can be obtained by means of a mathematical model. Long-term investigations on some dynamic top-oil temperature models are presented for three different types of transformer units. The last-state top-oil temperature, load current, ambient temperature and the operating state of pumps and fans are applied as inputs of the top-oil temperature models. In the fundamental physical models presented, some constant parameters are required and can be estimated using a least-squares optimization technique. Multilayer Feed-forward and Recurrent neural network models are also proposed and investigated. The neural network models are trained with three different Backpropagation training algorithms: Levenberg-Marquardt, Scaled Conjugate Gradient and Automated Bayesian Regularization. The effect of varying operating conditions of the cooling units and the non-steady-state behaviour of loading conditions, as well as ambient temperature are noted. Results show sophisticated temperature prediction is possible using the neural network models that is generally more accurate than with the physical

  17. Monitoring of low level environmental gamma exposure by the centralized radiation monitoring system

    International Nuclear Information System (INIS)

    Katagiri, Hiroshi; Kobayashi, Hideo; Obata, Kazuichi; Kokubu, Morinobu; Itoh, Naoji

    1981-07-01

    In the Japan Atomic Energy Research Institute (JAERI), a centralized automatic radiation monitoring system developed 20 years ago has recently been improved to monitor low level gamma radiation more accurately in normal operation of the nuclear facilities and to detect abnormal radioactive releases more effectively. The present state of the system is described. This system puts together environmental monitoring data such as gamma exposure rate (20 points), radioactive concentration in the air (4 points) and in water (2 drains), and meteorological items (14 including wind directions, wind speeds, solar radiation and air temperatures at a observation tower of 40 m height). Environmental monitoring around the JAERI site is carried out effectively using the system. Data processing system consists of a central processing unit, a magnetic disk, a magnetic tape, a line printer and a console typewriter. The data at respective monitoring points are transmitted to the central monitoring room by wireless or telephone line. All data are printed out and field in magnetic disk and magnetic tape every 10 minutes. When the emergency levels are exceeded, however, the data are automatically output on a line printer every 2 minute. This system can distinguish very low gamma exposure due to gaseous effluents, about 1 mR/y, from the background. Even in monthly exposures, calculated values based on the data of release amount and meteorology are in good agreement with the measured ones. (author)

  18. Environmental monitoring of low-level radioactive materials

    International Nuclear Information System (INIS)

    Jester, W.A.; Yu, C.

    1985-01-01

    The authors discuss some of the current rationale behind the environmental monitoring of low-level radioactive materials are as follows: Committee 4 of the International commission on Radiological Protection (ICRP) defined three broad objectives for environmental monitoring: 1) assessment of the actual or potential exposure of humans to radioactive materials or radiation present in their environment or the estimation of the probable upper limits of such exposure; 2) scientific investigation, sometimes related to the assessment of exposures, sometimes to other objectives; 3) improved public relations. Various regulations have been written requiring environmental monitoring to ensure that the public is not being exposed to excessive amounts of radiation from natural sources or from human activities. An example of the monitoring of natural sources of radiation is a requirement of the Environmental Protection Agency's (EPA) National Interim Primary Drinking Water Regulations whereby U.S. water supply companies must have drinking water monitored at least once every four years for radionuclides, primarily the naturally occurring radium-226

  19. A solution to the varying response of the linear power monitor induced by xenon poisoning

    Energy Technology Data Exchange (ETDEWEB)

    Godsey, T A; Randall, J D [Texas A and M University (United States)

    1974-07-01

    After conversion to FLIP fuel at Texas A and M, the fuel temperatures were examined very carefully. It was observed that the fuel temperature at 1 Mw varied over a wide range during the week. This variation was shown to be due to the variation in response of the linear CIC which was used to establish reactor power level. A modification of the linear power monitor was designed and installed. The response of this system was verified by using cobalt wires, fuel temperature, and a fission chamber located at 6 feet from the reactor core. The system has proven to be operationally satisfactory. (author)

  20. Results and experiences from environmental monitoring at Rheinsberg nuclear power plant

    International Nuclear Information System (INIS)

    Ettenhuber, E.; Loennig, M.; Hoffmann, M.L.; Roehnsch, W.; Babenzien, C.; Lehmann, R.; Schreiter, W.D.

    1975-12-01

    The paper presents the routine monitoring program at the Rheinsberg nuclear power plant including the methods applied therein. On the basis of data gathered during 1966 to 1973 it is shown, that the impact of nuclear power plant operation on the radioactivity level of the examined environmental media was exceedingly small compared to that of global fallout. Therefore only by means of a system based on assessment of radiation exposure from effluent data and environmental surveillance is it possible to prove the observance of maximum permissible values to individual members of the public. (author)

  1. Rule-based emergency action level monitor prototype

    International Nuclear Information System (INIS)

    Touchton, R.A.; Gunter, A.D.; Cain, D.

    1985-01-01

    In late 1983, the Electric Power Research Institute (EPRI) began a program to encourage and stimulate the development of artificial intelligence (AI) applications for the nuclear industry. Development of a rule-based emergency action level classification system prototype is discussed. The paper describes both the full prototype currently under development and the completed, simplified prototype

  2. Dynamic state estimation assisted power system monitoring and protection

    Science.gov (United States)

    Cui, Yinan

    The advent of phasor measurement units (PMUs) has unlocked several novel methods to monitor, control, and protect bulk electric power systems. This thesis introduces the concept of "Dynamic State Estimation" (DSE), aided by PMUs, for wide-area monitoring and protection of power systems. Unlike traditional State Estimation where algebraic variables are estimated from system measurements, DSE refers to a process to estimate the dynamic states associated with synchronous generators. This thesis first establishes the viability of using particle filtering as a technique to perform DSE in power systems. The utility of DSE for protection and wide-area monitoring are then shown as potential novel applications. The work is presented as a collection of several journal and conference papers. In the first paper, we present a particle filtering approach to dynamically estimate the states of a synchronous generator in a multi-machine setting considering the excitation and prime mover control systems. The second paper proposes an improved out-of-step detection method for generators by means of angular difference. The generator's rotor angle is estimated with a particle filter-based dynamic state estimator and the angular separation is then calculated by combining the raw local phasor measurements with this estimate. The third paper introduces a particle filter-based dual estimation method for tracking the dynamic states of a synchronous generator. It considers the situation where the field voltage measurements are not readily available. The particle filter is modified to treat the field voltage as an unknown input which is sequentially estimated along with the other dynamic states. The fourth paper proposes a novel framework for event detection based on energy functions. The key idea is that any event in the system will leave a signature in WAMS data-sets. It is shown that signatures for four broad classes of disturbance events are buried in the components that constitute the

  3. Monitoring of awareness level in dispensary patients with arterial hypertension.

    Science.gov (United States)

    Smiianov, Vladyslav; Witczak, Izabela; Smiianova, Olga; Rudenko, Lesia

    2017-01-01

    Results of monitoring of awareness level in dispensary patients with arterial hypertension (AH) are given in the article. The objective of the study was to investigate awareness level of dispensary patients with hypertension in Sumy as for the course of their disease, implementation of preventive measures, diagnosis and treatment, and to use the obtained information in the process of management of healthcare quality. The results of close-ended questionnaires were used in the capacity of materials. A total of 2019 patients were surveyed. Despite the high level of patients' awareness of AH course and possible complications, the survey showed insufficient level of their own responsibility for their health. The main reasons for poor adherence to doctor's recommendations are forgetfulness, lack of time, reluctance. Measures were developed to increase awareness level in patients with AH by means of strengthening awareness-raising activities and communications, as well as creation and implementation of effective targeted health-and-social programs.

  4. Voices of nuclear power 'monitors' in fiscal 1985: results of the questionnaire

    International Nuclear Information System (INIS)

    1986-01-01

    The system of nuclear power 'monitors' is to hear opinions etc. of the general people (i.e. of nuclear power monitors) on the nuclear power development and utilization and thereby to reflect the results in the nuclear power administration in Japan. The questionnairing survey by mail was made in June 1985 with 536 monitors across the country, of which 474 answered the questions. The results are described in the following: energies in the future, the development of nuclear power, the development of advanced-type reactors, the nuclear fuel cycle, nuclear power safety administration, nuclear hazard prevention, nuclear power PR activities. (Mori, K.)

  5. Internal exposure monitoring of personnel of a nuclear power plant with pressurized-water reactors

    International Nuclear Information System (INIS)

    Krueger, F.W.; Poulheim, K.F.; Rueger, G.; Schreiter, W.D.

    1982-01-01

    In the GDR a programme for monitoring the internal radiation exposure of personnel has been established in the Bruno Leuschner Nuclear Power Plant, Greifswald, which allows one to estimate the effective dose equivalent in the way recommended by the ICRP. The measuring equipment used, and the methods of calibration and of evaluation of results are described. At present about 400 persons are monthly monitored with a thorax monitor in the nuclear power plant. If an investigation level - corresponding to an effective dose equivalent of 0.3mSv/month - is exceeded, a more exact measurement is made in the whole-body counter at the National Board for Nuclear Safety and Radiation Protection of the GDR. In addition, a selected group of 50 persons is measured twice yearly in the whole-body counter. The measurements show the high effectiveness of the protective measures against radionuclide intake by workers in the nuclear power plant, resulting in a contribution of less than 1% to the collective dose of the personnel. A correlation has been found between external and internal exposure indicating that, in general, there will be a higher intake only under conditions resulting also in higher external exposures. The highest individual values of internal exposure found are below 0.5mSv/month and thus within the range of the lower detection limit of dosimeter films used for monitoring the external exposure. (author)

  6. Kinetic inductance of HTS resonators at various microwave power levels

    International Nuclear Information System (INIS)

    Srivastava, G.P.; Jacob, Mohan V.

    1997-01-01

    Microwave superconducting devices show a drastic deterioration in its performance at high microwave power levels. The flux penetration through the weak links increases the quasiparticle concentration which results in the increase of penetration depth and hence the kinetic inductance. We have modeled an expression to find the kinetic inductance at various RF power levels. The results show that the change in kinetic inductance is proportional to be square of the applied field. This model can explain the reported experimental results at and below the intermediate power levels. (author)

  7. Cutting device for a local power range monitor tube

    International Nuclear Information System (INIS)

    Watanabe, Shigeru; Tsuji, Teruaki.

    1976-01-01

    Object: To provide a combination of a lifting device for a local power range monitor (LPRM) tube, a cutter and a transfer machine to safely and securely cut the LPRM tube under water. Structure: An LPRM tube is gripped by an LPRM tube gripper, which is moved up and down by a chain drive, through a flexture corrector, and the tip of the LPRM tube is held and released from the LPRM tube gripper so as to be threaded into an LPRM tube cutter to grip it by a transfer gripper of an LPRM tube transfer machine, after which the LPRM tube cutter is operated under pressure water to cut the LPRM tube with a cutter edge so that a cut portion is closed. (Yoshino, Y.)

  8. Simulation of decreasing reactor power level with BWR simulator

    International Nuclear Information System (INIS)

    Suwoto; Zuhair; Rivai, Abu Khalid

    2002-01-01

    Study on characteristic of BWR using Desktop PC Based Simulator Program was analysed. This simulator is more efficient and cheaper for analyzing of characteristic and dynamic respond than full scope simulator for decreasing power level of BW. Dynamic responses of BWR reactor was investigated during the power level reduction from 100% FP (Full Power) which is 3926 MWth to 0% FP with 25% steps and 1 % FP/sec rate. The overall results for core flow rate, reactor steam flow, feed-water flow and turbine-generator power show tendency proportional to reduction of reactor power. This results show that reactor power control in BWR could be done by control of re-circulation flow that alter the density of water used as coolant and moderator. Decreasing the re-circulation flow rate will decrease void density which has negative reactivity and also affect the position of control rods

  9. Environmental monitoring of low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Shum, E.Y.; Starmer, R.J.; Young, M.H.

    1989-12-01

    This branch technical position (BTP) paper on the environmental monitoring program for a low-level radioactive waste disposal facility provides general guidance on what is required by Section 61.53 of Title 10 of the Code of Federal Regulations (10 CFR) of applicants submitting a license application for such a facility. In general, the environmental monitoring program consists of three phases: preoperational, operational, and postoperational. Each phase of the monitoring program should be designed to fulfill the specific objectives defined in the BTP paper. During the preoperational phase, the objectives of the program are to provide site characterization information, to demonstrate site suitability and acceptability, to obtain background or baseline information, and to provide a record for public information. During the operational phase, the emphasis on measurement shifts. Monitoring data are obtained to provide early warning of releases and to document compliance with regulations, the dose limits of 10 CFR Part 61, or applicable standards of the US Environmental Protection Agency. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational environmental monitoring program emphasizes measurements to demonstrate compliance with the site-closure requirements and continued compliance with the performance objective in regard to the release of radionuclides to the environment. The data are used to support evaluation of long-term effects on the general public and for public information. Guidance is also provided in the BTP paper on the choice of which constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance

  10. Microprocessor-assisted calibration for a remote working level monitor

    International Nuclear Information System (INIS)

    McDowell, W.P.; Keefe, D.J.; Groer, P.G.; Witek, R.T.

    1977-01-01

    A method is described for calibrating a Remote Working Level Monitor, an instrument which measures Working Level and Rn-daughter concentrations in the atmosphere. The method makes use of a microprocessor to calculate beta efficiencies for RaB and RaC from the counts accumulated in the RaA, Ra(B + C) and RaC' channels of the instrument. Both the alpha spectroscopic and total-alpha methods are used to determine the Rn-daughter concentrations. These methods require the processor to solve systems of linear equations with several unknowns. No assumptions about Rn-daughter equilibrium are made

  11. Microprocessor-assisted calibration for a remote working level monitor

    International Nuclear Information System (INIS)

    McDowell, W.P.; Keefe, D.J.; Groer, P.G.; Witek, R.T.

    1976-01-01

    A method is described for calibrating a Remote Working Level Monitor, an instrument which measures Working Level and Rn-daughter concentrations in the atmosphere. The method makes use of a microprocessor to calculate beta efficiencies for RaB and RaC from the counts accumulated in the RaA, Ra(B + C) and RaC' channels of the instrument. Both the alpha spectroscopic and total-alpha methods are used to determine the Rn-daughter concentrations. These methods require the processor to solve systems of linear equations with several unknowns. No assumptions about Rn-daughter equilibrium are made

  12. Environmental monitoring at the Forsmark nuclear power plant

    International Nuclear Information System (INIS)

    Sandstroem, O.

    1991-01-01

    The use of cooling water at such large power plants as Forsmark creates a considerable hazard for fish in the intake area, as they may be transported into the plant and killed. Several millions of Baltic herring and three-spined stickleback are lost each year at the intake screens. A release of cooling water to an open sea area is generally considered as a minor environmental problem, a presumption so far not contradicated by the results from the monitoring studies at Forsmark. In the Biotest basin, however, where the exposure to heat is maximal, a long series of effects ultimately changing populations of plants, benthic animals and fish have been documented. One important conclusion after ten years of studies in a heated Biotest basin, is that ecosystem stability seems to need very long time to be established, if it ever will. The monitoring of radioactivity controls the quality of the fish as food but is also directed to select special species accumulating these elements, bladder wrack etc. At Forsmark only small amounts of radionuclides from the plant so far have been detected in the marine environment. (KAE)

  13. Condition monitoring of rotormachinery in nuclear power plants

    International Nuclear Information System (INIS)

    Suedmersen, U.; Runkel, J.; Vortriede, A.; Reimche, W.; Stegemann, D.

    1996-01-01

    Due to safety and economical reasons diagnostic and monitoring systems are of growing interest in nuclear power plants and other complex industrial productions. Key components of NPP's are rotating machineries of the primary and secondary loops like PWR main coolant pumps, BWR recirculation pumps, turbines, fresh water pumps and feed water pumps. Diagnostic systems are requested which detect, diagnose and localize faulty operation conditions at an early stage in order to prevent severe failures and to enable predictive and condition oriented maintenance. The knowledge of characteristical machine signatures and their time dependent behaviour are the basis of efficient condition monitoring of rotating machines. The performance of reference measurements are of importance for fault detection during operation by trend settings. The comparison with thresholds given by norms and standards is only a small section of available possibilities. Therefore, for each machinery own thresholds should be determined using statistical time values, spectra comparison, cepstrum analysis and correlation analysis for source localization corresponding to certain machine operation conditions. (author). 14 refs, 15 figs

  14. Condition monitoring of rotormachinery in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Suedmersen, U; Runkel, J; Vortriede, A; Reimche, W; Stegemann, D [University of Hannover, Hannover (Germany). Inst. of Nuclear Engineering and Nondestructive Testing

    1997-12-31

    Due to safety and economical reasons diagnostic and monitoring systems are of growing interest in nuclear power plants and other complex industrial productions. Key components of NPP`s are rotating machineries of the primary and secondary loops like PWR main coolant pumps, BWR recirculation pumps, turbines, fresh water pumps and feed water pumps. Diagnostic systems are requested which detect, diagnose and localize faulty operation conditions at an early stage in order to prevent severe failures and to enable predictive and condition oriented maintenance. The knowledge of characteristical machine signatures and their time dependent behaviour are the basis of efficient condition monitoring of rotating machines. The performance of reference measurements are of importance for fault detection during operation by trend settings. The comparison with thresholds given by norms and standards is only a small section of available possibilities. Therefore, for each machinery own thresholds should be determined using statistical time values, spectra comparison, cepstrum analysis and correlation analysis for source localization corresponding to certain machine operation conditions. (author). 14 refs, 15 figs.

  15. Dynamic Sleep Scheduling on Air Pollution Levels Monitoring with Wireless Sensor Network

    OpenAIRE

    Gezaq Abror; Rusminto Tjatur Widodo; M. Udin Harun Al Rasyid

    2018-01-01

    Wireless Sensor Network (WSN) can be applied for Air Pollution Level Monitoring System that have been determined by the Environmental Impact Management Agency which is  PM10, SO2, O3, NO2 and CO. In WSN, node system is constrained to a limited power supply, so that the node system has a lifetime. To doing lifetime maximization, power management scheme is required and sensor nodes should use energy efficiently. This paper proposes dynamic sleep scheduling using Time Category-Fuzzy Logic (Time-...

  16. PC and monitor night status: Power management enabling and manual turn-off

    International Nuclear Information System (INIS)

    Nordman, Bruce; Meier, Alan; Piette, Mary Ann

    1998-01-01

    While office equipment accounts for about 7 percent of commercial building energy use, this reflects considerable energy savings from the use of automatic power management. Most of these savings were gained through the use of low-power modes that meet the criteria of the U.S. EPA's Energy Star program. Despite this success, there are large amounts of additional savings that could be gained if all equipment capable of power management use were enabled and functioning. A considerable portion of equipment is not enabled for power management at all, enabled only partially, or is enabled but prevented from functioning. Additional savings could be gained if more equipment were turned off at night manually. We compiled results from 17 studies from the office equipment literature addressing PCs and monitors. Some factors important for annual energy use, such as power levels, have been documented elsewhere and are not covered. We review methods for estimating office equipment use patterns and energy use, and present findings on night status-power management and manual turn-off rates. In early studies, PC power management was often found to function in 25 percent or less of the Energy Star compliant units (10 percent of all PCs). However, recent assessments have found higher rates, and we estimate that for Energy Star models, 35 percent of PC CPUs and 65 percent of PC monitors are enabled for power management. While the data lack statistical rigor, they can be used to estimate the magnitude of current and potential power management savings, which we did for major types of office equipment. The data also make clear that the topic of enabling rates, and the factors which influence them, deserve greater scrutiny

  17. Experimental Study of a Multi Level Overtopping Wave Power Device

    DEFF Research Database (Denmark)

    Kofoed, Jens Peter; Hald, Tue; Frigaard, Peter Bak

    2002-01-01

    Results of experimental investigations of a floating wave energy device called Power Pyramid is presented. The Power Pyramid utilizes reservoirs in multiple levels when capturing wave overtopping and converting it into electrical energy. The effect of capturing the overtopping in multiple levels,......, using 5 levels introduces practical problems, and is most probably not economically feasible. It is concluded that it is reasonable to use 2 levels (maybe 3), which can increase the efficiency by 25-40 % compared to using a single level.......Results of experimental investigations of a floating wave energy device called Power Pyramid is presented. The Power Pyramid utilizes reservoirs in multiple levels when capturing wave overtopping and converting it into electrical energy. The effect of capturing the overtopping in multiple levels......, compared to only one level, has been evaluated experimentally. From the experimental results, and the performed optimizations based on these, it has been found that the efficiency of a wave power device of the overtopping type can be increased by as much as 76 % by using 5 levels instead of 1. However...

  18. Vehicle power supply cable with optical jacket monitoring and arcing interference detection; Bordnetzkabel mit optischer Mantelueberwachung und Stoerlichtbogendetektion

    Energy Technology Data Exchange (ETDEWEB)

    Viehmann, Matthias [Fachhochschule Nordhausen (Germany). Lehrstuhl fuer Industrieelektronik; Kloss, Christina [Fachhochschule Nordhausen (Germany). Forschungsschwerpunkte Polymere/Elastomere und Lichtwellenleiter; Lustermann, Birgit [Fachhochschule Nordhausen (Germany). Forschungsschwerpunkte Lichtwellenleiter und Simulation optischer Systeme

    2012-10-15

    In vehicles with electrical drive, vehicle power supplies are used with high-voltage level, as well as with several voltage levels. In order to minimise any hazards through arcing faults associated with this, constructive and material-technical measures are necessary. Nordhausen Technical College presents a patented, opticalelectrical combination conductor - the main constituent of an innovative vehicle power supply cable with optical jacket monitoring and arcing interference detection. (orig.)

  19. Abnormal condition detector for a local power range monitor

    International Nuclear Information System (INIS)

    Akiyama, Takao.

    1976-01-01

    Object: to permit determination of abnormal condition by a number of local power range monitors (LPRM) to be quickly made through precise estimation of the ratio between the true rate of change in neutron flux and true change in the neutron flux by making use of the fact that the status of the neutron distribution does not widely change with a change in the core flow rate for a short period of time. Structure: While carrying out power control according to the core flow rate, detection values from LPRM which are disposed in a three-dimensional fashion within the reactor core are indicated on an indicator. The average value of rates of change in the indicated values for a group of LPRM under substantially the same fluid dynamic condition as that for each LPRM is determined while measuring time-wise change rate in the indicated value of each of the LPRM. The average value is successively divided by the rate of change in the indicated value for each LPRM and the amplifier gain thereof to obtain the reference value. When the difference between the average value and reference value obtained in this way exceeds a prescribed value, the corresponding LPRM is determined to be defective. (Moriyama, K.)

  20. FLAME MONITORING IN POWER STATION BOILERS USING IMAGE PROCESSING

    Directory of Open Access Journals (Sweden)

    K. Sujatha

    2012-05-01

    Full Text Available Combustion quality in power station boilers plays an important role in minimizing the flue gas emissions. In the present work various intelligent schemes to infer the flue gas emissions by monitoring the flame colour at the furnace of the boiler are proposed here. Flame image monitoring involves capturing the flame video over a period of time with the measurement of various parameters like Carbon dioxide (CO2, excess oxygen (O2, Nitrogen dioxide (NOx, Sulphur dioxide (SOx and Carbon monoxide (CO emissions plus the flame temperature at the core of the fire ball, air/fuel ratio and the combustion quality. Higher the quality of combustion less will be the flue gases at the exhaust. The flame video was captured using an infrared camera. The flame video is then split up into the frames for further analysis. The video splitter is used for progressive extraction of the flame images from the video. The images of the flame are then pre-processed to reduce noise. The conventional classification and clustering techniques include the Euclidean distance classifier (L2 norm classifier. The intelligent classifier includes the Radial Basis Function Network (RBF, Back Propagation Algorithm (BPA and parallel architecture with RBF and BPA (PRBFBPA. The results of the validation are supported with the above mentioned performance measures whose values are in the optimal range. The values of the temperatures, combustion quality, SOx, NOx, CO, CO2 concentrations, air and fuel supplied corresponding to the images were obtained thereby indicating the necessary control action taken to increase or decrease the air supply so as to ensure complete combustion. In this work, by continuously monitoring the flame images, combustion quality was inferred (complete/partial/incomplete combustion and the air/fuel ratio can be automatically varied. Moreover in the existing set-up, measurements like NOx, CO and CO2 are inferred from the samples that are collected periodically or by

  1. 77 FR 30030 - Monitoring the Effectiveness of Maintenance at Nuclear Power Plants

    Science.gov (United States)

    2012-05-21

    ... Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. SUMMARY... (RG) 1.160, ``Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.'' This guide... Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,'' which provides methods that are...

  2. A distributed monitoring system for photovoltaic arrays based on a two-level wireless sensor network

    Science.gov (United States)

    Su, F. P.; Chen, Z. C.; Zhou, H. F.; Wu, L. J.; Lin, P. J.; Cheng, S. Y.; Li, Y. F.

    2017-11-01

    In this paper, a distributed on-line monitoring system based on a two-level wireless sensor network (WSN) is proposed for real time status monitoring of photovoltaic (PV) arrays to support the fine management and maintenance of PV power plants. The system includes the sensing nodes installed on PV modules (PVM), sensing and routing nodes installed on combiner boxes of PV sub-arrays (PVA), a sink node and a data management centre (DMC) running on a host computer. The first level WSN is implemented by the low-cost wireless transceiver nRF24L01, and it is used to achieve single hop communication between the PVM nodes and their corresponding PVA nodes. The second level WSN is realized by the CC2530 based ZigBee network for multi-hop communication among PVA nodes and the sink node. The PVM nodes are used to monitor the PVM working voltage and backplane temperature, and they send the acquired data to their PVA node via the nRF24L01 based first level WSN. The PVA nodes are used to monitor the array voltage, PV string current and environment irradiance, and they send the acquired and received data to the DMC via the ZigBee based second level WSN. The DMC is designed using the MATLAB GUIDE and MySQL database. Laboratory experiment results show that the system can effectively acquire, display, store and manage the operating and environment parameters of PVA in real time.

  3. Deep convolutional neural network processing of aerial stereo imagery to monitor vulnerable zones near power lines

    Science.gov (United States)

    Qayyum, Abdul; Saad, Naufal M.; Kamel, Nidal; Malik, Aamir Saeed

    2018-01-01

    The monitoring of vegetation near high-voltage transmission power lines and poles is tedious. Blackouts present a huge challenge to power distribution companies and often occur due to tree growth in hilly and rural areas. There are numerous methods of monitoring hazardous overgrowth that are expensive and time-consuming. Accurate estimation of tree and vegetation heights near power poles can prevent the disruption of power transmission in vulnerable zones. This paper presents a cost-effective approach based on a convolutional neural network (CNN) algorithm to compute the height (depth maps) of objects proximal to power poles and transmission lines. The proposed CNN extracts and classifies features by employing convolutional pooling inputs to fully connected data layers that capture prominent features from stereo image patches. Unmanned aerial vehicle or satellite stereo image datasets can thus provide a feasible and cost-effective approach that identifies threat levels based on height and distance estimations of hazardous vegetation and other objects. Results were compared with extant disparity map estimation techniques, such as graph cut, dynamic programming, belief propagation, and area-based methods. The proposed method achieved an accuracy rate of 90%.

  4. Concerning results of environmental monitoring around the reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    1989-01-01

    The Central Evaluation Expert Group for Environmental radiation Monitoring has been engaged in examinations of plants for and results of the environmental radiation monitoring performed by Power Reactor and Nuclear Fuel Development Corporation around its reprocessing facilities. The present report outlines an examination of the results of monitoring carried out in 1987 (January to December). It is concluded that the methods used for the monitoring and its technical level are satisfactory in meeting the objectives of the monitoring plans. Expept for tritium in seawater, the level of radiations stays within the normal variation determined based on preliminary measurements of the background radiation. The procedure used for the calculation of exposure dose is also satisfactory in meeting the requirements specified in the monitoring plants. It is confirmed that the exposure dose of the residents around the facilities is well below the permissible exposure dose limite specified in law. (Nogami. K.)

  5. Monitoring device for radioactive leakage from steam system in nuclear power plant

    International Nuclear Information System (INIS)

    Ogawa, Tateo; Sato, Kohei

    1988-01-01

    Purpose: To improve the reliability for the monitor of radio-active leakage by accumulating small quantity of radioactivities each lower than the detectable level and increasing their dose rate. Constitution: Even if the steam system radiation monitor in the nuclear power plant is disposed for the detection of in-leak radioactivity, radioactive leakage can be monitored at high reliability by increasing the small quantity of radioactivities in the drains to a detectable sensitivity range of the monitor upon detection. In view of the above, in the present invention, radioactive material catching medium is incorporated to a radio-activity monitor spool piece for accumulating small quantity of radioactivities. Specifically as the catching medium, an ion exchange resin is used for the leakage of ionic radioactive material, while an ion exchange resin increased with the mixing ratio of a cationic resin or hollow thread membrane filter is used for crud-like radioactive material leakage. These catching media are incorporated into the spool piece, thereby enabling to catch even small quantity of radioactive leakage lower than the detectable sensitivity of the radiation monitor, if should occur, in the spool piece and enabling radioactive detection for the accumulated dose rate. (Horiuchi, T.)

  6. We Need to Talk... Developing Communicating Power Supplies to Monitor & Control Miscellaneous Electric Loads

    Energy Technology Data Exchange (ETDEWEB)

    Weber, Andrew; Lanzisera, Steven; Liao, Anna; Meier, Alan

    2014-08-11

    Plug loads represent 30percent of total electricity use in residential buildings. Significant energy savings would result from an accurate understanding of which miscellaneous electric devices are using energy, at what time, and in what quantity. Commercially available plug load monitoring and control solutions replace or limit the attached device's native controls - forcing the user to adapt to a separate set of controls associated with the monitoring and control hardware. A better solution is integration of these capabilities at the power supply level. In this paper, we demonstrate a method achieving this integration. Our solution allows unobtrusive power monitoring and control while retaining native device control features. Further, our prototype enables intelligent behaviors by allowing devices to respond to the state of one another automatically. The CPS enables energy savings while demonstrating an added level of functionality to the user. If CPS technology became widespread in devices, a combination of automated and human interactive solutions would enable high levels of energy savings in buildings.

  7. Continuous liquid level monitoring sensor system using fiber Bragg grating

    Science.gov (United States)

    Sengupta, Dipankar; Kishore, Putha

    2014-01-01

    The design and packaging of simple, small, and low cost sensor heads, used for continuous liquid level measurement using uniformly thinned (etched) optical fiber Bragg grating (FBG) are proposed. The sensor system consists of only an FBG and a simple detection system. The sensitivity of sensor is found to be 23 pm/cm of water column pressure. A linear optical fiber edge filter is designed and developed for the conversion of Bragg wavelength shift to its equivalent intensity. The result shows that relative power measured by a photo detector is linearly proportional to the liquid level. The obtained sensitivity of the sensor is nearly -15 mV/cm.

  8. Non-intrusive load monitoring based on low frequency active power measurements

    Directory of Open Access Journals (Sweden)

    Chinthaka Dinesh

    2016-03-01

    Full Text Available A Non-Intrusive Load Monitoring (NILM method for residential appliances based on active power signal is presented. This method works effectively with a single active power measurement taken at a low sampling rate (1 s. The proposed method utilizes the Karhunen Loéve (KL expansion to decompose windows of active power signals into subspace components in order to construct a unique set of features, referred to as signatures, from individual and aggregated active power signals. Similar signal windows were clustered in to one group prior to feature extraction. The clustering was performed using a modified mean shift algorithm. After the feature extraction, energy levels of signal windows and power levels of subspace components were utilized to reduce the number of possible appliance combinations and their energy level combinations. Then, the turned on appliance combination and the energy contribution from individual appliances were determined through the Maximum a Posteriori (MAP estimation. Finally, the proposed method was modified to adaptively accommodate the usage patterns of appliances at each residence. The proposed NILM method was validated using data from two public databases: tracebase and reference energy disaggregation data set (REDD. The presented results demonstrate the ability of the proposed method to accurately identify and disaggregate individual energy contributions of turned on appliance combinations in real households. Furthermore, the results emphasise the importance of clustering and the integration of the usage behaviour pattern in the proposed NILM method for real households.

  9. Geodetic infrastructure at the Barcelona harbour for sea level monitoring

    Science.gov (United States)

    Martinez-Benjamin, Juan Jose; Gili, Josep; Lopez, Rogelio; Tapia, Ana; Pros, Francesc; Palau, Vicenc; Perez, Begona

    2015-04-01

    The presentation is directed to the description of the actual geodetic infrastructure of Barcelona harbour with three tide gauges of different technologies for sea level determination and contribution to regional sea level rise and understanding past and present sea level rise in the Barcelona harbour. It is intended that the overall system will constitute a CGPS Station of the ESEAS (European Sea Level) and TIGA (GPS Tide Gauge Benchmark Monitoring) networks. At Barcelona harbour there is a MIROS radar tide gauge belonging to Puertos del Estado (Spanish Harbours).The radar sensor is over the water surface, on a L-shaped structure which elevates it a few meters above the quay shelf. 1-min data are transmitted to the ENAGAS Control Center by cable and then sent each 1 min to Puertos del Estado by e-mail. The information includes wave forescast (mean period, significant wave height, sea level, etc.This sensor also measures agitation and sends wave parameters each 20 min. There is a GPS station Leica Geosystems GRX1200 GG Pro and antenna AX 1202 GG. The Control Tower of the Port of Barcelona is situated in the North dike of the so-called Energy Pier in the Barcelona harbor (Spain). This tower has different kind of antennas for navigation monitoring and a GNSS permanent station. As the tower is founded in reclaimed land, and because its metallic structure, the 50 m building is subjected to diverse movements, including periodic fluctuations due to temperature changes. In this contribution the 2009, 2011, 2012, 2013 and 2014 the necessary monitoring campaigns are described. In the framework of a Spanish Space Project, the instrumentation of sea level measurements has been improved by providing the Barcelona site with a radar tide gauge Datamar 2000C from Geonica S.L. in June 2014 near an acoustic tide gauge from the Barcelona Harbour installed in 2013. Precision levelling has been made several times in the last two years because the tower is founded in reclaimed land and

  10. Thermal performance monitoring and assessment in Dukovany nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Madron, F. [Chemplant Technology s.r.o., Hrncirska 4, 400 01 Usti nad Labem (Czech Republic); Papuga, J. [CEZ a.s., JE Dukovany, 675 50 Dukovany (Czech Republic); Pliska, J. [I and C ENERGO a.s., Prazska 684, 674 01 Trebic (Czech Republic)

    2006-07-01

    Competition in the European electricity market forces generators to achieve - in compliance with safety and environmental standards - efficiency of production as high as possible. This efficiency or heat rate is an important indicator of both the condition of the plant equipment and the quality of plant operation. Similar thermal performance indicators can also be calculated for components of the plant equipment such as heat exchangers. However, it is not easy to quantify these indicators with sufficient precision so that the results can be used for conduct of plant operation in near-real time and for predictive maintenance. This paper describes a present state of the system monitoring and evaluating thermal performance of the reactor units in Dukovany Nuclear Power Plant. The system provides information on actual and desirable (should-be) values of thermal performance indicators for control room operators, performance engineers and maintenance planners. The system is designed to monitor steady states and has two main functions: data validation and process simulation. Data validation is based on data reconciliation methodology and carried out with Recon software by Chemplant Technology. A detailed model of the secondary side for mass and heat balancing has been made up by means of the Recon's graphical editor; now it contains roughly 300 flows and employs data of about 200 measurements. Main advantages of the data reconciliation are: - reconciled data are consistent with the model, - reconciled data are more precise than data directly measured with consequence that the thermal power of steam generators is determined with substantially lower uncertainty than before - data reconciliation represents a solid basis for detection and identification of data corrupted by gross errors. Simulation is performed with a different analytical model of plant components configured into secondary side. The model has been developed by I and C Energo. Main purposes of simulation

  11. Formal specification and animation of a water level monitoring system

    International Nuclear Information System (INIS)

    Jackson, P.S.; Stokes, P.A.

    1993-03-01

    This report describes the Vienna Development Method (VDM), which is a formal method for software specification and development. VDM evolved out of attempts to use mathematics in programming language specifications in order to avoid ambiguities in specifications written in natural language. This report also describes the use of VDM for a real-time application, where it is used to formally specify the requirements of a water level monitoring system. The procedures and techniques used to produce an executable form (animation) of the specification are covered. (Author)

  12. Ultrasonic level and temperature sensor for power reactor applications

    International Nuclear Information System (INIS)

    Dress, W.B.; Miller, G.N.

    1983-01-01

    An ultrasonic waveguide employing torsional and extensional acoustic waves has been developed for use as a level and temperature sensor in pressurized and boiling water nuclear power reactors. Features of the device include continuous measurement of level, density, and temperature producing a real-time profile of these parameters along a chosen path through the reactor vessel

  13. User's manual for levelized power generation cost using a microcomputer

    International Nuclear Information System (INIS)

    Fuller, L.C.

    1984-08-01

    Microcomputer programs for the estimation of levelized electrical power generation costs are described. Procedures for light-water reactor plants and coal-fired plants include capital investment cost, operation and maintenance cost, fuel cycle cost, nuclear decommissioning cost, and levelized total generation cost. Programs are written in Pascal and are run on an Apple II Plus microcomputer

  14. Practical experience with second law power plant monitoring

    International Nuclear Information System (INIS)

    Lang, F.D.; Horn, K.F.

    1992-01-01

    This article discusses the use of an ultimate performance monitoring technique derived from Second Law concepts. Other techniques and their methods have been reported. If electricity is to be produced with the minimum of unproductive consumption of fuel - then fundamental thermodynamic losses must be understood on a system bases. Such understanding cuts across vendor curves, plant design, fuels, etc. Thermal losses in a nuclear unit are comparable at a prime facia level to losses at any other thermal system. They are what we must minimize in the production of electricity, no manner the method of that production. The Second Law offers the only foundation for the study of such losses, and thus affords the bases for a true and ultimate indicator of system performance. From such a foundation, a parameter is needed to tell us specifically what components are thermodynamically responsible for fuel consumption given either their direct creation of electricity or their contribution to thermodynamic losses. The Fuel Consumption Index, discussed in this article, is this parameter. It can be used for thermodynamic system design, monitoring, diagnosing problems, and economic dispatching. It tells us why fuel is being consumed; consumed by a nuclear plant, trash burner, a 40 year-old fossil plant, etc

  15. POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT

    International Nuclear Information System (INIS)

    Diamond, D.J.; Bromley, B.P.; Aronson, A.L.

    2002-01-01

    The purpose of this study is to determine the effect of the initial power level during a rod ejection accident (REA) on the ejected rod worth and the resulting energy deposition in the fuel. The model used is for the hot zero power (HZP) conditions at the end of a typical fuel cycle for the Three Mile Island Unit 1 pressurized water reactor. PARCS , a transient, three-dimensional, two-group neutron nodal diffusion code, coupled with its own thermal-hydraulics model, is used to perform both steady-state and transient simulations. The worth of an ejected control rod is affected by both power level, and the positions of control banks. As the power level is increased, the worth of a single central control rod tends to drop due to thermal-hydraulic feedback and control bank removal, both of which flatten the radial neutron flux and power distributions. Although the peak fuel pellet enthalpy rise during an REA will be greater for a given ejected rod worth at elevated initial power levels, it is more likely the HZP condition will cause a greater net energy deposition because an ejected rod will have the highest worth at HZP. Thus, the HZP condition can be considered the most conservative in a safety evaluation

  16. Power Constrained High-Level Synthesis of Battery Powered Digital Systems

    DEFF Research Database (Denmark)

    Nielsen, Sune Fallgaard; Madsen, Jan

    2003-01-01

    We present a high-level synthesis algorithm solving the combined scheduling, allocation and binding problem minimizing area under both latency and maximum power per clock-cycle constraints. Our approach eliminates the large power spikes, resulting in an increased battery lifetime, a property...... of utmost importance for battery powered embedded systems. Our approach extends the partial-clique partitioning algorithm by introducing power awareness through a heuristic algorithm which bounds the design space to those of power feasible schedules. We have applied our algorithm on a set of dataflow graphs...

  17. Monitoring the levels of important nutrients in the food supply.

    Science.gov (United States)

    Neal, B; Sacks, G; Swinburn, B; Vandevijvere, S; Dunford, E; Snowdon, W; Webster, J; Barquera, S; Friel, S; Hawkes, C; Kelly, B; Kumanyika, S; L'Abbé, M; Lee, A; Lobstein, T; Ma, J; Macmullan, J; Mohan, S; Monteiro, C; Rayner, M; Sanders, D; Walker, C

    2013-10-01

    A food supply that delivers energy-dense products with high levels of salt, saturated fats and trans fats, in large portion sizes, is a major cause of non-communicable diseases (NCDs). The highly processed foods produced by large food corporations are primary drivers of increases in consumption of these adverse nutrients. The objective of this paper is to present an approach to monitoring food composition that can both document the extent of the problem and underpin novel actions to address it. The monitoring approach seeks to systematically collect information on high-level contextual factors influencing food composition and assess the energy density, salt, saturated fat, trans fats and portion sizes of highly processed foods for sale in retail outlets (with a focus on supermarkets and quick-service restaurants). Regular surveys of food composition are proposed across geographies and over time using a pragmatic, standardized methodology. Surveys have already been undertaken in several high- and middle-income countries, and the trends have been valuable in informing policy approaches. The purpose of collecting data is not to exhaustively document the composition of all foods in the food supply in each country, but rather to provide information to support governments, industry and communities to develop and enact strategies to curb food-related NCDs. © 2013 The Authors. Obesity Reviews published by John Wiley & Sons Ltd on behalf of the International Association for the Study of Obesity.

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

    Science.gov (United States)

    Hashemian, H. M.

    2010-10-01

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

  19. An extensible database architecture for nationwide power quality monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Kuecuek, Dilek; Inan, Tolga; Salor, Oezguel; Demirci, Turan; Buhan, Serkan; Boyrazoglu, Burak [TUBITAK Uzay, Power Electronics Group, TR 06531 Ankara (Turkey); Akkaya, Yener; Uensar, Oezguer; Altintas, Erinc; Haliloglu, Burhan [Turkish Electricity Transmission Co. Inc., TR 06490 Ankara (Turkey); Cadirci, Isik [TUBITAK Uzay, Power Electronics Group, TR 06531 Ankara (Turkey); Hacettepe University, Electrical and Electronics Eng. Dept., TR 06532 Ankara (Turkey); Ermis, Muammer [METU, Electrical and Electronics Eng. Dept., TR 06531 Ankara (Turkey)

    2010-07-15

    Electrical power quality (PQ) data is one of the prevalent types of engineering data. Its measurement at relevant sampling rates leads to large volumes of PQ data to be managed and analyzed. In this paper, an extensible database architecture is presented based on a novel generic data model for PQ data. The proposed architecture is operated on the nationwide PQ data of the Turkish Electricity Transmission System measured in the field by mobile PQ monitoring systems. The architecture is extensible in the sense that it can be used to store and manage PQ data collected by any means with little or no customization. The architecture has three modules: a PQ database corresponding to the implementation of the generic data model, a visual user query interface to enable its users to specify queries to the PQ database and a query processor acting as a bridge between the query interface and the database. The operation of the architecture is illustrated on the field PQ data with several query examples through the visual query interface. The execution of the architecture on this data of considerable volume supports its applicability and convenience for PQ data. (author)

  20. Coarse-Grained Online Monitoring of BTI Aging by Reusing Power-Gating Infrastructure

    OpenAIRE

    Tenentes, V.; Rossi, D.; Sheng Yang,; Khursheed, S.; Al-Hashimi, B.M.; Gunn, S.R.

    2017-01-01

    In this paper, we present a novel coarse-grained technique for monitoring online the Bias Temperature Instability (BTI) aging of circuits by exploiting their power gating infrastructure. The proposed technique relies on monitoring the discharge time of the virtual-power-network during stand-by operations, the value of which depends on the threshold voltage of the CMOS devices in the power-gated design (PGD). It does not require any distributed sensors, because the virtual-power network is alr...

  1. 1. Biologic monitoring at Barsebaeck nuclear power plant 1985-1997. 2. Biological monitoring at Swedish nuclear power plants in 1998. Annual report 1998

    International Nuclear Information System (INIS)

    Andersson, Jan; Mo, K.; Thoernqvist, S.

    1999-06-01

    This report gives an account for two studies on the ecological effects of effluents to the aquatic environment from the Swedish nuclear power plants: 1. The results of biological monitoring at the Barsebaeck nuclear power plant during the period 1985-1997 are summarised. Comparisons are made with a previous report from 1969-1983. The fish community was studied by fyke net test fishing in the cooling water effluent area along a gradient out to unaffected sites. The loss of young eels in the cooling water intake was estimated annually. Damage on female grey mullet oocyte development was analysed on samples of cooling water exposed fish. 2. The biological monitoring at the Swedish nuclear power plants during 1998 was with minor exceptions performed according to the established programmes. The monitoring at Forsmark is running in the enclosed Biotest basin at the cooling water outlet and in the surrounding archipelago. Reference data are collected at Finbo, NW Aaland, and in the nearby Graesoe archipelago. In 1998 as in previous years the benthic macro fauna abundance within the Biotest basin showed strong variations. In the beginning of the year abundance and biomass were low, in the autumn though, higher than average. Oskarshamn: The monitoring is performed in the small effluent bay, Hamnefjaerden bay, in the waters surrounding the cooling water plume and in a reference area, Kvaedoe-fjaerden, 100 km north of the power plant. Perch and roach catches have been high in the Hamnefjaerden bay since the late 1980's. In 1998 catches of perch were on a higher level than in 1997, both in spring and in summer. The changes for roach were small. A moderate decrease in eel catches took place in 1997 and 1998, indicating a reduced effect of stockings in the late 1980's. Ringhals: The monitoring is performed in the area close to the cooling water outlet, which is located at an open coast, and in a reference area. An attraction of yellow eel to the effluent area has been

  2. Radiation monitoring for the HTTR rise-to-power test (1) and (2)'

    Energy Technology Data Exchange (ETDEWEB)

    Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji; Ashikagaya, Yoshinobu; Kikuchi, Toshiki [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2001-02-01

    The High Temperature Engineering Test Reactor (HTTR) is the first high temperature gas-cooled research reactor in Japan. This reactor is a helium-gas-cooled and graphite-moderated reactor with a thermal output of 30 MW. The rated operation temperature of the outlet coolant is 850degC. (During high temperature test operation, this reaches 950degC). The first criticality of the HTTR was attained in November 1998. The single loaded, parallel loaded operation with a thermal output of 9 MW (called the HTTR Rise-to-Power Test (1)) was completed between September 16, 1999 and July 8, 2000. The single loaded, parallel loaded continuous operation with a thermal output of 20 MW (called the HTTR Rise-to-Power Test (2)) has also been carried out, but it was shutdown at the halfway stage by a single from the reactor, when the thermal output was 16.5 MW and the reactor outlet coolant temperature was 500degC. This report describes the radiation monitoring carried out during the HTTR Rise-to-Power Tests (1) and (2)'. The data measured by the various radiation monitors is also reported. These data will be used for the estimation of radiation levels (such as the radiation dose equivalent rate, the radioactive concentration in effluents, etc.) for the next HTTR Rise-to-Power Test, and for periodic inspections. (author)

  3. Groundwater Level Monitoring using Levelogger and the Importance of Long-Term Groundwater Level Data

    International Nuclear Information System (INIS)

    Nazran Harun; Ahmad Hasnulhadi Che Kamaruddin

    2016-01-01

    This review paper is focused on groundwater level monitoring using levelogger and the importance of long-term groundwater level data. The levelogger provides an inexpensive and convenient method to measure level, temperature and conductivity all in one probe. It can provide real time view as data is being recorded by the connected data logger. Water-level measurements from observation wells are the principal source of information about the hydrologic stresses acting on aquifers and how these stresses affect ground-water recharge, storage, and discharge. Long-term and systematic measurements of water levels provide essential data needed to evaluate changes in the resource over time to develop ground-water models, forecast trends and monitor the effectiveness of groundwater management. A significant advantage of this method of data collection and reporting are the groundwater level data can be updated real time. The accessibility of water level data is greatly enhanced by the Geographic Information System (GIS) to visually illustrate the locations of observation wells relative to relevant topographic, geologic, or hydrologic features. GIS and internet greatly enhance the capability for retrieval and transmittal of water-level data to potential users. (author)

  4. A Low-power CMOS BFSK Transceiver for Health Monitoring Systems.

    Science.gov (United States)

    Kim, Sungho; Lepkowski, William; Wilk, Seth J; Thornton, Trevor J; Bakkaloglu, Bertan

    2011-01-01

    A CMOS low-power transceiver for implantable and external health monitoring devices operating in the MICS band is presented. The LNA core has an integrated mixer in a folded configuration to reuse the bias current, allowing high linearity with a low power supply levels. The baseband strip consists of a pseudo differential MOS-C band-pass filter achieving demodulation of 150kHz-offset BFSK signals. An all digital frequency-locked loop is used for LO generation in the RX mode and for driving a class AB power amplifier in the TX mode. The MICS transceiver is designed and fabricated in a 0.18μm 1-poly, 6-metal CMOS process. The sensitivities of -70dBm and -98dBm were achieved with NF of 40dB and 11dB at the data rate of 100kb/s while consuming only 600μW and 1.5mW at 1.2V and 1.8V, respectively. The BERs are less than 10 -3 at the input powers of -70dBm at 1.2V and -98dBm at 1.8V at the data rate of 100kb/s. Finally, the output power of the transmitter is 0dBm for a power consumption of 1.8mW.

  5. Monitoring of air pollution levels related to Charilaos Trikoupis Bridge.

    Science.gov (United States)

    Sarigiannis, D A; Handakas, E J; Kermenidou, M; Zarkadas, I; Gotti, A; Charisiadis, P; Makris, K; Manousakas, M; Eleftheriadis, K; Karakitsios, S P

    2017-12-31

    Charilaos Trikoupis bridge is the longest cable bridge in Europe that connects Western Greece with the rest of the country. In this study, six air pollution monitoring campaigns (including major regulated air pollutants) were carried out from 2013 to 2015 at both sides of the bridge, located in the urban areas of Rio and Antirrio respectively. Pollution data were statistically analyzed and air quality was characterized using US and European air quality indices. From the overall campaign, it was found that air pollution levels were below the respective regulatory thresholds, but once at the site of Antirrio (26.4 and 52.2μg/m 3 for PM 2.5 and ΡΜ 10 , respectively) during the 2nd winter period. Daily average PM 10 and PM 2.5 levels from two monitoring sites were well correlated to gaseous pollutant (CO, NO, NO 2 , NO x and SO 2 ) levels, meteorological parameters and factor scores from Positive Matrix Factorization during the 3-year period. Moreover, the elemental composition of PM 10 and PM 2.5 was used for source apportionment. That analysis revealed that major emission sources were sulfates, mineral dust, biomass burning, sea salt, traffic and shipping emissions for PM 10 and PM 2.5 , for both Rio and Antirrio. Seasonal variation indicates that sulfates, mineral dust and traffic emissions increased during the warm season of the year, while biomass burning become the dominant during the cold season. Overall, the contribution of the Charilaos Trikoupis bridge to the vicinity air pollution is very low. This is the result of the relatively low daily traffic volume (~10,000 vehicles per day), the respective traffic fleet composition (~81% of the traffic fleet are private vehicles) and the speed limit (80km/h) which does not favor traffic emissions. In addition, the strong and frequent winds further contribute to the rapid dispersion of the emitted pollutants. Copyright © 2017. Published by Elsevier B.V.

  6. D and B monitors for Z-vacuum-section power-flow measurements

    International Nuclear Information System (INIS)

    Stygar, W.A.; Spielman, R.B.; Ives, H.C.

    1997-01-01

    The 36-module Z accelerator--designed to drive z-pinch loads at currents up to 20 MA--is contained in a 33-m-diameter tank with oil, water, and vacuum sections. The peak total forward-going power in the 36 water-section bi-plate transmission lines is approximately 63 TW. nine transmission lines deliver power to each of the four vacuum-section levels (referred to as levels A (the uppermost), B, C, and D). New differential D and B monitors were developed for the Z vacuum section. The Ds measure voltage at the insulator stack. The Bs measure current at the stack and in the outer magnetically-insulated transmission lines. Each monitor has two outputs that allow common-mode noise to be canceled to first order. The differential D has one signal and one noise channel; the differential B has two signal channels with opposite polarities. Each of the two B sensors in the differential B monitor has four 3-mm-diameter loops and is encased in copper to reduce flux penetration. For both types of probes, two 2.2-mm-diameter coaxial-cables connect the outputs to a Prodyn balun for common-mode-noise rejection. The cables provide reasonable bandwidth and generate acceptable levels of Compton drive in Z's bremsstrahlung field. A new cavity B is being developed to measure the total Z current 4.3 cm from the axis of the z-pinch load. All of the sensors are calibrated with 2--4% accuracy. The monitor signals are reduced with Barth or Weinschel attenuators, recorded on Tektronix 0.5-ns/sample digitizing oscilloscopes, and software cable compensated and integrated

  7. Monitoring and analyzing features of electrical power quality system performance

    OpenAIRE

    Genci Sharko; Nike Shanku

    2010-01-01

    Power quality is a set of boundaries that allows electrical systems to function in their intended manner without significant loss of performance or life. The term is used to describe electric power that drives an electrical load and the load's ability to function properly with that electric power. Without the proper quality of the power, an electrical device may malfunction, fail prematurely or not operate at all. There are many reasons why the electric power can be of poor quality and many m...

  8. Mechanical guided waves for fuel level monitoring system

    Directory of Open Access Journals (Sweden)

    Tiberiu Adrian SALAORU

    2017-09-01

    Full Text Available The mechanical guided waves have a wide range of applications in many types of equipment and devices. The fuel level is an important parameter which needs to be monitored for a vehicle which can be a space vehicle, an aircraft or any other. For this purpose mechanical guided waves can be used as they have several major advantages over any other methods. There are a wide ultrasonic sensors used for this purpose but in the most cases the mechanical waves are traveling through air or fuel for measuring their level. In general the wave propagation through a single media at a time is utilized. The method described in this work uses the propagation of the mechanical guided waves through two different media in the same time. The propagating media is the container wall and the other is the fuel. One of the advantages of this method is the reduction of the measurement errors when the incident angle to the fuel level surface is different from 90 degree. These situations could occur when the fuel tank is tilted or when the fuel surface is not flat. This measurement method will not be affected by these conditions.

  9. Watt-level wireless power transmission to multiple compact receivers

    International Nuclear Information System (INIS)

    Garraud, A; Munzer, D J; Althar, M; Garraud, N; Arnold, D P

    2015-01-01

    This paper reports an electrodynamic wireless power transmission (EWPT) system using a low-frequency (300 Hz) magnetic field to transmit watt-scale power levels to multiple compact receivers. As compared to inductively or resonantly coupled coils, EWPT facilitates transmission to multiple non-interacting receivers with little restriction on their orientation. A single 3.0 cm 3 receiver achieves 1.25 W power transmission with 8% efficiency at a distance of 1 cm (350 mW/cm 3 power density) from the transmitter. The same prototype achieves 9 mW at a distance of 9 cm. Moreover, we demonstrate simultaneous recharge of two wearable devices, using two receivers located in arbitrary positions and orientations. (paper)

  10. Challenges and Prospects of Equipment Health Monitoring with Wireless Sensor Network in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Chen, Dongyi; Jiang, Jin; Bari, Ataul; Wang, Quan; Hashemian, Hash-M.

    2014-01-01

    A wireless sensor network (WSN) system can offer tremendous benefits to equipment condition monitoring in newly-constructed and/or refurbished nuclear power plants (NPPs). However, it has not been widely accepted so far because of the following requirements by the NPP operators ectromagnetic (EM) emissions from the wireless transceivers must not interfere with the functionalities of the sensitive safety and protection systems in the plant, WSN must perform reliably in the presence of high levels of EM interference from devices such as relays and motor driven pumps, and ionizing radiation sources, dependable WSN performance in harsh industrial environments that are cluttered with cable trays, piping, valves, pumps, motors, and concrete and steel structures, and trict compliance with nuclear regulatory guidelines on EM emissions by the wireless devices. This paper will review the key issues associated with the deployment of WSN for equipment condition monitoring in NPPs. Some promising WSN technologies that can be used in NPP applications are also discussed

  11. Challenges and Prospects of Equipment Health Monitoring with Wireless Sensor Network in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Dongyi [University of Electronic Science and Technology of China, Chengdu (China); Jiang, Jin; Bari, Ataul; Wang, Quan [University of Western Ontario, Ontario (Canada); Hashemian, Hash-M. [AMS Technology Center Knoxville (United States)

    2014-08-15

    A wireless sensor network (WSN) system can offer tremendous benefits to equipment condition monitoring in newly-constructed and/or refurbished nuclear power plants (NPPs). However, it has not been widely accepted so far because of the following requirements by the NPP operators ectromagnetic (EM) emissions from the wireless transceivers must not interfere with the functionalities of the sensitive safety and protection systems in the plant, WSN must perform reliably in the presence of high levels of EM interference from devices such as relays and motor driven pumps, and ionizing radiation sources, dependable WSN performance in harsh industrial environments that are cluttered with cable trays, piping, valves, pumps, motors, and concrete and steel structures, and trict compliance with nuclear regulatory guidelines on EM emissions by the wireless devices. This paper will review the key issues associated with the deployment of WSN for equipment condition monitoring in NPPs. Some promising WSN technologies that can be used in NPP applications are also discussed.

  12. Nuclear power plant monitoring and fault diagnosis methods based on the artificial intelligence technique

    International Nuclear Information System (INIS)

    Yoshikawa, S.; Saiki, A.; Ugolini, D.; Ozawa, K.

    1996-01-01

    The main objective of this paper is to develop an advanced diagnosis system based on the artificial intelligence technique to monitor the operation and to improve the operational safety of nuclear power plants. Three different methods have been elaborated in this study: an artificial neural network local diagnosis (NN ds ) scheme that acting at the component level discriminates between normal and abnormal transients, a model-based diagnostic reasoning mechanism that combines a physical causal network model-based knowledge compiler (KC) that generates applicable diagnostic rules from widely accepted physical knowledge compiler (KC) that generates applicable diagnostic rules from widely accepted physical knowledge. Although the three methods have been developed and verified independently, they are highly correlated and, when connected together, form a effective and robust diagnosis and monitoring tool. (authors)

  13. An electromagnetic field measurement protocol for monitoring power lines

    International Nuclear Information System (INIS)

    Lubritto, C.; Iavazzo, A.; D'Onofrio, A.; Palmieri, A.; Sabbarese, C.; Terrasi, F.

    2002-01-01

    In the actions aiming to prevent risks related to the exposure to Low Frequencies Non Ionising electromagnetic Radiations (ELF-NIR), always arises the need to perform measurements in order to assess the field level existing in the considered sites. As a matter of fact very often it turns out difficult to predict, on the base of calculations, with sufficient approximation the field levels, due to extended variability of environmental conditions (e.g. coexistence of several sources, ground and building conformation, etc..). The measurement procedures must follow a methodology that could allow to minimise the interferences with the measurement set-up and the systematic and accidental errors. Risks for the operator and damages to the instrument should also be taken into account. One of the goal set for this research program was then the definition of the measurement protocol for electromagnetic field generated by low frequency non ionising radiation sources. In particular sources like power lines will be considered in order to validate the protocol by means of in-field measurements

  14. Seismic fragility levels of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.; Hofmayer, C.H.

    1987-01-01

    Seismic fragility levels of safety-related electrical and mechanical equipment used in nuclear power plants are discussed. The fragility level is defined as the vibration level corresponding to initiation of equipment malfunctions. The test response spectrum is used as a measure of this vibration level. The fragility phenomenon of an equipment is represented by a number of response spectra corresponding to various failure modes. Analysis methods are described for determination of the fragility level by use of existing test data. Useful conversion factors are tabulated to transform test response spectra from one damping value to another. Results are presented for switch-gears and motor control centers. The capacity levels of these equipment assemblies are observed to be limited by malfunctioning of contactors, motor starters, relays and/or switches. The applicability of the fragility levels, determined in terms of test response spectra, to Seismic Margin Studies and Probabilistic Risk Assessments is discussed and specific recommendations are provided

  15. Advanced power cycler with intelligent monitoring strategy of IGBT module under test

    DEFF Research Database (Denmark)

    Choi, U. M.; Blaabjerg, F.; Iannuzzo, F.

    2017-01-01

    and diode, which for the wear-out condition monitoring are presented. This advanced power cycler allows to perform power cycling test cost-effectively under conditions close to real power converter applications. In addition, an intelligent monitoring strategy for the separation of package-related wear......-out failure mechanisms has been proposed. By means of the proposed method, the wear-out failure mechanisms of an IGBT module can be separated without any additional efforts during the power cycling tests. The validity and effectiveness of the proposed monitoring strategy are also verified by experiments....

  16. Aerobic Capacity and Anaerobic Power Levels of the University Students

    Science.gov (United States)

    Taskin, Cengiz

    2016-01-01

    The aim of study was to analyze aerobic capacity and anaerobic power levels of the university students. Total forty university students who is department physical education and department business (age means; 21.15±1.46 years for male and age means; 20.55±1.79 years for female in department physical education), volunteered to participate in this…

  17. Online Vce measurement method for wear-out monitoring of high power IGBT modules

    DEFF Research Database (Denmark)

    Beczkowski, Szymon; Ghimire, Pramod; de Vega, Angel Ruiz

    2013-01-01

    A simple Vce online monitoring circuit is presented in this paper. It allows an accurate wear out prediction of IGBT modules, in high-power applications, during normal converter operation. Bipolar measurement allows monitoring of both IGBT and antiparallel diode. The circuit uses two serial...... offset due to diodes' forward voltage temperature dependency. Using four diodes one can monitor voltages on all power devices in a converter leg....

  18. Radiation monitoring data on the power-up test of HTTR. Results up to 20 MW operation

    International Nuclear Information System (INIS)

    Ashikagaya, Yoshinobu; Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji

    2002-01-01

    The High Temperature Engineering Test Reactor (HTTR) have completed the Power-up test of 9 MW (the single and parallel loaded operation) in the rated operation mode. After that the Power-up test in the rated operation mode and the high-temperature test operation mode with a thermal output of 20 MW (the single and parallel loaded operation) were performed between January 16, 2001 and June 10, 2001. This report describes the radiation monitoring data carried out during the HTTR Power-up test in the rated operation mode and the high-temperature test operation mode with a thermal output of 20 MW. The followings were concluded from these radiation monitoring data. The monitoring of radioactive gaseous effluents and the radiation protection for the works will be easy to do and the exposure dose of the workers will be kept the low level. (author)

  19. An analysis of the water-level monitoring system for a boiling-water reactor

    International Nuclear Information System (INIS)

    Carlson, R.W.; Belblidia, L.A.; Russell, J.L. Jr.

    1985-01-01

    The water-level instrumentation system is very important to the overall safety of a BWR. This system is being monitored by the Safety Parameter Display System (SPDS) that is being installed in Georgia Power Company's Plant Hatch. One of the most significant functions of the SPDS is the comparison of redundant instrument readings and formation of the best estimate of each parameter from those readings which are consistent. When comparing water-level instrument readings, it is necessary to correct the individual readings for differences between current and calibration conditions as well as for differences between calibration conditions for the multiple instruments. This paper documents the examination of the water-level instrumentation system at Plant Hatch and presents the development of the equations that were used to determine the differences between indicated and actual water levels. (author)

  20. Power monitoring in space nuclear reactors using silicon carbide radiation detectors

    Science.gov (United States)

    Ruddy, Frank H.; Patel, Jagdish U.; Williams, John G.

    2005-01-01

    Space reactor power monitors based on silicon carbide (SiC) semiconductor neutron detectors are proposed. Detection of fast leakage neutrons using SiC detectors in ex-core locations could be used to determine reactor power: Neutron fluxes, gamma-ray dose rates and ambient temperatures have been calculated as a function of distance from the reactor core, and the feasibility of power monitoring with SiC detectors has been evaluated at several ex-core locations. Arrays of SiC diodes can be configured to provide the required count rates to monitor reactor power from startup to full power Due to their resistance to temperature and the effects of neutron and gamma-ray exposure, SiC detectors can be expected to provide power monitoring information for the fill mission of a space reactor.

  1. Draft emergency action level guidelines for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-09-15

    This document is provided for interim use during the initial phases of the NRC effort to promptly improve emergency preparedness at operating nuclear power plants. Changes to the document can be expected as experience is gained in its use and public comments are received. Further, the Commission has initiated a rulemaking procedure, now scheduled for completion in January 1930 in the area of Emergency Planning and Preparedness. Additional requirements are to be expected when rulemaking is completed and some modifications to this document may be necessary. Four classes of Emergency Action Levels are established which replace the classes in Regulatory Guide 1.101, each with associated examples of initiating conditions. The classes are: - Notification of Unusual Event; - Alert; - Site Emergency; - General Emergency. The rationale for the notification and alert classes is to provide early and prompt notification of minor events which could lead to more serious consequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. A gradation is provided to assure fuller response preparations for more serious indicators. The site emergency class reflects conditions where some significant releases are likely or are occurring but where a core melt situation is not indicated based on current information. In this situation full mobilization of emergency personnel in tie :near site environs is indicated as well as dispatch of monitoring teams and associated communications. The general emergency class involves actual or imminent substantial core degradation or malting with the potential for loss of containment. The immediate action for this class is sheltering (staying inside) rather thai evacuation until an assessment can be made that (1) an evacuation is indicated and (2) an evacuation, if indicated, can be completed prior to significant release and transport of radioactive material to the affected

  2. Draft emergency action level guidelines for nuclear power plants

    International Nuclear Information System (INIS)

    1979-09-01

    This document is provided for interim use during the initial phases of the NRC effort to promptly improve emergency preparedness at operating nuclear power plants. Changes to the document can be expected as experience is gained in its use and public comments are received. Further, the Commission has initiated a rulemaking procedure, now scheduled for completion in January 1930 in the area of Emergency Planning and Preparedness. Additional requirements are to be expected when rulemaking is completed and some modifications to this document may be necessary. Four classes of Emergency Action Levels are established which replace the classes in Regulatory Guide 1.101, each with associated examples of initiating conditions. The classes are: - Notification of Unusual Event; - Alert; - Site Emergency; - General Emergency. The rationale for the notification and alert classes is to provide early and prompt notification of minor events which could lead to more serious consequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. A gradation is provided to assure fuller response preparations for more serious indicators. The site emergency class reflects conditions where some significant releases are likely or are occurring but where a core melt situation is not indicated based on current information. In this situation full mobilization of emergency personnel in tie :near site environs is indicated as well as dispatch of monitoring teams and associated communications. The general emergency class involves actual or imminent substantial core degradation or malting with the potential for loss of containment. The immediate action for this class is sheltering (staying inside) rather thai evacuation until an assessment can be made that (1) an evacuation is indicated and (2) an evacuation, if indicated, can be completed prior to significant release and transport of radioactive material to the affected

  3. Concept of voltage and frequency monitoring for a nuclear power plant normal power supply system - PWR 1300 MWe

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1990-01-01

    Voltage and frequency monitoring concept for a Nuclear Power Plant Normal Power Supply System (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and e NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  4. Wireless power transfer and data communication for neural implants case study : epilepsy monitoring

    CERN Document Server

    Yilmaz, Gürkan

    2017-01-01

    This book presents new circuits and systems for implantable biomedical applications targeting neural recording. The authors describe a system design adapted to conform to the requirements of an epilepsy monitoring system. Throughout the book, these requirements are reflected in terms of implant size, power consumption, and data rate. In addition to theoretical background which explains the relevant technical challenges, the authors provide practical, step-by-step solutions to these problems. Readers will gain understanding of the numerical values in such a system, enabling projections for feasibility of new projects. Provides complete, system-level perspective for implantable batteryless biomedical system; Extends design example to implementation and long term in-vitro validation; Discusses system design concerns regarding wireless power transmission and wireless data communication, particularly for systems in which both are performed on the same channel/frequency; Presents fully-integrated, implantable syste...

  5. Monitoring and management of tritium from the nuclear power plant effluent

    Science.gov (United States)

    Zhang, Qiaoe; Liu, Ting; Yang, Lili; Meng, De; Song, Dahu

    2018-01-01

    It is important to regulate tritium nuclides from the nuclear power plant effluent, the paper briefly analyzes the main source of tritium, and the regulatory requirements associated with tritium in our country and the United States. The monitoring methods of tritium from the nuclear power plant effluent are described, and the purpose to give some advice to our national nuclear power plant about the effluent of tritium monitoring and management.

  6. Design of megawatt power level heat pipe reactors

    Energy Technology Data Exchange (ETDEWEB)

    Mcclure, Patrick Ray [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dasari, Venkateswara Rao [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reid, Robert Stowers [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-11-12

    An important niche for nuclear energy is the need for power at remote locations removed from a reliable electrical grid. Nuclear energy has potential applications at strategic defense locations, theaters of battle, remote communities, and emergency locations. With proper safeguards, a 1 to 10-MWe (megawatt electric) mobile reactor system could provide robust, self-contained, and long-term power in any environment. Heat pipe-cooled fast-spectrum nuclear reactors have been identified as a candidate for these applications. Heat pipe reactors, using alkali metal heat pipes, are perfectly suited for mobile applications because their nature is inherently simpler, smaller, and more reliable than “traditional” reactors. The goal of this project was to develop a scalable conceptual design for a compact reactor and to identify scaling issues for compact heat pipe cooled reactors in general. Toward this goal two detailed concepts were developed, the first concept with more conventional materials and a power of about 2 MWe and a the second concept with less conventional materials and a power level of about 5 MWe. A series of more qualitative advanced designs were developed (with less detail) that show power levels can be pushed to approximately 30 MWe.

  7. Diagnosis of faults in EDF power plants: from monitoring to diagnosis

    International Nuclear Information System (INIS)

    Joussellin, A.

    1994-06-01

    Electricite de France is constantly is search of means to improve safety and availability in its nuclear power plants. To this end, EDF has designed new monitoring systems for the major components of its units: for turbogenerator and inlet valves monitoring, for reactor coolant pumps monitoring, for internal structures monitoring and for loose parts detection. New techniques for signal acquisition and processing for diagnosis are used and all these monitoring systems are designed with the same general concept on monitoring. Simultaneously, a workstation for monitoring and aid in diagnosis (PSAD) is under development. It will integrate every monitoring system and will constitute an indispensable tool for plant personnel, enabling them to diagnose the condition of plant equipment, and providing them with high efficiency and user-friendly tools. The PSAD will have a flexible architecture, guaranteeing optimum distribution of computing power to make it available where it is needed. (author). 5 figs., 4 refs

  8. Diagnosis of faults in EDF power plants: From monitoring to diagnosis

    International Nuclear Information System (INIS)

    Joussellin, A.; Chevalier, R.

    1994-01-01

    Electricite de France is constantly in search of means to improve safety and availability in its nuclear power plants. To this end, EDF has designed new monitoring systems for the major components of its units: for turbogenerator and inlet valves monitoring, for reactor coolant pumps monitoring, for internal structures monitoring and for loose parts detection. New techniques for signal acquisition and processing for diagnosis are used and all these monitoring systems are designed with the same general concept on monitoring. Simultaneously, a workstation for monitoring and aid in diagnosis (PSAD) is under development. It will integrate every monitoring system and will constitute an indispensable tool for plant personnel, enabling them to diagnose the condition of plant equipment, and providing them with high efficiency and user-friendly tools. The PSAD will have a flexible architecture, guaranteeing optimum distribution of computing power to make it available where it is needed

  9. Environmental Radiological Impact of Nuclear Power. Monitoring and Control Programs

    International Nuclear Information System (INIS)

    Ramos, L. M.

    2000-01-01

    Radioactive contamination of the environment and public exposure to ionizing radiation may result from releases from programmed or accidental operations in regulated activities, or they may be due to preexisting situations such as contamination caused by past accidents, radioactive rain caused by nuclear tests, or increased natural radioactivity resulting from human activities. In many cases, both the emission sources and the environment should be monitored to determine the risk to the population and verify to what extent the limits and conditions established by competent authorities are being observed. Monitoring can be divided into three categories: monitoring of the emission source, of the receiving medium and of members of the public; individual monitoring of the population is extremely rare and would only be considered when estimated doses substantially exceed the annual public dose limit. In practices likely to produce significant radioactive releases, as is the case of nuclear fuel cycle facilities, the limits and conditions for monitoring and controlling them and the requirements for environmental radiological monitoring are established in the licensing process. Programs implemented during normal operation of the facilities form the basis for monitoring in the event of accidents. in addition to environmental radiological monitoring associated with facilities, different countries have monitoring programs outside the facilities zones of influence, in order to ascertain the nationwide radiological fund and determine possible increases in this fund. In Spain, the facilities that generate radioactive waste have effluent storage, treatment and removal systems and radiological monitoring programs based on site and discharge characteristics. The environmental radiological monitoring system is composed of the network implemented by the owners in the nuclear fuel cycle facilities zones of influence, and by nationwide monitoring networks managed by the Consejo de

  10. Sea level hazards: Altimetric monitoring of tsunamis and sea level rise

    Science.gov (United States)

    Hamlington, Benjamin Dillon

    Whether on the short timescale of an impending tsunami or the much longer timescale of climate change-driven sea level rise, the threat stemming from rising and inundating ocean waters is a great concern to coastal populations. Timely and accurate observations of potentially dangerous changes in sea level are vital in determining the precautionary steps that need to be taken in order to protect coastal communities. While instruments from the past have provided in situ measurements of sea level at specific locations across the globe, satellites can be used to provide improved spatial and temporal sampling of the ocean in addition to producing more accurate measurements. Since 1993, satellite altimetry has provided accurate measurements of sea surface height (SSH) with near-global coverage. Not only have these measurements led to the first definitive estimates of global mean sea level rise, satellite altimetry observations have also been used to detect tsunami waves in the open ocean where wave amplitudes are relatively small, a vital step in providing early warning to those potentially affected by the impending tsunami. The use of satellite altimetry to monitor two specific sea level hazards is examined in this thesis. The first section will focus on the detection of tsunamis in the open ocean for the purpose of providing early warning to coastal inhabitants. The second section will focus on estimating secular trends using satellite altimetry data with the hope of improving our understanding of future sea level change. Results presented here will show the utility of satellite altimetry for sea level monitoring and will lay the foundation for further advancement in the detection of the two sea level hazards considered.

  11. Monitoring of atmospheric 3H around Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Gautam, Y.P.; Sharma, A.K.; Sharma, S.; Rao, K.S.; Kumar, J.; Kumar, V.; Singh, B.; Kumar, A.; Hedge, A.G.

    2010-01-01

    Atmospheric tritium activity is measured regularly around Narora Atomic Power Station (NAPS) since gaseous waste, which contains tritium, is being released through a 145 m high stack at NAPS site. Atmospheric data collected during 2004-2008 shows a large variation of 3 H concentration in air, fluctuating in the range of ≤0.2-91.6 Bq m -3 . Significantly, higher tritium levels were measured in samples near the site boundary (1.6 km) of NAPS compared to off-site locations. The atmospheric dilution factor was found to be in the range of 1.1 x 10 -7 -7.3 x 10 -7 s m -3 . The scavenging ratio of NAPS site was found to be varying from 0.2 x 10 4 to 14.1 x 10 4 (Bq m -3 rain water per Bq m -3 air). The inhalation dose to a member of general public at different distances (1.6-30 km) from NAPS site was found to be ranged from 0.08-0.21 μSv year -1 . (author)

  12. 77 FR 24228 - Condition Monitoring Techniques for Electric Cables Used in Nuclear Power Plants

    Science.gov (United States)

    2012-04-23

    ... Used in Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... guide, (RG) 1.218, ``Condition Monitoring Techniques for Electric Cables Used in Nuclear Power Plants... of electric cables for nuclear power plants. RG 1.218 is not intended to be prescriptive, instead it...

  13. Development of a VxWorks-based distributed power quality monitoring system

    Energy Technology Data Exchange (ETDEWEB)

    Shin, M.J.; Kim, S.J.; Son, Y.I.; Kang, S.H. [Myongji Univ., Yongin (Korea, Republic of). Next-generation Power Technology Center

    2007-07-01

    Electric utilities are becoming increasingly concerned about power quality because end user equipment is more sensitive to disturbances within the power supply system and also within the consumer facilities. In order to improve the quality of electricity, the sources and causes of disturbances must be known. However, voltage sag and swell, wave-faults and momentary interruptions are difficult to detect and avoid unless power quality monitoring devices are installed permanently. The impact that alternative energy sources have on power quality was also discussed. When distributed generation is connected to the power grid, it can generate and supply more reliable power to the grid. For a reliable interconnection of distributed power to the grid, monitoring systems should display the status of distributed power and record power events. Lack of source stability in distributed generation such as solar-cells or wind-power creates events that should be measured and stored immediately. This paper presented a newly developed real-time power quality monitoring system for distributed power systems. The system is based on a real-time operating system (OS) and can therefore handle many events that happen simultaneously. The proposed system contains a digital signal processor (MPC7410, Motorola) and an A/D board (VMIVME3122, GE). VxWorks was used to implement the monitoring algorithm. This paper outlined the structure and the functions of the developed Distributed Power Quality Monitoring System. Some experiments were conducted to test the performance of the proposed system. According to test results, the system is compatible with standards of the Institute of Electrical and Electronics Engineers (IEEE) for power quality monitoring. 15 refs., 1 tab., 18 figs.

  14. Knolls Atomic Power Laboratory Environmental Monitoring Report. Calendar Year 2003

    International Nuclear Information System (INIS)

    2003-01-01

    The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations

  15. Knolls Atomic Power Laboratory Environmental Monitoring Report, Calendar Year 2003

    Energy Technology Data Exchange (ETDEWEB)

    None

    2003-12-31

    The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations.

  16. Evaluation of power commissioning of the Mochovce Unit 1 power level up to 100 % Nnom

    International Nuclear Information System (INIS)

    Sarvaic, I.; Mickolci, M.

    1998-01-01

    The document contains an evaluation of the power phase of power commissioning of the Mochovce Unit 1 in the phase up to the power level of 100 % N nom .In the document, the courses and results of tests in this phase of power commissioning are summarized, evaluation of the performance of important systems and equipment of the unit is carried out, and the compliance with Limits and Conditions in the course of the phase is assessed. On this basis, conclusions are drawn and recommendations for the unit to be ready for subsequent phases of the power commissioning. The evaluation was developed by the scientific management of the Mochovce commissioning providing an independent support for the operators for supervising the commissioning tasks from the point of nuclear safety

  17. Technical impacts of high penetration levels of wind power on power system stability

    OpenAIRE

    Flynn, Damian; Rather, Z.; Ardal, Atle; Darco, Salvatore; Hansen, Anca Daniela; Cutululis, Nicolaos Antonio; Sørensen, Poul Ejnar; Estanqueiro, Ana; Gomez, Emilio; Menemenlis, Nickie; Smith, Charlie; Wang, Ye

    2017-01-01

    With increasing penetrations of wind generation, based on power-electronic converters, power systems are transitioning away from well-understood synchronous generator-based systems, with growing implications for their stability. Issues of concern will vary with system size, wind penetration level, geographical distribution and turbine type, network topology, electricity market structure, unit commitment procedures, and other factors. However, variable-speed wind turbines, both onshore and con...

  18. Implementation of a radiological emergency monitoring system for Bruce Power nuclear power plant (Canada); Implementierung eines radiologischen Umgebungsueberwachungsmesssystems fuer das Kernkraftwerk Bruce Power (Kanada)

    Energy Technology Data Exchange (ETDEWEB)

    Madaric, M. [Saphymo GmbH, Frankfurt (Germany)

    2016-07-01

    The Bruce Power nuclear power plant (BP NPP) in Ontario, Canada, is the largest nuclear generating station in the world, operating 8 nuclear reactors producing 6300 MW. In correlation with Bruce Power's safety culture, ''Safety first'' and continuous improvements are essential and substantial parts of the Bruce Power philosophy and management system. After the Fukushima nuclear accident the existing radiological emergency monitoring was analyzed and improved.

  19. Environmental monitoring around the Nuclear Power Plants (NPPs) in India

    International Nuclear Information System (INIS)

    Ravi, P.M.

    2014-01-01

    Environmental Survey Laboratories (ESLs) are established at all major nuclear installations before the commissioning of an installation. As per the lndian regulations, the environmental monitoring around NPPs are carried out by an independent body. Accordingly, Environmental Survey Laboratories (ESLs) under Health Physics Division, Bhabha Atomic Research Centre is entrusted with the responsibility. This paper presents the various aspects of environmental monitoring programmes being pursued around Indian NPPs

  20. Environmental monitoring considerations for low-level waste disposal sites

    International Nuclear Information System (INIS)

    Sedlet, J.

    1982-01-01

    All waste disposal sites are required to monitor the environment. The proposed NRC licensing rule, 10 CFR Part 61, requires that such monitoring be conducted before, during, and after a site is operated. An adequate monitoring program consists of measuring concentrations of radionuclides, chemically-toxic substances, and leachate indicators in environmental media and of evaluating specific physical properties of the site. In addition, the composition of the buried waste must be known. Methods for obtaining this information are discussed and monitoring programs are presented for the preoperational, operational, and postclosure phases of a disposal site. Environmental monitoring is considered in a broad context, since it includes monitoring burial trenches onsite, as well as surveillance in the offsite environment. Postclosure monitoring programs will be strongly influenced by the operational monitoring results. In some respects, this phase will be easier since the migration pathways should be well known and the number of radionuclides of concern reduced by radioactive decay. The results of the environmental monitoring program will be vital to successful site operation. These results should be used to determine if operational changes are needed and to predict future environmental impacts

  1. A Low Level Radioactivity Monitor for Aqueous Waste

    International Nuclear Information System (INIS)

    Quirk, E.J.M.

    1968-04-01

    A system is described for continuous monitoring of very low levels of radioactivity in waste water containing typically 3.5 g/l dissolved solids. Spray evaporation of the water enables the dissolved solids to be recovered in the form of an aerosol and collected on a filter tape where the radioactivity is measured by a radiation detector. The advantage of this method compared with a direct measurement is that the attenuating effect of the water is removed and thus greater sensitivity is obtained. Compensation for background and any contamination is achieved by feeding distilled water to the aerosol generator every alternate sampling period and recording the count difference between two successive sampling periods . A printed record of the totalised count difference is obtained once per hour during the integration time of one month. For β radioactivity the minimum values of specific activity measurable extend from 1 x 10 -6 Ci/m 3 to 6 x 10 -8 Ci/m depending on the B end-point energy in the range 167 KeV to 2.26 MeV. The estimated minimum measurable specific activity is 6 x 10 -8 Ci/m 3

  2. A Low Level Radioactivity Monitor for Aqueous Waste

    Energy Technology Data Exchange (ETDEWEB)

    Quirk, E J.M.

    1968-04-15

    A system is described for continuous monitoring of very low levels of radioactivity in waste water containing typically 3.5 g/l dissolved solids. Spray evaporation of the water enables the dissolved solids to be recovered in the form of an aerosol and collected on a filter tape where the radioactivity is measured by a radiation detector. The advantage of this method compared with a direct measurement is that the attenuating effect of the water is removed and thus greater sensitivity is obtained. Compensation for background and any contamination is achieved by feeding distilled water to the aerosol generator every alternate sampling period and recording the count difference between two successive sampling periods . A printed record of the totalised count difference is obtained once per hour during the integration time of one month. For {beta} radioactivity the minimum values of specific activity measurable extend from 1 x 10{sup -6} Ci/m{sup 3} to 6 x 10{sup -8} Ci/m depending on the B end-point energy in the range 167 KeV to 2.26 MeV. The estimated minimum measurable specific activity is 6 x 10{sup -8} Ci/m{sup 3}.

  3. Radio frequency plasma nitriding of aluminium at higher power levels

    International Nuclear Information System (INIS)

    Gredelj, Sabina; Kumar, Sunil; Gerson, Andrea R.; Cavallaro, Giuseppe P.

    2006-01-01

    Nitriding of aluminium 2011 using a radio frequency plasma at higher power levels (500 and 700 W) and lower substrate temperature (500 deg. C) resulted in higher AlN/Al 2 O 3 ratios than obtained at 100 W and 575 deg. C. AlN/Al 2 O 3 ratios derived from X-ray photoelectron spectroscopic analysis (and corroborated by heavy ion elastic recoil time of flight spectrometry) for treatments preformed at 100 (575 deg. C), 500 (500 deg. C) and 700 W (500 deg. C) were 1.0, 1.5 and 3.3, respectively. Scanning electron microscopy revealed that plasma nitrided surfaces obtained at higher power levels exhibited much finer nodular morphology than obtained at 100 W

  4. Radiation monitoring complete change by an unprecedented nuclear power plant accident

    International Nuclear Information System (INIS)

    Omura, Tomomi

    2011-01-01

    Hydrogen explosion at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company that was triggered by the tsunami generated from the Great East Japan Earthquake led to a series of disasters up to meltdown and melt-through. A large amount of discharge of radioactive substances to the environment due to the disasters marked a sea change in the situation of radiation monitoring in Japan to date. The Japanese Government took the following actions. (1) Establishment of government-led monitoring system through the setup of the Monitoring Coordination Council, (2) Decision on 'Comprehensive Monitoring Program' that implements unified comprehensive radiation monitoring and publishes the results, and (3) Law establishment for radiation monitoring by stipulating immediate implementation systems and implementation points as well as budgetary backup for this purpose. This paper describes the plans to monitor the environment, public facilities, aquatic environment, agricultural land, food, etc., as well as the future challenges. (O.A.)

  5. Improved Power Quality Monitoring through Phasor Measurement Unit Data Interpretation

    DEFF Research Database (Denmark)

    Pertl, Michael; Marinelli, Mattia; Bindner, Henrik W.

    2015-01-01

    and wind power production on the voltage unbalance was analyzed. PMU data and NTP-synchronized data from two different MV networks were used. It has been found that PV production has only a minor negative impact on the voltage unbalance whereas the wind power production has a great positive impact...

  6. Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

    International Nuclear Information System (INIS)

    Sturm, A.; Foerster, R.

    1977-01-01

    Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

  7. Application of wireless sensor networks in personnel dosage monitoring system of nuclear power plant

    International Nuclear Information System (INIS)

    Chen Yonghong; Zhang Dafa; Jiang Wei; Chen Dengke

    2007-01-01

    Aim to meet the need of personnel dosage monitoring of nuclear power plant, a monitoring system was designed which based on wireless sensor network. First, the basic concept was described; the characteristics of the wireless sensor network applied in the monitoring system of nuclear power plant were also been analyzed; the structure of the system was built too. Finally, the special technologies like the choice of communication mode, the security of communication network and orientation that used in the monitoring system were discussed. (authors)

  8. Monitoring biofouling in the seawater tunnel of a coastal power station

    International Nuclear Information System (INIS)

    Sasikumar, N.

    1994-01-01

    Water level difference (head loss) between the seawater intake and the forebay was used to determine the biofouling growth in the cooling-water tunnel of Madras atomic power station, India. During 1986-87, due to biofouling growth in the tunnel, the head loss dropped beyond the permissible limits required for operation of the power plant. The head loss showed an improvement during 1988 and 1989, after exomotive chlorination was adopted instead of shock chlorination. Fouling biomass estimated from the head loss showed a heavy biomass build-up of 535.52 ± 102 tonnes in the tunnel during 1992. The head loss showed a seasonal pattern, very similar to the settlement pattern of foulants in the coastal waters, with maximum values during summer months. On the basis of head-loss data, a suitable chlorination practice has been recommended to the power station. The experience suggested that a continuous monitoring of head loss is a simple and reliable method of estimating and controlling biofouling in power-plant cooling-water tunnels. (author)

  9. A Wave Power Device with Pendulum Based on Ocean Monitoring Buoy

    Science.gov (United States)

    Chai, Hui; Guan, Wanchun; Wan, Xiaozheng; Li, Xuanqun; Zhao, Qiang; Liu, Shixuan

    2018-01-01

    The ocean monitoring buoy usually exploits solar energy for power supply. In order to improve power supply capacity, this paper proposes a wave power device according to the structure and moving character of buoy. The wave power device composes of pendulum mechanism that converts wave energy into mechanical energy and energy storage mechanism where the mechanical energy is transferred quantitatively to generator. The hydrodynamic equation for the motion of buoy system with generator devise is established based on the potential flow theory, and then the characteristics of pendulum motion and energy conversion properties are analysed. The results of this research show that the proposed wave power devise is able to efficiently and periodically convert wave energy into power, and increasing the stiffness of energy storage spring is benefit for enhancing the power supply capacity of the buoy. This study provides a theory reference for the development of technology on wave power generator for ocean monitoring buoy.

  10. A Rotating Speed Controller Design Method for Power Levelling by Means of Inertia Energy in Wind Power Systems

    DEFF Research Database (Denmark)

    Qin, Zian; Blaabjerg, Frede; Loh, Poh Chiang

    2015-01-01

    Power fluctuation caused by wind speed variations may be harmful for the stability of the power system as well as the reliability of the wind power converter, since it may induce thermal excursions in the solder joints of the power modules. Using the wind turbine rotor inertia energy for power...... in the frequency domain for power leveling. Moreover, the impact of other parameters on power leveling, including the time constant of maximum power point tracking (MPPT) and the rotor inertia, are also studied. With the proposed optimal design, the power fluctuations are mitigated as much as possible, while...

  11. Introduction of virtual detectors for core monitoring system of korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Eun, Ki Lee.; Yong, Hee Kim.; Jybe, Ho Cha.; Moon, Ghu Park.

    2000-01-01

    A novel algorithm known as the virtual detector method (VDM) is introduced to reconstruct the axial power shape (APS) for the on-line core monitoring system of the Korean Standard Nuclear Power Plant (KSNP). A pure statistical method (SM) is also introduced and the results are compared with the currently implemented five-mode Fourier fitting method (FFM). VDM adopts nine virtual detector informations coupled with a regression model based on the Alternating Conditional Expectation (ACE) algorithm. VDM uses Fourier fitting with the information of nine virtual detectors expanded from the currently implemented FFM, which uses five-level detector information. By introducing virtual detectors, we can increase the number of axial detectors, and thus expect the computational errors of APS to be reduced. The two methods (SM and VDM) are applied to in-core mapping data from six cycles of Yong Gwang nuclear power plant Units 3 and 4. For ∼ 3500 cases of APSs extracted from a cycle of operation which is simulated by a three-dimensional nodal code, the accuracy of the three methods (SM, VDM, FFM) is compared. The average root mean square (RMS) error and average of axial peaking error of SM and VDM resulted in reduction of more than 50 % and 70 %, respectively, relative to FFM. VDM and SM also show more realistic axial profiles and predict more accurate axial peaking than FFM. These improvements can contribute to a larger thermal margin. SM shows the most accurate results for all cases. VDM can almost obtain the same results as SM, and using far fewer computation steps. VDM can be a useful tool for precisely reconstructing axial power shapes in a core monitoring system. (authors)

  12. Identifications and Monitoring of Power System Dynamics Based on the PMUs and Wavelet Technique

    OpenAIRE

    Samir Avdakovic; Amir Nuhanovic

    2010-01-01

    Low frequency power oscillations may be triggered by many events in the system. Most oscillations are damped by the system, but undamped oscillations can lead to system collapse. Oscillations develop as a result of rotor acceleration/deceleration following a change in active power transfer from a generator. Like the operations limits, the monitoring of power system oscillating modes is a relevant aspect of power system operation and control. Unprevented low-frequency powe...

  13. 25 years of monitoring the Waste Management Center of the Almirante Alvaro Alberto Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, O.C; Barboza, E.; Cardoso, S.N.M., E-mail: landocf@eletronuclear.gov.br, E-mail: barboza@eletronuclear.gov.br, E-mail: sergion@eletronuclear.gov.br [Eletrobras Eletronuclear S.A (ELETONUCLEAR), Paraty, RJ (Brazil). Lab. de Monitoracao Ambiental

    2013-07-01

    The goal of this paper is to present an assessment of 25 years of monitoring of the environment around the Waste Management Center (WMC) of the Almirante Alvaro Alberto Nuclear Power Station (AAANPS) since 1986 until 2011. The Environmental Monitoring Laboratory (EML) has, for purposes, to monitor the environment around the station to verify if there's a potential impact caused by the operation of the two units and to verify the dose rate levels around the waste deposits. The WMC is located in an area belonging to the AAANPS and receive solid waste of low and medium activities from Angra 1 NPP. The waste generated from Angra 2 NPP is stored inside the unit. The EML monitors the environment around the WMC to determine the environmental dose rate. The monitoring is made by direct measurement of the radiation using thermoluminescent dosimeters (TLD). Nowadays, the TLD are installed, at this time, in 6 points at the boundaries of WMC and are changed monthly. The locations of these points were already changed several times to allow the construction of new buildings. The constitution of the TLD are 4 crystals, being 3 crystals of Calcium Sulphate doped with Thulium (CaSO{sub 4}:Tm) with 3 shields and 1 crystal of Lithium Borate doped with Copper (Li{sub 2}B{sub 4}O{sub 7}:Cu) without shield. The results of the TLD measurements are normalized to a period of 30 days to compensate accidental statistical variations of the dose rates. The results, in these 25 years, show that the external area of the WMC is a supervised area, following the Norm CNEN-NN-3.01 - 'Diretrizes Basicas de Protecao Radiologica' - with access permitted only for authorized people. (author)

  14. 25 years of monitoring the Waste Management Center of the Almirante Alvaro Alberto Nuclear Power Station

    International Nuclear Information System (INIS)

    Ferreira, O.C; Barboza, E.; Cardoso, S.N.M.

    2013-01-01

    The goal of this paper is to present an assessment of 25 years of monitoring of the environment around the Waste Management Center (WMC) of the Almirante Alvaro Alberto Nuclear Power Station (AAANPS) since 1986 until 2011. The Environmental Monitoring Laboratory (EML) has, for purposes, to monitor the environment around the station to verify if there's a potential impact caused by the operation of the two units and to verify the dose rate levels around the waste deposits. The WMC is located in an area belonging to the AAANPS and receive solid waste of low and medium activities from Angra 1 NPP. The waste generated from Angra 2 NPP is stored inside the unit. The EML monitors the environment around the WMC to determine the environmental dose rate. The monitoring is made by direct measurement of the radiation using thermoluminescent dosimeters (TLD). Nowadays, the TLD are installed, at this time, in 6 points at the boundaries of WMC and are changed monthly. The locations of these points were already changed several times to allow the construction of new buildings. The constitution of the TLD are 4 crystals, being 3 crystals of Calcium Sulphate doped with Thulium (CaSO 4 :Tm) with 3 shields and 1 crystal of Lithium Borate doped with Copper (Li 2 B 4 O 7 :Cu) without shield. The results of the TLD measurements are normalized to a period of 30 days to compensate accidental statistical variations of the dose rates. The results, in these 25 years, show that the external area of the WMC is a supervised area, following the Norm CNEN-NN-3.01 - 'Diretrizes Basicas de Protecao Radiologica' - with access permitted only for authorized people. (author)

  15. New technologies in nuclear power plant monitoring and diagnosis

    International Nuclear Information System (INIS)

    Tuerkcan, E.; Ciftcioglu, Oe.

    1996-05-01

    The content of the present paper is as follows. In Sec. 2, the Kalman filtering is briefly described and its relevance to conventional time series analysis methods has been emphasized. In this respect, its NPP monitoring and fault diagnosis implementations are given and the important features are pointed out. In Sec. 3, the NN technology is briefly described and the scope is focused on the NPP monitoring and fault diagnosis implementations. The potentialities of this technology are pointed out. In Sec. 4, the wavelet technology is briefly described and the utilization of this technology in Nuclear Technology is demonstrated. In this respect, also the prospective role of this technology for real-time monitoring and fault diagnosis is revealed. Finally, the influence of the new technologies in reliable and cost effective plant operation viewpoint is discussed. (orig./WL)

  16. Water level measurement system in reactor pressure vessel of BWR and hydrogen concentration monitoring system for severe accident

    International Nuclear Information System (INIS)

    Kuroda, Hidehiko; Okazaki, Koki; Shiraishi, Fujio; Kenjyo, Hiroaki; Isoda, Koichiro

    2013-01-01

    TEPCO's Fukushima Daiichi Nuclear Power Station Accident caused severe accident to lose functions of many instrumentation systems. As a result, many important plant parameters couldn't be monitored. In order to monitor plant parameters in the case of severe accident, new instrumentation systems available in the severe conditions are being developed. Water level in reactor pressure vessel and hydrogen concentration in primary containment vessel are one of the most important parameters. Performance test results about water level measurement sensor and hydrogen sensor in severe environmental conditions are described. (author)

  17. Monitoring of radioactive discharges from nuclear power plants

    International Nuclear Information System (INIS)

    Winkelmann, I.; Becker, D.E.; Ruehle, H.

    1994-01-01

    The system of measurement of gaseous and liquid releases from NPP's into the environment in Germany is described. The emissions are continuously monitored by the operators according to uniform regulations and reported to the authorities. The quality of the measurements is assured by officially commissioned experts in accordance with the federal rule. The operators' measurements are supplemented by remote monitoring system operated by the state authorities. The measured discharges are the basis for calculation of the radiation exposure of the public. 5 tabs., 10 refs. (orig.)

  18. Power Replenishment Patch for Spacecraft Health Monitoring Sensors, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — Metis Design Corporation (MDC) proposes the development of a strain-based power replenishment technology to harvest energy for recharging remote sensors. MDC has...

  19. Striction-based Power Monitoring in Space Environment, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — The program delivers a completely new technology solution to isolation and sensing of power flow (current and voltage). Based on striction materials technology,...

  20. A knowledge on environmental radiation monitoring about the influence from Fukushima Dai-ichi Nuclear Power accident

    International Nuclear Information System (INIS)

    Yoshioka, Mitsuo; Terakawa, Kazuyoshi; Kasai, Toshihiro

    2012-01-01

    A large amount of radioactive substances were released in the atmosphere and contaminated a large area across Japan due to the accident at Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company triggered by Great East Japan Earthquake and tsunami on May 11th 2011. At Fukui University of Technology, monitoring of air radiation (gamma ray) and radiation in environmental samples in Fukui prefecture and some areas of Fukushima prefecture were conducted in order to study the influence of radiation and radioactivity on the citizens as well as the perception of this study results by the citizens. Also, in order to study the dependency of the radiation influence on the distance from the accident location, radiation monitoring of fallouts (air-borne dust, rainwater, sediment mud, and so on) was conducted. In this article, the knowledge obtained on environmental radiation monitoring was summarized and reported. Especially, slightly modified dose-level evaluation for internal exposure was reported. (S.K.)

  1. Monitoring of noble gas radioisotopes in nuclear power plant effluents

    International Nuclear Information System (INIS)

    Kabat, M.J.

    1985-01-01

    Monitoring of gaseous radionuclides in the effluents of nuclear facilities is an essential requirement in effluent management programs. Since there is no practical way of removing noble gas radioisotopes from air at release pathways, their accurate monitoring is essential for providing appropriate environmental protection. Emitted γ dose-rate is the limiting factor for concentration-time integral of noble gas in gaseous effluents of reactor facilities. The external exposure to the public from a semi-infinite cloud is directly proportional to both the noble gas isotope concentration and the integrated γ energy per disintegration. Both can be directly measured in gaseous effluent pathways with a suitable detector. The capability of NaI(T1), CaF 2 (Eu) and plastic scintillation detectors to measure the γ-Ci.MeV content of noble gas releases was experimentally evaluated. The combination of CaF 2 (Eu) detector in a pressurized through-flow chamber, with a charge integrating scaler well complied with both γ energy response and detection sensitivity requirements. Noble gas source terms and effluent monitoring criteria are discussed, theoretical and experimental results are presented and a practical, on-line noble gas monitoring system is described

  2. Remote and Centralized Monitoring of PV Power Plants

    DEFF Research Database (Denmark)

    Kopacz, Csaba; Spataru, Sergiu; Sera, Dezso

    2014-01-01

    the inverters within each PV plant. The monitoring software stores the PV measurements in a data warehouse optimized for managing and data mining large amounts of data, from where it can be later visualized, analyzed and exported. By combining PV production measurements data with I-V curve measurements...

  3. Self-powered detector probes for electron and gamma-ray beam monitoring in high-power industrial accelerators

    International Nuclear Information System (INIS)

    Lone, M.A.

    1992-08-01

    A self-powered detector (SPD) is a simple passive device that consists of a coaxial probe with a metallic outer sleeve, a mineral oxide insulating layer, and a metallic inner core. SPDs are used in nuclear reactors for monitoring neutron and gamma ray fields. Responses of various SPDs to electron and gamma ray beams from industrial accelerators were investigated with Monte Carlo simulations. By judicious choice of transmission filters, threshold SPD probes were investigated for on-line monitoring of the beam energy spectrum of the high-power IMPELA industrial electron accelerator. (Author) (14 figs, 16 refs.)

  4. Bulk monitoring of soil for low level transuranic contamination

    International Nuclear Information System (INIS)

    Mandler, J.W.; Randolph, P.D.

    1976-01-01

    A system using γ-ray analysis was developed to survey the soil surrounding retrieval barrels for liquid radioactive waste containing 239 Pu and 241 Am. The performance of scintillation detectors of various sizes for monitoring soil samples was evaluated

  5. High-power fiber optic cable with integrated active sensors for live process monitoring

    Science.gov (United States)

    Blomster, Ola; Blomqvist, Mats; Bergstrand, Hans; Pålsson, Magnus

    2012-03-01

    In industrial applications using high-brilliance lasers at power levels up to and exceeding 20 kW and similarly direct diode lasers of 10 kW, there is an increasing demand to continuously monitor component status even in passive components such as fiber-optic cables. With fiber-optic cables designed according to the European Automotive Industry fiber standard interface there is room for integrating active sensors inside the connectors. In this paper we present the integrated active sensors in the new Optoskand QD fiber-optic cable designed to handle extreme levels of power losses, and how these sensors can be employed in industrial manufacturing. The sensors include photo diodes for detection of scattered light inside the fiber connector, absolute temperature of the fiber connector, difference in temperature of incoming and outgoing cooling water, and humidity measurement inside the fiber connector. All these sensors are connected to the fiber interlock system, where interlock break enable functions can be activated when measured signals are higher than threshold levels. It is a very fast interlock break system as the control of the signals is integrated in the electronics inside the fiber connector. Also, since all signals can be logged it is possible to evaluate what happened inside the connector before the interlock break instance. The communication to the fiber-optic connectors is via a CAN interface. Thus it is straightforward to develop the existing laser host control to also control the CAN-messages from the QD sensors.

  6. Development of self-powered wireless high temperature electrochemical sensor for in situ corrosion monitoring of coal-fired power plant.

    Science.gov (United States)

    Aung, Naing Naing; Crowe, Edward; Liu, Xingbo

    2015-03-01

    Reliable wireless high temperature electrochemical sensor technology is needed to provide in situ corrosion information for optimal predictive maintenance to ensure a high level of operational effectiveness under the harsh conditions present in coal-fired power generation systems. This research highlights the effectiveness of our novel high temperature electrochemical sensor for in situ coal ash hot corrosion monitoring in combination with the application of wireless communication and an energy harvesting thermoelectric generator (TEG). This self-powered sensor demonstrates the successful wireless transmission of both corrosion potential and corrosion current signals to a simulated control room environment. Copyright © 2014 ISA. All rights reserved.

  7. Dynamic Sleep Scheduling on Air Pollution Levels Monitoring with Wireless Sensor Network

    Directory of Open Access Journals (Sweden)

    Gezaq Abror

    2018-01-01

    Full Text Available Wireless Sensor Network (WSN can be applied for Air Pollution Level Monitoring System that have been determined by the Environmental Impact Management Agency which is  PM10, SO2, O3, NO2 and CO. In WSN, node system is constrained to a limited power supply, so that the node system has a lifetime. To doing lifetime maximization, power management scheme is required and sensor nodes should use energy efficiently. This paper proposes dynamic sleep scheduling using Time Category-Fuzzy Logic (Time-Fuzzy Scheduling as a reference for calculating time interval for sleep and activated node system to support power management scheme. This research contributed in power management design to be applied to the WSN system to reduce energy expenditure. From the test result in real hardware node system, it can be seen that Time-Fuzzy Scheduling is better in terms of using the battery and it is better in terms of energy consumption too because it is more efficient 51.85% when it is compared with Fuzzy Scheduling, it is more efficient 68.81% when it is compared with Standard Scheduling and it is more efficient 85.03% when compared with No Scheduling.

  8. Development of a component centered fault monitoring and diagnosis knowledge based system for space power system

    Science.gov (United States)

    Lee, S. C.; Lollar, Louis F.

    1988-01-01

    The overall approach currently being taken in the development of AMPERES (Autonomously Managed Power System Extendable Real-time Expert System), a knowledge-based expert system for fault monitoring and diagnosis of space power systems, is discussed. The system architecture, knowledge representation, and fault monitoring and diagnosis strategy are examined. A 'component-centered' approach developed in this project is described. Critical issues requiring further study are identified.

  9. Prospects of Appliance-Level Load Monitoring in Off-the-Shelf Energy Monitors: A Technical Review

    Directory of Open Access Journals (Sweden)

    Anwar Ul Haq

    2018-01-01

    Full Text Available The smart grid initiative has encouraged utility companies worldwide to roll-out new and smarter versions of energy meters. Before an extensive roll-out, which is both labor-intensive and incurs high capital costs, consumers need to be incentivised to reap the long-term benefits of such smart meters. Off-the-shelf energy monitors (e-monitors can provide consumers with an insight into such potential benefits. As e-monitors are owned by the consumer, the consumer has greater control over the data, which significantly reduces the privacy and data confidentiality concerns. Because only limited online technical information is available about e-monitors, we evaluate several existing e-monitors using an online technical survey directly from the vendors. Besides automated e-monitoring, the use of different off-the-shelf e-monitors can also help to demonstrate state-of-the-art techniques such as non-intrusive load monitoring (NILM, data analytics, and the predictive maintenance of appliances. Our survey indicates a trend towards the incorporation of such state-of-the-art capabilities, particularly the appliance-level e-monitoring and load disaggregation. We have also discussed some essential requirements to implement load disaggregation in the next generation e-monitors. In future, these intelligent e-monitoring techniques will encourage effective consumer participation in the demand-side management (DSM programs.

  10. On-line monitoring of low-level plutonium concentrations

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Huff, G.A.; Rebagay, T.V.

    1979-10-01

    An on-line monitor has been developed to assay plutonium in nitric acid solutions. The performance of the monitor has been assessed by a laboratory experimentation program using solutions with plutonium concentrations from 0.1 to 10 g/l. These conditions are typical of the plutonium solutions in an input stream to a plutonium-purification cycle in a reprocessing plant following uranium/plutonium partitioning. The monitoring system can be fully automated and shows great promise for detecting and quantifying plutonium in situ, thus minimizing the reliance on traditional sampling and laboratory-analysis techniques. The total concentration and isotopic abundance of plutonium are determined by measuring the absolute intensities of the low-energy gamma rays characteristics of 238 Pu, 239 Pu, and 240 Pu nuclides by direct gamma-ray spectroscopy and computer analysis of the spectral data. The addition of a monitoring system of this type to the input stream of a plutonium-purification cycle along with other suitable monitors on the waste streams and on the product stream provides the basis for a near real-time materials control and inventory system. Results of the laboratory-evaluation program employing plutonium in solutions with isotopic compositions typical of those involved in processing light water reactor fuels are presented. The detailed design of a monitoring cell and detection system is given. The precision and accuracy of the results relative to those measured by mass spectrometry and controlled potential coulometry are also summarized

  11. Ex-vessel water-level and fission-product monitoring for LWR

    International Nuclear Information System (INIS)

    DeVolpi, A.; Markoff, D.

    1988-01-01

    Given that the need for direct measurement of reactor coolant inventory under operational or abnormal conditions remains unsatisfied, a high-energy gamma-ray detection system is described for ex-vessel monitoring. The system has been modeled to predict response in a PWR, and the model has been validated with a LOFT LOCA sequence. The apparatus, situated outside the pressure vessel, would give relative water level and density over the entire vessel height and distinguish differing levels in the downcomer and core. It would also have significant sensitivity after power shutdown because of high-energy gamma rays from photoneutron capture, the photoneutrons being the result of fission-product decay in the core. Fission-products released to the coolant and accumulated in the top of a PWR vessel would also be theoretically detectable

  12. Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

    2014-01-01

    The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

  13. Monitored Natural Attenuation as a Remediation Strategy for Nuclear Power Plant Applications

    Science.gov (United States)

    Kim, K.; Bushart, S.

    2009-12-01

    A NRC Information Notice (IN 2006-13) was produced to inform holders of nuclear operating licenses “of the occurrence of radioactive contamination of ground water at multiple facilities due to undetected leakage from facility structures, systems, or components (SSCs) that contain or transport radioactive fluids” so that they could consider actions, as appropriate, to avoid similar problems. To reinforce their commitment to environmental stewardship the nuclear energy industry has committed to improving management of situations that have the potential to lead to the inadvertent release of radioactive fluids. This Industry Groundwater Protection Initiative, finalized in June 2007 as [NEI 07-07], calls for implementation and improvement of on-site groundwater monitoring programs and enhanced communications with stakeholders and regulators about situations related to inadvertent releases. EPRI developed its Groundwater Protection Program to provide the nuclear energy industry with the technical support needed to implement the Industry Groundwater Initiative. An objective of the EPRI Groundwater Protection Program is to provide the nuclear industry with technically sound guidance for implementing and enhancing on-site groundwater monitoring programs. EPRI, in collaboration with the EPRI Groundwater Protection Committee of utility members, developed the EPRI Groundwater Protection Guidelines for Nuclear Power Plants (EPRI Report 1015118, November 2007), which provides site-specific guidance for implementing a technically sound groundwater monitoring program. The guidance applies a graded approach for nuclear plants to tailor a technically effective and cost efficient groundwater monitoring program to the site’s hydrogeology and risk for groundwater contamination. As part of the Groundwater Protection Program, EPRI is also investigating innovative remediation technologies for addressing low-level radioactive contamination in soils and groundwater at nuclear power

  14. Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis

  15. Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

    Energy Technology Data Exchange (ETDEWEB)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis.

  16. Primary shutdown system monitoring unit for nuclear power plants

    International Nuclear Information System (INIS)

    Khan, Tahir Kamal; Balasubramanian, R.; Agilandaeswari, K.

    2013-01-01

    Shut off rods made up of neutron absorbing material are used as Primary Shutdown System. To reduce the power of the reactor under certain abnormal operating conditions, these rods must go down into the core within a specified time. Any malfunctioning in the movement of rods cannot be tolerated and Secondary Shutdown System (SSS) must be actuated within stipulated time to reduce the reactor power. A special safety critical, hardwired electronics unit has been designed to detect failure of PSS Shut off rods movements and generate trip signals for initiating SSS. (author)

  17. Two and three dimensional core power distribution monitor and display

    International Nuclear Information System (INIS)

    Impink, A.J. Jr.; Grobmyer, L.R.

    1988-01-01

    This patent describes a sensor monitoring system for displaying a profile of fractional deviations in relative coolant enthalpy rise over a defined area comprising at least a part of a core of a nuclear reactor, which system comprises: core exit coolant temperature sensors positioned to monitor at least a portion of the defined area; an inlet temperature sensor outside the core which monitors the temperature of core coolant at an inlet to the reactor means, responsive to the outputs from both the core exit temperature sensors and the inlet temperature sensor, for generating corresponding representative values of actual coolant enthalpy rise and corresponding values of relative enthalpy rise at each location in the defined area at which a core exit coolant temperature sensor is available; means, responsive to the generated values of relative enthalpy rise and to reference values of relative enthalpy rise at corresponding locations in the defined area, for generating values of the fractional deviation of the measured values of relative enthalpy rise from the corresponding values; means for interpolating the generated values of fractional deviation in relative enthalpy rise to provide interpolated values of fractional deviation in relative enthalpy rise at locations in the defined area of the core other than those at which core exit coolant temperature sensors are available; and means for multidimensionally displaying the generated and interpolated values

  18. Survey of ambient electromagnetic and radio-frequency interference levels in nuclear power plants

    International Nuclear Information System (INIS)

    Kercel, S.W.; Moore, M.R.; Blakeman, E.D.; Ewing, P.D.; Wood, R.T.

    1996-11-01

    This document reports the results of a survey of ambient electromagnetic conditions in representative nuclear power plants. The U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research engaged the Oak Ridge National Laboratory (ORNL) to perform these measurements to characterize the electromagnetic interference (EMI) and radio-frequency interference (RFI) levels that can be expected in nuclear power plant environments. This survey is the first of its kind, being based on long-term unattended observations. The data presented in this report were measured at eight different nuclear units and required 14 months to collect. A representative sampling of power plant conditions (reactor type, operating mode, site location) monitored over extended observation periods (up to 5 weeks) were selected to more completely determine the characteristic electromagnetic environment for nuclear power plants. Radiated electric fields were measured over the frequency range of 5 MHz to 8 GHz. Radiated magnetic fields and conducted EMI events were measured over the frequency range of 305 Hz to 5 MHz. Highest strength observations of the electromagnetic ambient environment across all measurement conditions at each site provide frequency-dependent profiles for EMI/RFI levels in nuclear power plants

  19. Extended Pulse-Powered Humidity-Freeze Cycling for Testing Module-Level Power Electronics

    Energy Technology Data Exchange (ETDEWEB)

    Hacke, Peter L [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Rodriguez, Miguel [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Kempe, Michael D [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Repins, Ingrid L [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2017-11-28

    An EMI suppression capacitor (polypropylene film type) failed by 'popcorning' due to vapor outgassing in pulse powered humidity-freeze cycles. No shorts or shunts could be detected despite mildly corroded metallization visible in the failed capacitor. Humidity-freeze cycling is optimized to break into moisture barriers. However, further studies will be required on additional module level power electronic (MLPE) devices to optimize the stress testing for condensation to precipitate any weakness to short circuiting and other humidity/bias failure modes.

  20. Low-Power, Chip-Scale, Carbon Dioxide Gas Sensors for Spacesuit Monitoring

    Science.gov (United States)

    Rani, Asha; Shi, Chen; Thomson, Brian; Debnath, Ratan; Wen, Boamei; Motayed, Abhishek; Chullen, Cinda

    2018-01-01

    N5 Sensors, Inc. through a Small Business Technology Transfer (STTR) contract award has been developing ultra-small, low-power carbon dioxide (CO2) gas sensors, suited for monitoring CO2 levels inside NASA spacesuits. Due to the unique environmental conditions within the spacesuits, such as high humidity, large temperature swings, and operating pressure swings, measurement of key gases relevant to astronaut's safety and health such as(CO2), is quite challenging. Conventional non-dispersive infrared absorption based CO2 sensors present challenges inside the spacesuits due to size, weight, and power constraints, along with the ability to sense CO2 in a high humidity environment. Unique chip-scale, nanoengineered chemiresistive gas-sensing architecture has been developed for this application, which can be operated in a typical space-suite environmental conditions. Unique design combining the selective adsorption properties of the nanophotocatalytic clusters of metal-oxides and metals, provides selective detection of CO2 in high relative humidity conditions. All electronic design provides a compact and low-power solution, which can be implemented for multipoint detection of CO2 inside the spacesuits. This paper will describe the sensor architecture, development of new photocatalytic material for better sensor response, and advanced structure for better sensitivity and shorter response times.

  1. Development of an induction motor abnormality monitoring system(IMAMS) using power line signal analysis

    International Nuclear Information System (INIS)

    Jung, Jae Cheon

    1997-02-01

    An induction motor abnormality monitoring system using power line signal analysis is developed in this work. Various studies have focused their attention on the detection of particular harmonic frequencies produced from each defect mode of motors. However, these harmonic frequencies are valuable only when the motor has a continuous slip frequency and operate in constant torque/load condition. The basic concept of the system developed in this work is to detect the characteristic harmonic frequencies occurred when the motor is in abnormal state and to compare it with a predetermined setpoint. Based on these analyses, the place and degree of defect can be easily identified. The experimental results under test bench simulation are also introduced. To find out an alternative way to obtain a threshold level independent of slip/torque, with the rotating field theory, the ratio between harmonic current and total current was calculated with the simplified circuit that is equivalent to two abnormal cases, such as the spatial rotor resistance variation and the symmetrical components changes with field. Also, the threshold level calculation was done with performed the rotating field theory. The results show that they are in good agreement with a experimental results. Further studies are undertaken to extend this work to the on-line monitoring and diagnostic system with a likelihood ratio test method for field application

  2. Development of methods for monitoring and controlling power in nuclear reactors

    International Nuclear Information System (INIS)

    Mesquita, Amir Zacarias; Rezende, Hugo Cesar; Santos, Andre Augusto Campagnole dos; Silva, Vitor Vasconcelos Araujo

    2012-01-01

    Redundancy and diversity are two important criteria for power measurement in nuclear reactors. Other criteria such as accuracy, reliability and response speed are also of major concern. Power monitoring of nuclear reactors is normally done by means of neutronic instruments, i.e. by the measurement of neutron flux. The greater the number of channels for power measuring the greater is the reliability and safety of reactor operations. The aim of this research is to develop new methodologies for on-line monitoring of nuclear reactor power using other reliable processes. One method uses the temperature difference between an instrumented fuel element and the pool water below the reactor core. Another method consists of the steady-state energy balance of the primary and secondary reactor cooling loops. A further method is the calorimetric procedure whereby a constant reactor power is monitored as a function of the temperature-rise rate and the system heat capacity. Another methodology, which does not employ thermal methods, is based on measurement of Cherenkov radiation produced within and around the core. The first three procedures, fuel temperature, energy balance and calorimetric, were implemented in the IPR-R1 TRIGA nuclear research reactor at Belo Horizonte (Brazil) and are the focus of the work described here. Knowledge of the reactor thermal power is very important for precise neutron flux and fuel element burnup calculations. The burnup is linearly dependent on the reactor thermal power and its accuracy is important in the determination of the mass of burned 235 U, fission products, fuel element activity, decay heat power generation and radiotoxicity. The thermal balance method developed in this project is now the standard methodology used for IPR-R1 TRIGA reactor power calibration and the fuel temperature measuring is the most reliable way of on-line monitoring of the reactor power. This research project primarily aims at increasing the reliability and safety of

  3. Radioecological monitoring of the environment of a French nuclear power plant after 12 years in operation

    International Nuclear Information System (INIS)

    Foulquier, L.; Descamps, B.; Roussel, S.

    1992-01-01

    Taking Fessenheim Nuclear Power Plant as an example, this paper gives a description of various types of environmental test carried out under the responsibility of the Operator of Nuclear Power Plants in France: permanent monitoring of radioactivity, periodic radioecological assessments. The main results of measurements taken, show the effect of the Plant to be negligible. 8 refs., 1 fig., 4 tabs

  4. Meteorological monitoring Program in the location to the Juragua Nuclear Power Plant

    International Nuclear Information System (INIS)

    Linares Gonzalez, M.E.; Ramos Biltres, E.O.; Prendes Alonso, M.

    1998-01-01

    The objective gives the work it is to present the meteorological Monitoring program in the Juragua nuclear power plant, which you makes according to the standards settled down by the OIEA, the standards give the World meteorological organization and the demands to the content and elaboration gives the Nuclear Power Plant security documents DTN-1.03.91

  5. A technical system to improve the operational monitoring of the Zaporozh'ye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.

    1997-01-01

    As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)

  6. [Space-time water monitoring system at the Iriklinsk hydroelectric power station].

    Science.gov (United States)

    Deriabin, D G; Poliakov, E G; Priakhina, A A; Karimov, I F

    2002-01-01

    The Microbiosensor B 17677 F test system was applied to make a space-time monitoring of the biotoxicity of water used for production and everyday purposes at the Iriklinsk hydroelectric power station (IHEPS) and to identify the leading causes determining the biotoxicity of tested samples. There were seasonal variations in the biotoxicity with the maximum in spring and with minimum in winter and spring and a relationship of the spring rise in the biotoxicity to water pH changes. There was also an association of the certain values of the biotoxicity of industrial water with the concentration of petroleum products that are major pollutants at the IHEPS. The datum points that characterize the maximum level of technogenic exposure were identified.

  7. Supervision monitoring for radiation environment around Daya Bay and Lingao nuclear power stations

    International Nuclear Information System (INIS)

    Huang Naiming; Chen Zhidong; Song Haiqing; Deng Fei; Lin Qing; Huang Nairong; Zhou Ruidong; Mo Guanghua; Li Lingjuan; Liu Ying; Li Qiaoqin; Lai Liming; Zhou Xue

    2004-01-01

    This paper systematically introduces the supervision monitoring for radiation environment around the Guangdong Daya Bay and Ling Ao nuclear power station by the Guangdong Environmental Radiation Research and Monitoring Center. It includes the monitoring plan, methods, quality assurance, main results and conclusions. The results show that: (1) The gas discharge have not caused any detectable impacts to the terrestrial and atmospheric environment since their operation; (2) 110m Ag could only be detected in seawater in the West Daya Bay in 1995 and 1997 and in sediments in 1997. The maximum annual average in seawater was 3.1 Bq/m 3 , annual average of 110m Ag in sediments was 1.0 Bq/kg(dry). But it was always detectable in pearl oyster, gulfweed and cuttlefish in the West Daya Bay. The 110m Ag concentrations in halobios were relatively higher in 1994, 1996 and 1997. The maximum concentrations in pearl oyster, gulfweed and cuttlefish were 2.2, 1.7 and 5.8 Bq/kg (fresh) respectively. It has significantly decreased with decreasing discharge from the stations since 1997. (3) 137 Cs could be detected in almost all seawater samples in the West Daya Bay and the concentration were relatively higher from 1994-1998. The maximum annual average was laid in 1995 and it was 4.6 Bq/m 3 . After 1999, its concentration ranged in the background level. The concentrations in other marine samples were extremely low and changed in the range of the background. (4) 3 H in seawater in the West Daya Bay would go up as a pulse soon after 3 H discharge from the station and would go down to the background after 3-5 days. The annual average of monitoring results were between 0.8-3.4 Bq/L

  8. Effect of reactor conditions on MSIV-ATWS power level

    International Nuclear Information System (INIS)

    Diamond, D.J.

    1987-01-01

    In a boiling water reactor (BWR) when there is closure of the main steam isolation valves (MSIVs), the energy generated in the core will be transferred to the pressure suppression pool (PSP) via steam that flows out of the relief valves. The pool has limited capacity as a heat sink and hence, if there is no reactor trip [an anticipated transient without scram (ATWS) event], there is the possibility that the pool temperature may rise beyond acceptable limits. The present study was undertaken to determine how the initial reactor conditions affect the power level during an MSIV-ATWS event. The time of interest is the 20- to 30-min period when it is assumed that the reactor is in a quasi equilibrium condition with the water level and pressure fixed, natural circulation conditions and no control rod movement or significant boron in the core. The initial conditions of interest are the time of the cycle and the operating state

  9. ''PSAD'' on-line monitoring and aid to diagnosis workstation: a monitoring tool for EDF power plants

    International Nuclear Information System (INIS)

    Morel, J.; Mazalerat, J.M.; Monnier, B.; Cordier, R.

    1993-01-01

    Like other electricity utilities, Electricite de France seeks to enhance the safety and availability of its nuclear power plants. To this end, for over ten years EDF has been installing on each plant unit two monitoring systems of its own design, one to monitor the primary cooling system, and the other, the turbogenerator set. Since the beginning of this project, widespread progress has been made in techniques of signal acquisition and processing, and in diagnosis using artificial intelligence methods. EDF has decided to call on these advanced techniques in developing its new-generation monitoring equipment, and to integrate them in its development of a workstation for on-line monitoring and diagnosis-support (PSAD: Poste de Surveillance et d'Aide au Diagnostic). PSAD will be a tool for on-line monitoring of the main components in nuclear power plants (initially the main coolant pumps and turbogenerator sets, and soon thereafter, monitoring of internal structures, detection of loose parts in the primary cooling system, etc.). PSAD will provide plant personnel with indispensable support in their diagnosis of the condition of plant equipment. It will integrate user-friendly, high-performance systems that also free the operator from many day-to-day tasks. PSAD will have a flexible architecture, for optimum distribution of the computing power where it is most needed, thereby improving the quality of the data. This paper presents the project objectives and describes work currently under way to implement EDF's diagnosis-support strategy for the years to come. (authors). 5 figs., 6 refs

  10. Proceeding of 26th domestic symposium on present and future of integrity monitoring technology in nuclear power generation facilities

    International Nuclear Information System (INIS)

    2000-06-01

    As the 26th domestic symposium of Atomic Energy Research Committee, the Japan Welding Engineering Society, the symposium was held titled as 'Current status and future of integrity monitoring techniques in nuclear power facilities'. Six speakers gave lectures titled as 'Maintenance and integrity monitoring in nuclear power plants', 'Present status of fatigue and creep-fatigue monitoring techniques in the US', 'Fatigue monitoring system in Tsuruga-1 nuclear power station', 'Vibration monitoring technique of rotational machine', 'SCC monitoring with electrochemical noise analysis' and Monitoring technique for corrosive environments and crack shape'. (T. Tanaka)

  11. Monitoring of external background radiation level in Asa dam ...

    African Journals Online (AJOL)

    An external background ionizing radiation study has been carried out within the Asa Dam Industrial Layout of Ilorin in Kwara State. The study was carried out in 5 stations within the industrial area using two Digilert Nuclear Radiation Monitors. The study has revealed that the external background ionizing radiation is ...

  12. Monitoring operational conditions of vehicle tyre pressure levels and ...

    African Journals Online (AJOL)

    Compliance with vehicle tyre inflation pressure and tread depth standard specifications and legal requirements were monitored by survey study in Kumasi Metropolis, Ghana. The survey covered 400 vehicles, comprising cars (28 %), medium buses (25 %), large capacity buses (15 %) and trucks (32 %). There were wide ...

  13. Continuous emission monitoring systems for power plants. The state-of-the-art

    International Nuclear Information System (INIS)

    Bamberger, J.A.

    1988-01-01

    Continuous monitoring of power plant emissions is performed to improve combustion and control equipment efficiency, and in response to various government agency requirements. This paper focuses upon recent developments in Continuous Emission Monitoring (CEM) and Systems (CEMS) for power plants. Topics presented include the perspective of the U.S. Environmental Protection Agency and the states: Continuous Monitoring of Power Plant Emissions - An EPA Perspective; Pennsylvania's Proposed Continuous Emission Monitoring System Data Telemetry Requirements for Municipal, Hospital and Infectious Waste Incinerators; the importance of quality assurance; Continuous Emission Monitoring and Quality Assurance Requirements for New Power Plants; Highlights of Pennsylvania's Continuous Emission Monitoring System Quality Assurance Program; improved system specifications and data acquisition methods; Improved Specifications for Continuous Emission Monitoring; A Microcomputer-Based Data Acquisition System for CEMS; CEMS applications; Expanded Use of CEMS in Acid Rain Control Programs: Opinions of Users, Control Agencies and Vendors; and an innovative measurement technique to assess electrostatic precipitator performance; The Assessment of Pulverized Coal Fly Ash Collection in Electrostatic Precipitators Using an Instrumental Assessment Technique

  14. Monitoring the Thermal Power of Nuclear Reactors with a Prototype Cubic Meter Antineutrino Detector

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, A; Bowden, N; Misner, A; Palmer, T

    2007-06-27

    In this paper, we estimate how quickly and how precisely a reactor's operational status and thermal power can be monitored over hour to month time scales, using the antineutrino rate as measured by a cubic meter scale detector. Our results are obtained from a detector we have deployed and operated at 25 meter standoff from a reactor core. This prototype can detect a prompt reactor shutdown within five hours, and monitor relative thermal power to 3.5% within 7 days. Monitoring of short-term power changes in this way may be useful in the context of International Atomic Energy Agency's (IAEA) Reactor Safeguards Regime, or other cooperative monitoring regimes.

  15. Sea level monitoring in Africa | Woodworth | African Journal of ...

    African Journals Online (AJOL)

    Information Network for Africa (ODINAfrica) programme are described and a survey of currently existing and planned sea level stations in Africa is presented, together with information on where data for existing stations may be found. Keywords: sea level data applications, sea level data telemetry, sea level networks. African ...

  16. Technical basis for staffing levels at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shurberg, D.A.; Haber, S.B. [Brookhaven National Lab., Upton, NY (United States); Morisseau, D. [Nuclear Regulatory Commission, Washington, DC (United States)] [and others

    1995-04-01

    The objective of this project is to provide a technical basis for the establishment of criteria for minimum staffing levels of licensed and non-licensed NPP shift personnel. Minimum staffing levels for the purpose of this study, are defined as those necessary for successful accomplishment of all safety and additional functions that must be performed in order for the licensee to meet applicable regulatory requirements. This project involves a multi-faceted approach to the investigation of the issue. Relevant NRC documentation was identified and reviewed. Using the information obtained from this documentation review, a test plan was developed to aid in the collection of further information regarding the adequacy of current shift staffing levels. The test plan addresses three different activities to be conducted to provide information to the NRC for use in the assessment of current minimum staffing levels. The first activity is collection of data related to industry shift staffing practices through site visits to seven nuclear power plants. The second activity is a simulator study, which will use licensed operator crews responding to a simulated event, under two different staffing levels. Finally, workload models will be constructed for both licensed and non-licensed personnel, using a priori knowledge of the simulator scenarios with data resulting from one of the staffing levels studied in the simulator, and the data collected from the site visits. The model will then be validated against the data obtained from the second staffing level studied in the simulator. The validated model can then be used to study the impact of changing staffing-related variables on the plant shift crew`s ability to effectively mitigate an event.

  17. Econometric models of power prices. An approach to market monitoring in the Western US

    International Nuclear Information System (INIS)

    Barmack, Matthew; Kahn, Edward; Tierney, Susan; Goldman, Charles

    2008-01-01

    Given the limitations of data and resources available for market monitoring in electricity markets where regional transmission organizations (RTO) do not exist, we argue that econometric models of power prices could provide a useful screening tool for market monitoring. To explore its feasibility, we developed several econometric models of power prices at two major trading hubs in the West: Palo Verde and Mid-Columbia. We show that our models explain a large portion of the variation in power prices in Palo Verde and can establish a benchmark that can be used to identify outlier prices that are potentially the result of anti-competitive behavior. (author)

  18. Substantiation of the radiation monitoring scope in the region of nuclear power plant location

    Energy Technology Data Exchange (ETDEWEB)

    Zykova, A S; Zhakov, Yu A; Yambrovskii, Ya M

    1977-12-01

    To provide radiation safety of the population in the region of nuclear power plant location, it is necessary to define the character and quantity of radiation monitoring. On the basis of radiation monitoring of effluents from operating nuclear power plants it is found that the effluents can be registered at a distance of 5-7 km from the plant. The quantity of sample analysis of the main enviromental objectives must provide an exact definition of the content of radioactive substances produced by radioactive fallouts and effluents from nuclear power plants.

  19. Substantiation of the radiation monitoring scope in the region of nuclear power plant location

    International Nuclear Information System (INIS)

    Zykova, A.S.; Zhakov, Yu.A.; Jambrovskij, Ya.M.

    1977-01-01

    To provide radiation safety of the population in the region of nuclear power plant location, it is necessary to define the character and quantity of radiation monitoring. On the basis of radiation monitoring of flowouts from operating nuclear power plants it is found that the flowouts can be registered at a distance of 5-7 km from the plant. The quantity of sample analysis of the main enviromental objectives must provide an exact definition of the content of radioactive substances produced by radioactive fallouts and flowouts from nuclear power plants

  20. Knowledge-based and integrated monitoring and diagnosis in autonomous power systems

    Science.gov (United States)

    Momoh, J. A.; Zhang, Z. Z.

    1990-01-01

    A new technique of knowledge-based and integrated monitoring and diagnosis (KBIMD) to deal with abnormalities and incipient or potential failures in autonomous power systems is presented. The KBIMD conception is discussed as a new function of autonomous power system automation. Available diagnostic modelling, system structure, principles and strategies are suggested. In order to verify the feasibility of the KBIMD, a preliminary prototype expert system is designed to simulate the KBIMD function in a main electric network of the autonomous power system.

  1. Triboelectric Nanogenerator Enabled Body Sensor Network for Self-Powered Human Heart-Rate Monitoring.

    Science.gov (United States)

    Lin, Zhiming; Chen, Jun; Li, Xiaoshi; Zhou, Zhihao; Meng, Keyu; Wei, Wei; Yang, Jin; Wang, Zhong Lin

    2017-09-26

    Heart-rate monitoring plays a critical role in personal healthcare management. A low-cost, noninvasive, and user-friendly heart-rate monitoring system is highly desirable. Here, a self-powered wireless body sensor network (BSN) system is developed for heart-rate monitoring via integration of a downy-structure-based triboelectric nanogenerator (D-TENG), a power management circuit, a heart-rate sensor, a signal processing unit, and Bluetooth module for wireless data transmission. By converting the inertia energy of human walking into electric power, a maximum power of 2.28 mW with total conversion efficiency of 57.9% was delivered at low operation frequency, which is capable of immediately and sustainably driving the highly integrated BSN system. The acquired heart-rate signal by the sensor would be processed in the signal process circuit, sent to an external device via the Bluetooth module, and displayed on a personal cell phone in a real-time manner. Moreover, by combining a TENG-based generator and a TENG-based sensor, an all-TENG-based wireless BSN system was developed, realizing continuous and self-powered heart-rate monitoring. This work presents a potential method for personal heart-rate monitoring, featured as being self-powered, cost-effective, noninvasive, and user-friendly.

  2. Ultracompact on-chip photothermal power monitor based on silicon hybrid plasmonic waveguides

    Directory of Open Access Journals (Sweden)

    Wu Hao

    2017-01-01

    Full Text Available We propose and demonstrate an ultracompact on-chip photothermal power monitor based on a silicon hybrid plasmonic waveguide (HPWG, which consists of a metal strip, a silicon core, and a silicon oxide (SiO2 insulator layer between them. When light injected to an HPWG is absorbed by the metal strip, the temperature increases and the resistance of the metal strip changes accordingly due to the photothermal and thermal resistance effects of the metal. Therefore, the optical power variation can be monitored by measuring the resistance of the metal strip on the HPWG. To obtain the electrical signal for the resistance measurement conveniently, a Wheatstone bridge circuit is monolithically integrated with the HPWG on the same chip. As the HPWG has nanoscale light confinement, the present power monitor is as short as ~3 μm, which is the smallest photothermal power monitor reported until now. The compactness helps to improve the thermal efficiency and the response speed. For the present power monitor fabricated with simple fabrication processes, the measured responsivity is as high as about 17.7 mV/mW at a bias voltage of 2 V and the power dynamic range is as large as 35 dB.

  3. Design of dynamic power quality monitoring and fault diagnosis system of ship-power system based on Ethernet

    Directory of Open Access Journals (Sweden)

    HU Hongqian

    2018-02-01

    Full Text Available [Objectives] According to situation that the ship power information exchange system based on the traditional field bus has been unable to meet the needs of modern ship power system for informatization, automation, intelligent and safe operation. [Methods] This paper proposes the use of industrial Ethernet Modbus/TCP to make up for lack of field-bus. Then, the data center is established by collecting the inherent data of the field bus of the combined ship power system and collecting the real-time data from the online measurement device based on the Modbus/TCP. Correlation theory and neural network intelligent algorithm are used to analyze big data to complete the dynamic power quality monitoring and fault diagnosis of ship power system. [Results] Finally, the man-machine interface is designed with LabVIEW. [Conclusions] The feasibility of the software and hardware implementation of the scheme is verified by the laboratory platform.

  4. Design and development of Solar Powered Wireless Telemetering System (SPWTS) for Environmental Radiation Monitoring (ERM) of nuclear power plants

    International Nuclear Information System (INIS)

    Mariappan, Bhuvaneswari; Ramachandran, Shanmugalakshmi

    2014-01-01

    Presently, the real time environmental radiation monitoring system installed in the nuclear power plant is based on LAN. Generally data from the surveillance instrument are collected at regular intervals using a lap-top or system/units and taken to the laboratory for downloading the archival data. So a need was felt to design and develop Solar powered Wireless Telemetering System (SPWTS) for Environmental Radiation Monitoring (ERM) of Nuclear Power Plants. SPWTS is used for real-time monitoring and wireless transmission of the on-line data to the Central Control Unit (CCU) to investigate the history of monitored data. Thus, in this paper a wireless mode using Zigbee is proposed, thereby improving scalability, flexibility and continuous radiological surveillance along with data archival facility. The proposed Solar Powered Wireless Telemetering System (SPWTS) comprising of transmitter, intermediate devices and receiver units transmits the ERM data to Central Control Unit (CCU) for storage and display to RADAS unit. In order to meet the coverage distance without data loss, suitable number of repeaters/routers are configured and joined in the network. The entire wireless telemetry system is powered up by solar cells with rechargeable battery backup facility, SPWTS suitable for ERM data transmission module will replace the wired Ethernet environment by wireless mode thereby improving scalability, flexibility and continuous radiological surveillance of the gamma dose monitoring. This module also proposes solutions for wireless transmission of safety related critical data to a remote control unit. Finally, this module promotes interoperability within hierarchical framework by reducing the amount of changes that could be introduced into the existing system. (author)

  5. Technical description and evaluation of BWR hybrid power shape monitoring system. Final report

    International Nuclear Information System (INIS)

    Frogner, B.; Ipaktchi, A.; Yang, C.; Grow, R.; Ho, C.; Kiguchi, T.

    1982-03-01

    This report discusses the method for monitoring BWR cores that has been implemented in the Power Shape Monitoring System (PSMS). The approach has been benchmarked to TIP data from three plants and five fuel cycles and the accuracy of the calculations has been evaluated by using gamma scan data from two plants. A coupled neutronics/thermal-hydraulic nodal code (NODE-B/THERM-B) is used in the PSMS. It has been demonstrated that adaptation of this code to partially fit the TIP readings followed by a statistical characterization of the remaining errors results in better accuracy and improved sensitivity for anomaly detection compared to an approach that is entirely dependent upon the detector readings. The computed power distribution has a one-sigma uncertainty of 6% for the nodal power and 4% for the bundle power. This is significantly better than the plant process computers that actually were used for monitoring those two plants where comparisons were made

  6. Design of an optimal automatic regulator for regulating the power levels of a nuclear reactor in a wind power range

    International Nuclear Information System (INIS)

    Noori Khajavi, M.; Menhaj, M.B.; Ghofrani, M.B.

    2000-01-01

    Nuclear power reactors are, in nature nonlinear and time varying. These characteristics must be considered, if large power variations occur in their working regime. In this paper a robust optimal self-tuning regulator for regulating the power of a nuclear reactor has been designed and simulated. The proposed controller is capable of regulating power levels in a wide power range (10% to 100% power levels). The controller achieves a fast and good transient response. The simulation results show that the proposed controller outperforms the fixed optimal control recently cited in the literature for nuclear power plants

  7. Service life monitoring of the main components at the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Hahn, J.; Vincour, D.

    2007-01-01

    Knowledge and experience gained from the introduction and periodical implementation of life assessment of the major components of the Temelin nuclear power plant is summarized. The initial Soviet technical design of the plant did not incorporate lifetime monitoring and evaluation, therefore it was completed with demonstrative strength and lifetime calculations from Czech companies. Moreover, a Westinghouse primary circuit diagnosis and monitoring system, including the monitoring of temperature and pressure cycles for low-cycle fatigue evaluation, was installed at the plant. The DIALIFE code for the calculation of mainly the low-cycle fatigue of the key pressure components, was developed and installed subsequently as a superstructure to the monitoring system. (author)

  8. Knolls Atomic Power Laboratory annual environmental monitoring report, calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

  9. Knolls Atomic Power Laboratory annual environmental monitoring report, calendar year 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

  10. A cell-level power management IC in BCD-SOI for partial power processing in Concentrating-PV systems

    NARCIS (Netherlands)

    Zaman, M.S.; Wen, Y.; Fernandes, R.; Buter, B.; Doorn, T.S.; Dijkstra, M.; Bergveld, H.J.; Trescases, O.

    2014-01-01

    This work presents a power management IC used to mitigate the effects of mismatch in Concentrating-Photovoltaic (CPV) systems. The IC contains a bi-directional dc-dc converter, an auxiliary boost converter to generate the internal 10 V power supply, as well as protection and monitoring circuits. The

  11. Partial Discharge Monitoring in Power Transformers Using Low-Cost Piezoelectric Sensors.

    Science.gov (United States)

    Castro, Bruno; Clerice, Guilherme; Ramos, Caio; Andreoli, André; Baptista, Fabricio; Campos, Fernando; Ulson, José

    2016-08-10

    Power transformers are crucial in an electric power system. Failures in transformers can affect the quality and cause interruptions in the power supply. Partial discharges are a phenomenon that can cause failures in the transformers if not properly monitored. Typically, the monitoring requires high-cost corrective maintenance or even interruptions of the power system. Therefore, the development of online non-invasive monitoring systems to detect partial discharges in power transformers has great relevance since it can reduce significant maintenance costs. Although commercial acoustic emission sensors have been used to monitor partial discharges in power transformers, they still represent a significant cost. In order to overcome this drawback, this paper presents a study of the feasibility of low-cost piezoelectric sensors to identify partial discharges in mineral insulating oil of power transformers. The analysis of the feasibility of the proposed low-cost sensor is performed by its comparison with a commercial acoustic emission sensor commonly used to detect partial discharges. The comparison between the responses in the time and frequency domain of both sensors was carried out and the experimental results indicate that the proposed piezoelectric sensors have great potential in the detection of acoustic waves generated by partial discharges in insulation oil, contributing for the popularization of this noninvasive technique.

  12. Partial Discharge Monitoring in Power Transformers Using Low-Cost Piezoelectric Sensors

    Directory of Open Access Journals (Sweden)

    Bruno Castro

    2016-08-01

    Full Text Available Power transformers are crucial in an electric power system. Failures in transformers can affect the quality and cause interruptions in the power supply. Partial discharges are a phenomenon that can cause failures in the transformers if not properly monitored. Typically, the monitoring requires high-cost corrective maintenance or even interruptions of the power system. Therefore, the development of online non-invasive monitoring systems to detect partial discharges in power transformers has great relevance since it can reduce significant maintenance costs. Although commercial acoustic emission sensors have been used to monitor partial discharges in power transformers, they still represent a significant cost. In order to overcome this drawback, this paper presents a study of the feasibility of low-cost piezoelectric sensors to identify partial discharges in mineral insulating oil of power transformers. The analysis of the feasibility of the proposed low-cost sensor is performed by its comparison with a commercial acoustic emission sensor commonly used to detect partial discharges. The comparison between the responses in the time and frequency domain of both sensors was carried out and the experimental results indicate that the proposed piezoelectric sensors have great potential in the detection of acoustic waves generated by partial discharges in insulation oil, contributing for the popularization of this noninvasive technique.

  13. Power estimation on functional level for programmable processors

    Directory of Open Access Journals (Sweden)

    M. Schneider

    2004-01-01

    Full Text Available In diesem Beitrag werden verschiedene Ansätze zur Verlustleistungsschätzung von programmierbaren Prozessoren vorgestellt und bezüglich ihrer Übertragbarkeit auf moderne Prozessor-Architekturen wie beispielsweise Very Long Instruction Word (VLIW-Architekturen bewertet. Besonderes Augenmerk liegt hierbei auf dem Konzept der sogenannten Functional-Level Power Analysis (FLPA. Dieser Ansatz basiert auf der Einteilung der Prozessor-Architektur in funktionale Blöcke wie beispielsweise Processing-Unit, Clock-Netzwerk, interner Speicher und andere. Die Verlustleistungsaufnahme dieser Bl¨ocke wird parameterabhängig durch arithmetische Modellfunktionen beschrieben. Durch automatisierte Analyse von Assemblercodes des zu schätzenden Systems mittels eines Parsers können die Eingangsparameter wie beispielsweise der erzielte Parallelitätsgrad oder die Art des Speicherzugriffs gewonnen werden. Dieser Ansatz wird am Beispiel zweier moderner digitaler Signalprozessoren durch eine Vielzahl von Basis-Algorithmen der digitalen Signalverarbeitung evaluiert. Die ermittelten Schätzwerte für die einzelnen Algorithmen werden dabei mit physikalisch gemessenen Werten verglichen. Es ergibt sich ein sehr kleiner maximaler Schätzfehler von 3%. In this contribution different approaches for power estimation for programmable processors are presented and evaluated concerning their capability to be applied to modern digital signal processor architectures like e.g. Very Long InstructionWord (VLIW -architectures. Special emphasis will be laid on the concept of so-called Functional-Level Power Analysis (FLPA. This approach is based on the separation of the processor architecture into functional blocks like e.g. processing unit, clock network, internal memory and others. The power consumption of these blocks is described by parameter dependent arithmetic model functions. By application of a parser based automized analysis of assembler codes of the systems to be estimated

  14. Power estimation on functional level for programmable processors

    Science.gov (United States)

    Schneider, M.; Blume, H.; Noll, T. G.

    2004-05-01

    In diesem Beitrag werden verschiedene Ansätze zur Verlustleistungsschätzung von programmierbaren Prozessoren vorgestellt und bezüglich ihrer Übertragbarkeit auf moderne Prozessor-Architekturen wie beispielsweise Very Long Instruction Word (VLIW)-Architekturen bewertet. Besonderes Augenmerk liegt hierbei auf dem Konzept der sogenannten Functional-Level Power Analysis (FLPA). Dieser Ansatz basiert auf der Einteilung der Prozessor-Architektur in funktionale Blöcke wie beispielsweise Processing-Unit, Clock-Netzwerk, interner Speicher und andere. Die Verlustleistungsaufnahme dieser Bl¨ocke wird parameterabhängig durch arithmetische Modellfunktionen beschrieben. Durch automatisierte Analyse von Assemblercodes des zu schätzenden Systems mittels eines Parsers können die Eingangsparameter wie beispielsweise der erzielte Parallelitätsgrad oder die Art des Speicherzugriffs gewonnen werden. Dieser Ansatz wird am Beispiel zweier moderner digitaler Signalprozessoren durch eine Vielzahl von Basis-Algorithmen der digitalen Signalverarbeitung evaluiert. Die ermittelten Schätzwerte für die einzelnen Algorithmen werden dabei mit physikalisch gemessenen Werten verglichen. Es ergibt sich ein sehr kleiner maximaler Schätzfehler von 3%. In this contribution different approaches for power estimation for programmable processors are presented and evaluated concerning their capability to be applied to modern digital signal processor architectures like e.g. Very Long InstructionWord (VLIW) -architectures. Special emphasis will be laid on the concept of so-called Functional-Level Power Analysis (FLPA). This approach is based on the separation of the processor architecture into functional blocks like e.g. processing unit, clock network, internal memory and others. The power consumption of these blocks is described by parameter dependent arithmetic model functions. By application of a parser based automized analysis of assembler codes of the systems to be estimated the input

  15. Use of neural networks to monitor power plant components

    International Nuclear Information System (INIS)

    Ikonomopoulos, A.; Tsoukalas, L.H.

    1992-01-01

    A new methodology is presented for nondestructive evaluation (NDE) of check valve performance and degradation. Artificial neural network (ANN) technology is utilized for processing frequency domain signatures of check valves operating in a nuclear power plant (NPP). Acoustic signatures obtained from different locations on a check valve are transformed from the time domain to the frequency domain and then used as input to a pretrained neural network. The neural network has been trained with data sets corresponding to normal operation, therefore establishing a basis for check valve satisfactory performance. Results obtained from the proposed methodology demonstrate the ability of neural networks to perform accurate and quick evaluations of check valve performance

  16. Multi-level Simulation of a Real Time Vibration Monitoring System Component

    Science.gov (United States)

    Robertson, Bryan A.; Wilkerson, Delisa

    2005-01-01

    This paper describes the development of a custom built Digital Signal Processing (DSP) printed circuit board designed to implement the Advanced Real Time Vibration Monitoring Subsystem proposed by Marshall Space Flight Center (MSFC) Transportation Directorate in 2000 for the Space Shuttle Main Engine Advanced Health Management System (AHMS). This Real Time Vibration Monitoring System (RTVMS) is being developed for ground use as part of the AHMS Health Management Computer-Integrated Rack Assembly (HMC-IRA). The HMC-IRA RTVMS design contains five DSPs which are highly interconnected through individual communication ports, shared memory, and a unique communication router that allows all the DSPs to receive digitized data fiom two multi-channel analog boards simultaneously. This paper will briefly cover the overall board design but will focus primarily on the state-of-the-art simulation environment within which this board was developed. This 16-layer board with over 1800 components and an additional mezzanine card has been an extremely challenging design. Utilization of a Mentor Graphics simulation environment provided the unique board and system level simulation capability to ascertain any timing or functional concerns before production. By combining VHDL, Synopsys Software and Hardware Models, and the Mentor Design Capture Environment, multiple simulations were developed to verify the RTVMS design. This multi-level simulation allowed the designers to achieve complete operability without error the first time the RTVMS printed circuit board was powered. The HMC-IRA design has completed all engineering and deliverable unit testing. P

  17. On-line monitoring applications at nuclear power plants. A risk informed approach to calibration reduction

    International Nuclear Information System (INIS)

    Shankar, Ramesh; Hussey, Aaron; Davis, Eddie

    2003-01-01

    On-line monitoring of instrument channels provides increased information about the condition of monitored channels through accurate, more frequent evaluation of each cannel's performance over time. This type of performance monitoring is a methodology that offers an alternate approach to traditional time-directed calibration. EPRI's strategic role in on-line monitoring is to facilitate its implementation and cost-effective use in numerous applications at power plants. To this end, EPRI has sponsored an on-line monitoring implementation project at multiple nuclear plants specifically intended to install and use on-line monitoring technology. The selected on-line monitoring method is based on the Multivariate State Estimation Technique. The project has a planned three-year life; seven plants are participating in the project. The goal is to apply on-line monitoring to all types of power plant applications and document all aspects of the implementation process in a series of EPRI reports. These deliverables cover installation, modeling, optimization, and proven cost-benefit. This paper discusses the actual implementation of on-line monitoring to various nuclear plant instrument systems. Examples of detected instrument drift are provided. (author)

  18. Comparison of p53 levels in lymphocytes and in blood plasma of nuclear power plant workers

    International Nuclear Information System (INIS)

    Roessner, Pavel; Chvatalova, Irena; Schmuczerova, Jana; Milcova, Alena; Roessner, Pavel; Sram, Radim J.

    2004-01-01

    p53 levels were assessed in lymphocytes and in blood plasma of workers from two Czech nuclear power plants (NPP): 114 subjects working in Temelin and 108 subjects working in Dukovany. Ionizing radiation (IR) exposure data were available for 64 and 59 subjects working in the monitored zones from the NPP in Temelin and Dukovany, respectively. The short-term doses of IR for these subjects were 0.01 and 0.12 mSv, and the long-term doses were 0.46 and 5.68 mSv, in the Temelin and Dukovany NPP, respectively. As a control group, 46 subjects living in Ceske Budejovice, a city nearby the Temelin NPP, were analyzed. The concentration of p53 in lymphocytes was significantly higher in workers from the monitored zone in the Dukovany NPP (median value 6.4 pg/μg protein, P < 0.001) than in workers from the Temelin NPP (3.2 pg/μg) as well as in the control group (3.5 pg/μg). In contrast, plasma levels of p53 were comparable in the control group (median value 116 pg/ml plasma) and workers from the monitored zone of Dukovany NPP (102 pg/ml), but lower in workers from Temelin NPP (5 pg/ml). Other factors affecting p53 levels were studied. Smoking resulted in increased p53 lymphocyte levels. The effect of polymorphisms in metabolic and DNA repair genes on p53 levels was analyzed. The correlation was found between p53 levels in lymphocytes and p53 codon 72 polymorphism in subjects working in NPPs, but not in the control group. The results of measurement p53 levels in lymphocytes suggest that this biomarker could reflect the short-term as well as long-term effects of low doses IR. Its impact on human health should be further explored

  19. Development of Self-Powered Wireless Structural Health Monitoring (SHM) for Wind Turbine Blades

    Science.gov (United States)

    Lim, Dong-Won

    Wind turbine blade failure can lead to unexpected power interruptions. Monitoring wind turbine blades is important to ensure seamless electricity delivery from power generation to consumers. Structural health monitoring (SHM) enables early recognition of structural problems so that the safety and reliability of operation can be enhanced. This dissertation focuses on the development of a wireless SHM system for wind turbine blades. The sensor is comprised of a piezoelectric energy harvester (EH) and a telemetry unit. The sensor node is mounted on the blade surface. As the blade rotates, the blade flexes, and the energy harvester captures the strain energy on the blade surface. Once sufficient electricity is captured, a pulse is sent from the sensing node to a gateway. Then, a central monitoring algorithm processes a series of pulses received from all three blades. This wireless SHM, which uses commercially available components, can be retrofitted to existing turbines. The harvested energy for sensing can be estimated in terms of two factors: the available strain energy and conversion efficiency. The available strain energy was evaluated using the FAST (Fatigue, Aerodynamics, Structures, and Turbulence) simulator. The conversion efficiency was studied analytically and experimentally. An experimental set-up was designed to mimic the expected strain frequency and amplitude for rotor blades. From a series of experiments, the efficiency of a piezoelectric EH at a typical rotor speed (0.2 Hz) was approximately 0.5%. The power requirement for sending one measurement (280 muJ) can be achieved in 10 minutes. Designing a detection algorithm is challenging due to this low sampling rate. A new sensing approach-the timing of pulses from the transmitter-was introduced. This pulse timing, which is tied to the charging time, is indicative of the structural health. The SHM system exploits the inherent triple redundancy of the three blades. The timing data of the three blades are

  20. Dynamic evaluation of the levelized cost of wind power generation

    International Nuclear Information System (INIS)

    Díaz, Guzmán; Gómez-Aleixandre, Javier; Coto, José

    2015-01-01

    Highlights: • Conventional levelized cost of energy is static and does not consider flexibility. • This paper defines a dynamic version by means of stochastic programming. • A penalty for early exercising is proposed to differentiate static and dynamic. • Results show the effects of feed-in tariff support in low wind sites. • Policy implications are derived on the basis of the static and dynamic measures. - Abstract: This paper discusses an alternative computation method of the levelized cost of energy of distributed wind power generators. Unlike in the conventional procedures, it includes time of commencement as an optimization variable. For that purpose, a methodology from Longstaff and Schwartz’s dynamic program for pricing financial American options is derived, which provides the ability to find the optimum time and value while coping with uncertainty revenues from energy sales and variable capital costs. The results obtained from the analysis of wind records of 50 sites entail that the conventional levelized cost of energy can be broken down into an optimum, minimum (time-dependent) value and a penalty for early exercising, which can be employed to define investment strategies and support policies

  1. CEA contribution to power plant operation with high burnup level

    International Nuclear Information System (INIS)

    1981-03-01

    High level burnup in PWR leads to investigate again the choices carried out in the field of fuel management. French CEA has studied the economic importance of reshuffling technique, cycle length, discharge burnup, and non-operation period between two cycles. Power plants operators wish to work with increased length cycles of 18 months instead of 12. That leads to control problems because the core reactivity cannot be controlled with the only soluble boron: moderator temperature coefficient must be negative. With such cycles, it is necessary to use burnable poisons and for economic reasons with a low penalty in end of cycle. CEA has studied the use of Gd 2 O 3 mixed with fuel or with inert element like Al 2 O 3 . Parametric studies of specific weights, efficacities relatively to the fuel burnup and the fuel enrichment have been carried out. Particular studies of 1 month cycles with Gd 2 O 3 have shown the possibility to control power distribution with a very low reactivity penalty in EOC. In the same time, in the 100 MW PWR-CAP, control reactivity has been made with large use of gadolinia in parallel with soluble boron for the two first cycles

  2. Design of power cable grounding wire anti-theft monitoring system

    Science.gov (United States)

    An, Xisheng; Lu, Peng; Wei, Niansheng; Hong, Gang

    2018-01-01

    In order to prevent the serious consequences of the power grid failure caused by the power cable grounding wire theft, this paper presents a GPRS based power cable grounding wire anti-theft monitoring device system, which includes a camera module, a sensor module, a micro processing system module, and a data monitoring center module, a mobile terminal module. Our design utilize two kinds of methods for detecting and reporting comprehensive image, it can effectively solve the problem of power and cable grounding wire box theft problem, timely follow-up grounded cable theft events, prevent the occurrence of electric field of high voltage transmission line fault, improve the reliability of the safe operation of power grid.

  3. Evaluation of utility monitoring and preoperational hydrothermal modeling at three nuclear power plant sites

    International Nuclear Information System (INIS)

    Marmer, G.J.; Policastro, A.J.

    1977-01-01

    This paper evaluates the preoperational hydrothermal modeling and operational monitoring carried out by utilities as three nuclear-power-plant sites using once-through cooling. Our work was part of a larger study to assess the environmental impact of operating plants for the Nuclear Regulatory Commission (NRC) and the suitability of the NRC Environmental Technical Specifications (Tech Specs) as set up for these plants. The study revealed that the plume mappings at the Kewaunee, Zion, and Quad Cities sites were generally satisfactory in terms of delineating plume size and other characteristics. Unfortunately, monitoring was not carried out during the most critical periods when largest plume size would be expected. At Kewaunee and Zion, preoperational predictions using analytical models were found to be rather poor. At Kewaunee (surface discharge), the Pritchard Model underestimated plume size in the near field, but grossly overestimated the plume's far-field extent. Moreover, lake-level variations affected plume dispersion, yet were not considered in preoperational predictions. At Zion (submerged discharge) the Pritchard Model was successful only in special, simple cases (single-unit operation, no stratification, no reversing currents, no recirculation). Due to neglect of the above-mentioned phenomena, the model underpredicted plume size. At Quad Cities (submerged discharge), the undistorted laboratory model predicted plume dispersion for low river flows. These low flow predictions appear to be reasonable extrapolations of the field data acquired at higher flows

  4. Design of Nuclear Power Plant Online Monitoring System

    International Nuclear Information System (INIS)

    An, Sang-ha; Jeong, Yong-hoon; Chang, Soon-heung; Lee, Song-kyu

    2007-01-01

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

  5. Uncertainty analysis of power monitoring transit time ultrasonic flow meters

    International Nuclear Information System (INIS)

    Orosz, A.; Miller, D. W.; Christensen, R. N.; Arndt, S.

    2006-01-01

    A general uncertainty analysis is applied to chordal, transit time ultrasonic flow meters that are used in nuclear power plant feedwater loops. This investigation focuses on relationships between the major parameters of the flow measurement. For this study, mass flow rate is divided into three components, profile factor, density, and a form of volumetric flow rate. All system parameters are used to calculate values for these three components. Uncertainty is analyzed using a perturbation method. Sensitivity coefficients for major system parameters are shown, and these coefficients are applicable to a range of ultrasonic flow meters used in similar applications. Also shown is the uncertainty to be expected for density along with its relationship to other system uncertainties. One other conclusion is that pipe diameter sensitivity coefficients may be a function of the calibration technique used. (authors)

  6. Water quality monitoring device for nuclear power plant

    International Nuclear Information System (INIS)

    Kubo, Mitsushi.

    1995-01-01

    The device of the present invention measures quality of feedwater after heated in a regenerative heat exchanger device of a coolant cleanup system in a BWR type reactor, to detect ions generated from organic materials decomposed at high temperature and specify the position where impurities are formed. Namely, in a power plant having a reactor coolant cleanup pipeline connected to a feedwater pipeline, a water quality measuring portion is disposed to the feedwater system at the downstream of the junction to the feedwater system pipeline. A water quality sample is taken to measure the water quality in a state where the feedwater heated by a feedwater heater and flowing to the reactor, and the cleanup coolants heated by the regenerative heat exchanger are mixed. Thus, the impurities formed at the down stream of the feedwater system pipeline, as well as the water quality including impurities decomposed in a high temperature state can be measured. (I.S.)

  7. Characteristics of Hydrogen Monitoring Systems for Severe Accident Management at a Nuclear Power Plant

    Science.gov (United States)

    Petrosyan, V. G.; Yeghoyan, E. A.; Grigoryan, A. D.; Petrosyan, A. P.; Movsisyan, M. R.

    2018-02-01

    One of the main objectives of severe accident management at a nuclear power plant is to protect the integrity of the containment, for which the most serious threat is possible ignition of the generated hydrogen. There should be a monitoring system providing information support of NPP personnel, ensuring data on the current state of a containment gaseous environment and trends in its composition changes. Monitoring systems' requisite characteristics definition issues are considered by the example of a particular power unit. Major characteristics important for proper information support are discussed. Some features of progression of severe accident scenarios at considered power unit are described and a possible influence of the hydrogen concentration monitoring system performance on the information support reliability in a severe accident is analyzed. The analysis results show that the following technical characteristics of the combustible gas monitoring systems are important for the proper information support of NPP personnel in the event of a severe accident at a nuclear power plant: measured parameters, measuring ranges and errors, update rate, minimum detectable concentration of combustible gas, monitoring reference points, environmental qualification parameters of the system components. For NPP power units with WWER-440/270 (230) type reactors, which have a relatively small containment volume, the update period for measurement results is a critical characteristic of the containment combustible gas monitoring system, and the choice of monitoring reference points should be focused not so much on the definition of places of possible hydrogen pockets but rather on the definition of places of a possible combustible mixture formation. It may be necessary for the above-mentioned power units to include in the emergency operating procedures measures aimed at a timely heat removal reduction from the containment environment if there are signs of a severe accident phase

  8. Quarkonium level fitting with two-power potentials

    International Nuclear Information System (INIS)

    Joshi, G.C.; Wignall, J.W.G.

    1981-01-01

    An attempt has been made to fit psi and UPSILON energy levels and leptonic decay width ratios with a non-relativistic potential model using a potential of the form V(r) = Arsup(p) + Brsup(q) + C. It is found that reasonable fits to states below hadronic decay threshold can be obtained for values of the powers p and q anywhere along a family of curves in the (p,q) plane that smoothly join the Martin potential (p = 0, q = 0.1) to the potential forms with p approximately -1 suggested by QCD; for the latter case the best fit is obtained with q approximately 0.4 - 0.5

  9. Experimental study of rectenna coupling at low power level

    International Nuclear Information System (INIS)

    Douyère, A; Alicalapa, F; Lan Sun Luk, J-D; Rivière, S

    2013-01-01

    The experimental results presented in this paper focus on the performance of a rectenna array by studying the effect of mutual coupling between two rectennas. The measurements in several planes of the space are investigated and used to help us to define the minimum distance for future rectenna arrays that can be used at a low power density level. The single element chosen for the array is composed of a rectifier circuit and a CSPA (Circular Slot Patch Antenna). This study shows that at a distance greater than 6cm (λ/2) between two rectennas in reception, we observe that the DC received voltage is constant in the Y plane, while in the X plane, the DC received voltage remains constant whatever the distance. We deduce that these rectennas are uncoupled in this case. We can consider each rectenna like an independent system.

  10. Condition monitoring of electrical equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Sugarman, A.

    1986-01-01

    Condition monitoring (CM) is a subset of maintenance testing. It is a quantitative, predictive technique for assessing the effects of all types of aging (environmental, cyclic, operational, etc) on the ''health'' of the equipment. A difference between CM and maintenance testing is that the latter is neither quantitative (i.e., measures the relative condition of the component or material as opposed to merely verifying that its condition is acceptable) nor predictive (i.e., makes judgments, on the ability of the component to perform at a future time). A common example of the principle of CM can be illustrated with the automobile which has a lifetime that is small enough to observe all the periods (break in, random failure, wear out) that occur throughout aging. There are several weak link components in the car (e.g., water hoses, contacts in the distributor, generator, spark plug cables, solenoid, etc) which if they fail will cause failure of the automobile to either start or run. From the day the car is put on the road and is subjected to heat and vibration, significant aging of these components occurs. Degradation in the water hoses, for example is manifested by the elastomeric casing becoming brittle and cracking

  11. Monitoring device for the power distribution within a nuclear reactor core

    International Nuclear Information System (INIS)

    Tanzawa, Tomio; Kumanomido, Hironori; Toyoshi, Isamu.

    1986-01-01

    Purpose: To provide a monitoring device for the power distribution in the reactor core that calculates the power distribution based on the measurement by instruments disposed within the reactor core of BWR type reactors. Constitution: The power distribution monitoring device in a reactor core comprises a signal correcting device, a signal normalizing device and a power distribution calculating device, in which the power distribution calculating device is constituted with an average power calculating device for four fuel assemblies and an average power calculating device for fuel assemblies. Gamma-ray signals corrected by the signal correcting device and signals from neutron detectors are inputted to the signal normalizing device, both of which are calibrated to determine the axial gamma-ray signal distribution in the central water gap region with the four fuel assemblies being as the unit. The average power from the four fuel assemblies are inputted to the fuel assembly average power calculating device to allocate to each of the fuel assembly average power thereby attaining the purpose. Further, thermal restriction values are calculated thereby enabling to secure the fuel integrity. (Kamimura, M.)

  12. A Design of Wireless Sensor Networks for a Power Quality Monitoring System

    Directory of Open Access Journals (Sweden)

    Sanggil Kang

    2010-11-01

    Full Text Available Power grids deal with the business of generation, transmission, and distribution of electric power. Recently, interest in power quality in electrical distribution systems has increased rapidly. In Korea, the communication network to deliver voltage, current, and temperature measurements gathered from pole transformers to remote monitoring centers employs cellular mobile technology. Due to high cost of the cellular mobile technology, power quality monitoring measurements are limited and data gathering intervals are large. This causes difficulties in providing the power quality monitoring service. To alleviate the problems, in this paper we present a communication infrastructure to provide low cost, reliable data delivery. The communication infrastructure consists of wired connections between substations and monitoring centers, and wireless connections between pole transformers and substations. For the wireless connection, we employ a wireless sensor network and design its corresponding data forwarding protocol to improve the quality of data delivery. For the design, we adopt a tree-based data forwarding protocol in order to customize the distribution pattern of the power quality information. We verify the performance of the proposed data forwarding protocol quantitatively using the NS-2 network simulator.

  13. A design of wireless sensor networks for a power quality monitoring system.

    Science.gov (United States)

    Lim, Yujin; Kim, Hak-Man; Kang, Sanggil

    2010-01-01

    Power grids deal with the business of generation, transmission, and distribution of electric power. Recently, interest in power quality in electrical distribution systems has increased rapidly. In Korea, the communication network to deliver voltage, current, and temperature measurements gathered from pole transformers to remote monitoring centers employs cellular mobile technology. Due to high cost of the cellular mobile technology, power quality monitoring measurements are limited and data gathering intervals are large. This causes difficulties in providing the power quality monitoring service. To alleviate the problems, in this paper we present a communication infrastructure to provide low cost, reliable data delivery. The communication infrastructure consists of wired connections between substations and monitoring centers, and wireless connections between pole transformers and substations. For the wireless connection, we employ a wireless sensor network and design its corresponding data forwarding protocol to improve the quality of data delivery. For the design, we adopt a tree-based data forwarding protocol in order to customize the distribution pattern of the power quality information. We verify the performance of the proposed data forwarding protocol quantitatively using the NS-2 network simulator.

  14. Conceptual design of intravenous fluids level monitoring system - a review

    Science.gov (United States)

    Verma, Prikshit; Padmani, Aniket; Boopathi, M.

    2017-11-01

    In today’s world of automation, there are advancements going on in all the fields. Each work is being automated day by day. However, if we see our current medical care system, some areas require manual caretaker and are loaded with heavy jobs, which consumes a lot of time. Nevertheless, since the work is related to human health, it should be properly done and that too with accuracy. An example of such a particular work is injecting saline or Intravenous (IV) fluids in a patient. The monitoring of such fluids needs utter attention as if the bottle of the fluid is not changed on time, it may lead to various problems for the patients like backflow of blood, blood loss etc. Various researches have been performed to overcome such critical situation. Different monitoring and alerting techniques are described in different researches. So, in our study, we will go through the researches done in this particular field and will see how different ideas are implemented.

  15. Forest Focus Monitoring Database System - Technical Report 2003 Level II Data

    OpenAIRE

    HIEDERER ROLAND; DURRANT TRACY; GRANKE O.; LAMBOTTE Michel; LORENZ M.; MIGNON B.; OEHMICHEN K.

    2007-01-01

    Forest Focus (Regulation (EC) No 2152/2003) is a Community scheme for harmonized, broad-based, comprehensive and long-term monitoring of European forest ecosystems. Under this scheme the monitoring of air pollution effects on forests is carried out by participating countries on the basis of the systematic network of observation points (Level I) and of the network of observation plots for intensive and continuous monitoring (Level II). According to Article 15(1) of the Forest Focus Regulat...

  16. Forest Focus Monitoring Database System - Technical Report 2006 Level II Data

    OpenAIRE

    HIEDERER Roland; DURRANT Tracy; GRANKE Oliver; LAMBOTTE Michel; LORENZ Martin; MIGNON Bertrand

    2008-01-01

    Forest Focus (Regulation (EC) No 2152/2003) is a Community scheme for harmonized, broadbased, comprehensive and long-term monitoring of European forest ecosystems. Under this scheme the monitoring of air pollution effects on forests is carried out by participating countries on the basis of the systematic network of observation points (Level I) and of the network of observation plots for intensive and continuous monitoring (Level II). According to Article 15(1) of the Forest Focus Regulatio...

  17. Development of an inconel self powered neutron detector for in-core reactor monitoring

    Science.gov (United States)

    Alex, M.; Ghodgaonkar, M. D.

    2007-04-01

    The paper describes the development and testing of an Inconel600 (2 mm diameter×21 cm long) self-powered neutron detector for in-core neutron monitoring. The detector has 3.5 mm overall diameter and 22 cm length and is integrally coupled to a 12 m long mineral insulated cable. The performance of the detector was compared with cobalt and platinum detectors of similar dimensions. Gamma sensitivity measurements performed at the 60Co irradiation facility in 14 MR/h gamma field showed values of -4.4×10 -18 A/R/h/cm (-9.3×10 -24 A/ γ/cm 2-s/cm), -5.2×10 -18 A/R/h/cm (-1.133×10 -23 A/ γ/cm 2-s/cm) and 34×10 -18 A/R/h/cm (7.14×10 -23 A/ γ/cm 2-s/cm) for the Inconel, Co and Pt detectors, respectively. The detectors together with a miniature gamma ion chamber and fission chamber were tested in the in-core Apsara Swimming Pool type reactor. The ion chambers were used to estimate the neutron and gamma fields. With an effective neutron cross-section of 4b, the Inconel detector has a total sensitivity of 6×10 -23 A/nv/cm while the corresponding sensitivities for the platinum and cobalt detectors were 1.69×10 -22 and 2.64×10 -22 A/nv/cm. The linearity of the detector responses at power levels ranging from 100 to 200 kW was within ±5%. The response of the detectors to reactor scram showed that the prompt response of the Inconel detector was 0.95 while it was 0.7 and 0.95 for the platinum and cobalt self-powered detectors, respectively. The detector was also installed in the horizontal flux unit of 540 MW Pressurised Heavy Water Reactor (PHWR). The neutron flux at the detector location was calculated by Triveni code. The detector response was measured from 0.02% to 0.07% of full power and showed good correlation between power level and detector signals. Long-term tests and the dynamic response of the detector to shut down in PHWR are in progress.

  18. Development of an inconel self powered neutron detector for in-core reactor monitoring

    International Nuclear Information System (INIS)

    Alex, M.; Ghodgaonkar, M.D.

    2007-01-01

    The paper describes the development and testing of an Inconel600 (2 mm diameterx21 cm long) self-powered neutron detector for in-core neutron monitoring. The detector has 3.5 mm overall diameter and 22 cm length and is integrally coupled to a 12 m long mineral insulated cable. The performance of the detector was compared with cobalt and platinum detectors of similar dimensions. Gamma sensitivity measurements performed at the 60 Co irradiation facility in 14 MR/h gamma field showed values of -4.4x10 -18 A/R/h/cm (-9.3x10 -24 A/γ/cm 2 -s/cm), -5.2x10 -18 A/R/h/cm (-1.133x10 -23 A/γ/cm 2 -s/cm) and 34x10 -18 A/R/h/cm (7.14x10 -23 A/γ/cm 2 -s/cm) for the Inconel, Co and Pt detectors, respectively. The detectors together with a miniature gamma ion chamber and fission chamber were tested in the in-core Apsara Swimming Pool type reactor. The ion chambers were used to estimate the neutron and gamma fields. With an effective neutron cross-section of 4b, the Inconel detector has a total sensitivity of 6x10 -23 A/nv/cm while the corresponding sensitivities for the platinum and cobalt detectors were 1.69x10 -22 and 2.64x10 -22 A/nv/cm. The linearity of the detector responses at power levels ranging from 100 to 200 kW was within ±5%. The response of the detectors to reactor scram showed that the prompt response of the Inconel detector was 0.95 while it was 0.7 and 0.95 for the platinum and cobalt self-powered detectors, respectively. The detector was also installed in the horizontal flux unit of 540 MW Pressurised Heavy Water Reactor (PHWR). The neutron flux at the detector location was calculated by Triveni code. The detector response was measured from 0.02% to 0.07% of full power and showed good correlation between power level and detector signals. Long-term tests and the dynamic response of the detector to shut down in PHWR are in progress

  19. Development of an inconel self powered neutron detector for in-core reactor monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Alex, M. [Electronics Division, BARC, Mumbai (India)]. E-mail: maryalex@barc.gov.in; Ghodgaonkar, M.D. [Electronics Division, BARC, Mumbai (India)

    2007-04-21

    The paper describes the development and testing of an Inconel600 (2 mm diameterx21 cm long) self-powered neutron detector for in-core neutron monitoring. The detector has 3.5 mm overall diameter and 22 cm length and is integrally coupled to a 12 m long mineral insulated cable. The performance of the detector was compared with cobalt and platinum detectors of similar dimensions. Gamma sensitivity measurements performed at the {sup 60}Co irradiation facility in 14 MR/h gamma field showed values of -4.4x10{sup -18} A/R/h/cm (-9.3x10{sup -24} A/{gamma}/cm{sup 2}-s/cm), -5.2x10{sup -18} A/R/h/cm (-1.133x10{sup -23} A/{gamma}/cm{sup 2}-s/cm) and 34x10{sup -18} A/R/h/cm (7.14x10{sup -23} A/{gamma}/cm{sup 2}-s/cm) for the Inconel, Co and Pt detectors, respectively. The detectors together with a miniature gamma ion chamber and fission chamber were tested in the in-core Apsara Swimming Pool type reactor. The ion chambers were used to estimate the neutron and gamma fields. With an effective neutron cross-section of 4b, the Inconel detector has a total sensitivity of 6x10{sup -23} A/nv/cm while the corresponding sensitivities for the platinum and cobalt detectors were 1.69x10{sup -22} and 2.64x10{sup -22} A/nv/cm. The linearity of the detector responses at power levels ranging from 100 to 200 kW was within {+-}5%. The response of the detectors to reactor scram showed that the prompt response of the Inconel detector was 0.95 while it was 0.7 and 0.95 for the platinum and cobalt self-powered detectors, respectively. The detector was also installed in the horizontal flux unit of 540 MW Pressurised Heavy Water Reactor (PHWR). The neutron flux at the detector location was calculated by Triveni code. The detector response was measured from 0.02% to 0.07% of full power and showed good correlation between power level and detector signals. Long-term tests and the dynamic response of the detector to shut down in PHWR are in progress.

  20. Real-time identification of residential appliance events based on power monitoring

    Science.gov (United States)

    Yang, Zhao; Zhu, Zhicheng; Wei, Zhiqiang; Yin, Bo; Wang, Xiuwei

    2018-03-01

    Energy monitoring for specific home appliances has been regarded as the pre-requisite for reducing residential energy consumption. To enhance the accuracy of identifying operation status of household appliances and to keep pace with the development of smart power grid, this paper puts forward the integration of electric current and power data on the basis of existing algorithm. If average power difference of several adjacent cycles varies from the baseline and goes beyond the pre-assigned threshold value, the event will be flagged. Based on MATLAB platform and domestic appliances simulations, the results of tested data and verified algorithm indicate that the power method has accomplished desired results of appliance identification.

  1. Ultra sensitive sea water radioactivity monitoring system. Autonomous low power consumption equipped with wireless data communication

    International Nuclear Information System (INIS)

    Bonet, H.; Debauche, A.; Lellis, C. de; Adam, V.; Lacroix, J.P.; Put, P. van

    2003-01-01

    Following the recognition of their usefulness by the States and the scientific community, the automatic water monitoring networks were developed again to be able to measure sea water. For that purpose they had to be fully autonomous, have low power consumption (solar panels power supply), use wireless communicating (satellite, GSM, Radio) and be very sensitive (few Bq/m 3 ). It is important to note that radioactivity detection in sea has many constraints: The detection system sensitivity must be very high because of the dilution factor of the ocean. The analysis method has to be adapted: the detection of very low levels of artificial contamination is made difficult due to the natural radioactivity in seawater (i.e., more than 10 kBq of 40 K/m 3 ). The system has to be completely autonomous, 'wireless'. Additional conventional measuring probes must be connected to the system to increase its interest (pH, t deg, salinity, position, meteorology). The system maintenance must be very limited (1/year). Wind and corrosion resistance must be high. The probe must be installed on a buoy. Moreover, some improvements are needed to allow: Amplification Gain drifts due to NaI sensitivity to t deg to be compensated. Net peak area computation in a specific energy range. Interference correction to prevent false alarms due to natural radiation. Very long counting time. (author)

  2. Technical impacts of high penetration levels of wind power on power system stability

    DEFF Research Database (Denmark)

    Flynn, Damian; Rather, Z.; Ardal, Atle

    2017-01-01

    With increasing penetrations of wind generation, based on power-electronic converters, power systems are transitioning away from well-understood synchronous generator-based systems, with growing implications for their stability. Issues of concern will vary with system size, wind penetration level......, geographical distribution and turbine type, network topology, electricity market structure, unit commitment procedures, and other factors. However, variable-speed wind turbines, both onshore and connected offshore through DC grids, offer many control opportunities to either replace or enhance existing...... capabilities. Achieving a complete understanding of future stability issues, and ensuring the effectiveness of new measures and policies, is an iterative procedure involving portfolio development and flexibility assessment, generation cost simulations, load flow, and security analysis, in addition...

  3. Using modular neural networks to monitor accident conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Guo, Z.

    1992-01-01

    Nuclear power plants are very complex systems. The diagnoses of transients or accident conditions is very difficult because a large amount of information, which is often noisy, or intermittent, or even incomplete, need to be processed in real time. To demonstrate their potential application to nuclear power plants, neural networks axe used to monitor the accident scenarios simulated by the training simulator of TVA's Watts Bar Nuclear Power Plant. A self-organization network is used to compress original data to reduce the total number of training patterns. Different accident scenarios are closely related to different key parameters which distinguish one accident scenario from another. Therefore, the accident scenarios can be monitored by a set of small size neural networks, called modular networks, each one of which monitors only one assigned accident scenario, to obtain fast training and recall. Sensitivity analysis is applied to select proper input variables for modular networks

  4. Containment pressure monitoring method after severe accident in nuclear power plant

    International Nuclear Information System (INIS)

    Luo Chuanjie; Zhang Shishui

    2011-01-01

    The containment atmosphere monitoring system in nuclear power plant was designed on the basis of design accident. But containment pressure will increase greatly in a severe accident, and pressure instrument in the containment can't satisfy the monitoring requirement. A new method to monitor the pressure change in the containment after a severe accident was considered, through which accident soften methods can be adopted. Under present technical condition, adding a pressure monitoring channel out of containment for post-severe accident is a considerable method. Daya Bay Nuclear Power Plant implemented this modification, by which the containment release time can be delayed during severe accident, and nuclear safety can be increased. After analysis, this method is safe and feasible. (authors)

  5. Uncertainty Quantification Techniques for Sensor Calibration Monitoring in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, Pradeep; Lin, Guang; Crawford, Susan L.; Konomi, Bledar A.; Coble, Jamie B.; Shumaker, Brent; Hashemian, Hash

    2014-04-30

    This report describes research towards the development of advanced algorithms for online calibration monitoring. The objective of this research is to develop the next generation of online monitoring technologies for sensor calibration interval extension and signal validation in operating and new reactors. These advances are expected to improve the safety and reliability of current and planned nuclear power systems as a result of higher accuracies and increased reliability of sensors used to monitor key parameters. The focus of this report is on documenting the outcomes of the first phase of R&D under this project, which addressed approaches to uncertainty quantification (UQ) in online monitoring that are data-driven, and can therefore adjust estimates of uncertainty as measurement conditions change. Such data-driven approaches to UQ are necessary to address changing plant conditions, for example, as nuclear power plants experience transients, or as next-generation small modular reactors (SMR) operate in load-following conditions.

  6. Uncertainty Quantification Techniques for Sensor Calibration Monitoring in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, Pradeep; Lin, Guang; Crawford, Susan L.; Konomi, Bledar A.; Braatz, Brett G.; Coble, Jamie B.; Shumaker, Brent; Hashemian, Hash

    2013-09-01

    This report describes the status of ongoing research towards the development of advanced algorithms for online calibration monitoring. The objective of this research is to develop the next generation of online monitoring technologies for sensor calibration interval extension and signal validation in operating and new reactors. These advances are expected to improve the safety and reliability of current and planned nuclear power systems as a result of higher accuracies and increased reliability of sensors used to monitor key parameters. The focus of this report is on documenting the outcomes of the first phase of R&D under this project, which addressed approaches to uncertainty quantification (UQ) in online monitoring that are data-driven, and can therefore adjust estimates of uncertainty as measurement conditions change. Such data-driven approaches to UQ are necessary to address changing plant conditions, for example, as nuclear power plants experience transients, or as next-generation small modular reactors (SMR) operate in load-following conditions.

  7. Development of a computerized system for performance monitoring and diagnostics in nuclear power plants

    International Nuclear Information System (INIS)

    Chou, G.H.; Chao, H.J.

    1995-01-01

    An on-line computerized system for thermal performance monitoring and diagnostics has been developed at the Institute of Nuclear Energy Research (INER). It was the product of the ChinShan plant performance Monitoring, Analysis and Diagnostics Expert System (CS-MADES) project sponsored by Taiwan Power Company (TPC). The system can carry out turbine performance monitoring and analysis during normal operation, and yield diagnostic results of component degradation after finding out the missing generation problems. Three subsystems were generated to support the whole system framework. They are Test Data Processing Subsystem (TDPS), On-line Monitoring and Analysis Subsystem (OMAS), and Thermal Performance Diagnostics Expert System (TPDES). Some visible benefits have been gained so far through the prototype system installed at the Chinshan nuclear power station

  8. A field method for monitoring thoron-daughter working level

    International Nuclear Information System (INIS)

    Khan, A.H.; Dhandayatham, R.; Raghavayya, M.; Nambiar, P.P.V.J.

    1975-01-01

    The concept of working level, generally used for radon daughters, has been extended to the daughter products of thoron. Accordingly, thorondaughter working level (TWL) has been defined as the alpha energy released from the ultimate decay of 100 pCi/1 each of the short-lived decay products of thoron. In order to facilitate the evaluation of inhalation hazard in thorium handling areas, a simple field method has been suggested to measure the thoron-daughter working level. A comparison of the potential alpha energies from radon-daughters and that from thoron-daughter is included. (K.B.)

  9. Planning Workshop on Local Level Poverty Monitoring System

    International Development Research Centre (IDRC) Digital Library (Canada)

    Md. Abdul Quader - Ranjan Kumar Guha

    decision making and incorporate these in preparing the development plans and programmes of the ... and highlight the usefulness of the information in local level planning. The aim ..... proper accounts of the cooperatives for its sustainability.

  10. The computerized management for individual monitoring data in Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    Lin Shumou; Yang Xiaochen

    1995-01-01

    The authors report the individual monitoring data management system (IDOSE) at Daya Bay Nuclear Power Station. The components of the individual monitoring system, the design requirements of IDOSE, the characteristics and application of this computerized management system are mainly presented. Its application shows that IDOSE meets the requirements of the concerning occupational standards of the state and matches with the requirements of IAEA/ISOE

  11. Vibration monitoring and diagnostic system developments in the VEIKI for the electric power industry

    International Nuclear Information System (INIS)

    Bessenyei, Z.

    1993-01-01

    Members of the ARGUS family comprising IBM PC-based data logging and data evaluation devices for vibration monitoring and diagnostics have been installed at WWER type nuclear reactors (in Paks, Hungary, and in Kalinin, Russia), and at some fossil fuel power plants in Hungary. The important features of the ARGUS monitoring system are discussed, and application details are presented. (N.T.) 2 figs

  12. Real Time In-circuit Condition Monitoring of MOSFET in Power Converters

    Directory of Open Access Journals (Sweden)

    Shakeb A. Khan

    2015-03-01

    Full Text Available Abstract:This paper presents simple and low-cost, real time in-circuit condition monitoring of MOSFET in power electronic converters. Design metrics requirements like low cost, small size, high power factor, low percentage of total harmonic distortion etc. requires the power electronic systems to operate at high frequencies and at high power density. Failures of power converters are attributed largely by aging of power MOSFETs at high switching frequencies. Therefore, real time in-circuit prognostic of MOSFET needs to be done before their selection for power system design. Accelerated aging tests are performed in different circuits to determine the wear out failure of critical components based on their parametric degradation. In this paper, the simple and low-cost test beds are designed for real time in-circuit prognostics of power MOSFETs. The proposed condition monitoring scheme helps in estimating the condition of MOSFETs at their maximum rated operating condition and will aid the system designers to test their reliability and benchmark them before selecting in power converters.

  13. Fiber optic sensors for monitoring sodium circuits and power grid cables

    Energy Technology Data Exchange (ETDEWEB)

    Kasinathan, M.; Sosamma, S.; Pandian, C.; Vijayakumar, V.; Chandramouli, S.; Nashine, B. K.; Rao, C. B.; Murali, N.; Rajan, K. K.; Jayakumar, T. [IGCAR, Kalpakkam (India)

    2011-07-01

    At Kalpakkam, India, a programme on development of Raman Distributed Temperature sensor (RDTS) for Fast Breeder Reactors (FBR) application is undertaken. Leak detection in sodium circuits of FBR is critical for the safety and performance of the reactors. It is demonstrated that RDTS can be usefully employed in monitoring sodium circuits and in tracking the percolating sodium in case of any leak. Aluminum Conductor Steel Reinforced (ACSR) cable is commonly used as overhead power transmission cable in power grid. A second application demonstrates the suitability of using RDTS to monitor this transmission cable for any defect. (authors)

  14. Nuclear power plant remote monitoring system of Hessen (KFUe Hessen) now fully available

    International Nuclear Information System (INIS)

    Lettmann, W.; Merkel, M.

    1991-01-01

    The remote monitoring system for the Biblis nuclear power station has commenced operation in 1990. It is intended to provide the radiological data and other information required by the supervisory Land authority for performing its supervisory functions in accordance with the Atomic Energy Act. The monitoring station records and reports emissions of the reactor station during specified normal operation and as a result of incidents or accidents, measures local dose rates at four measuring stations at the power plant fence, and records the meteorological conditions. The system is explained in detail, including illustration and graphs. (BBR) [de

  15. Support of the Ukrainian supervisory authority in establishing a modern nuclear power plant monitoring

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.; Nowak, K.

    2000-01-01

    The type of monitoring of nuclear power plants in Ukraine practiced in the early nineties provided the supervisory authority with only inadequate access to information about the current safety status of plants. For the Zaporozhye nuclear power plant, unit 5, a technical system to improve operational monitoring has been designed, installed and commissioned for trial operation at the end of 1995 as a pilot project. The system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables concentration on a continuous monitoring of the state of unit 5 in normal operation and in cases of anormalies or incidents so that when recognisable deviations from the regular plant operation occur, the authority can immediately inquire and if necessary impose conditions on the operator. In 1997, the Information and Crisis Centre of the Ukraninian supervisory authority in Kiev was equipped with the most essential technical means necessary for quasi-simultaneous transfer of data and voice and for monitoring purposes and connected to the Centre to the Zaporozhye system. A similar monitoring system for both VVER-440 units of the Rovno nuclear power plant by analogy with the pilot project was specified and put into operation and connected to the ICC in 1998. (orig.) [de

  16. Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

    1976-12-01

    A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement

  17. Online condition monitoring to enable extended operation of nuclear power plants

    International Nuclear Information System (INIS)

    Meyer, Ryan Michael; Bond, Leonard John; Ramuhalli, Pradeep

    2012-01-01

    Safe, secure, and economic operation of nuclear power plants will remain of strategic significance. New and improved monitoring will likely have increased significance in the post-Fukushima world. Prior to Fukushima, many activities were already underway globally to facilitate operation of nuclear power plants beyond their initial licensing periods. Decisions to shut down a nuclear power plant are mostly driven by economic considerations. Online condition monitoring is a means to improve both the safety and economics of extending the operating lifetimes of nuclear power plants, enabling adoption of proactive aging management. With regard to active components (e.g., pumps, valves, motors, etc.), significant experience in other industries has been leveraged to build the science base to support adoption of online condition-based maintenance and proactive aging management in the nuclear industry. Many of the research needs are associated with enabling proactive management of aging in passive components (e.g., pipes, vessels, cables, containment structures, etc.). This paper provides an overview of online condition monitoring for the nuclear power industry with an emphasis on passive components. Following the overview, several technology/knowledge gaps are identified, which require addressing to facilitate widespread online condition monitoring of passive components. (author)

  18. Virtual instrument for controlling and monitoring digitalized power supply in SSRF

    International Nuclear Information System (INIS)

    Tang Junlong; Chen Huanguang; Chinese Academy of Sciences, Beijing; Xu Ruinian; Shen Tianjian; Li Deming

    2006-01-01

    The Shanghai Synchrotron Radiation Facility (SSRF) needs extremely precise power supplies for their various magnets. A digital controller is being developed for the power converters of the SSRF power supply (PS). In the digital controller, a fully digital pulse-width modulator (PWM) directly controls the power unit insulated gate bipolar transistor (IGBT) of the PS. A program in LabVIEW language has been developed to control and monitor the digital PS via serial communication (RS232) from a PC and to modify its parameters as well. In this article, the software design of the virtual instrument for controlling and monitoring digitalized PS and its associated functions are described, and the essential elements of the program graphical main-VI and sub-VI source code are presented and explained. The communication protocol and the structure of the developed system are also included in this article. (authors)

  19. In Vivo Self-Powered Wireless Cardiac Monitoring via Implantable Triboelectric Nanogenerator.

    Science.gov (United States)

    Zheng, Qiang; Zhang, Hao; Shi, Bojing; Xue, Xiang; Liu, Zhuo; Jin, Yiming; Ma, Ye; Zou, Yang; Wang, Xinxin; An, Zhao; Tang, Wei; Zhang, Wei; Yang, Fan; Liu, Yang; Lang, Xilong; Xu, Zhiyun; Li, Zhou; Wang, Zhong Lin

    2016-07-26

    Harvesting biomechanical energy in vivo is an important route in obtaining sustainable electric energy for powering implantable medical devices. Here, we demonstrate an innovative implantable triboelectric nanogenerator (iTENG) for in vivo biomechanical energy harvesting. Driven by the heartbeat of adult swine, the output voltage and the corresponding current were improved by factors of 3.5 and 25, respectively, compared with the reported in vivo output performance of biomechanical energy conversion devices. In addition, the in vivo evaluation of the iTENG was demonstrated for over 72 h of implantation, during which the iTENG generated electricity continuously in the active animal. Due to its excellent in vivo performance, a self-powered wireless transmission system was fabricated for real-time wireless cardiac monitoring. Given its outstanding in vivo output and stability, iTENG can be applied not only to power implantable medical devices but also possibly to fabricate a self-powered, wireless healthcare monitoring system.

  20. Power distribution monitoring system in the boiling water cooled reactor core

    International Nuclear Information System (INIS)

    Leshchenko, Yu.I.; Sadulin, V.P.; Semidotskij, I.I.

    1987-01-01

    Consideration is being given to the system of physical power distribution monitoring, used during several years in the VK-50 tank type boiling water cooled reactor. Experiments were conducted to measure the ratios of detector prompt and activation currents, coefficients of detector relative sensitivity with respect to neutrons and effective cross sections of 103 Rh interaction with thermal and epithermal neutrons. Mobile self-powered detectors (SPD) with rhodium emitters are used as the power distribution detectors in the considered system. All detectors move simultaneously with constant rate in channels, located in fuel assembly central tubes, when conducting the measurements. It is concluded on the basis of analyzing the obtained data, that investigated system with calibrated SPD enables to monitor the absolute power distribution in fuel assemblies under conditions of boiling water cooled reactor and is independent of thermal engineering measurements conducted by in core instruments

  1. Monitoring of radioactivity in the environs of Finnish nuclear power stations in 1986

    International Nuclear Information System (INIS)

    Ilus, E.; Sjoeblom, K.L.; Aaltonen, H.; Klemola, S.; Arvela, H.

    1987-06-01

    Results of the environmental programmes monitoring radioactivity around the Finnish nuclear power stations in 1986 are reported. After the end of April the fallout nuclides from the Chernobyl accident predominated in all samples taken from the environs of the two power stations Loviisa and Olkiluoto. Radionuclides originating from the Finnish power stations were detected mainly in samples taken from the aquatic environment. The concentrations of the locally discharged nuclides were very low in comparison with the fallout nuclides and their impact on the radiation doses of the population was insignificant. Both nuclear power stations are situated in the main fallout area in Finland. The results of these large monitoring programmes give a good picture of the behaviour of the Chernobyl fallout in the specific areas in Finland

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  3. System for remote routine monitoring of power equipment at TPP and NPP

    International Nuclear Information System (INIS)

    Kantsedalov, V.G.; Samojlenko, V.P.; Doroshenko, V.A.

    1988-01-01

    A system for remote routine monitoring of TPP and NPP pipeline metals is described. The principal functional unit of the system is the unit of remote routine methods and techniques for studying and monitoring the metal and properties. The system is equipped with 5 types of routine monitoring equipment: robots, remote aggregated complexes, periodical diagnostic monitors, other means of metal diagnostics (endoscopes, introscopes). All current information enters the unit for estimating and forecasting the service life of power unit, where it is compared with the standard indices of reliability, duravility and efficiency. The system considered permits to reduce significantly or minimize the scope of works on metal monitoring during overhauls, increase intermonitoring and interrepairing compaigns to 8 years

  4. Indicators for monitoring of safety operation and condition of nuclear power stations

    International Nuclear Information System (INIS)

    Manova, D.

    2001-01-01

    A common goal of all employees in the nuclear power field is safety operation of nuclear power stations. The evaluation and control of NPP safety operation are a part of the elements of safety management. The present report is related only to a part of the total assessment and control of the plant safety operation, namely - the indicator system for monitoring of Kozloduy NPP operation and condition. (author)

  5. Recent Technology of Sensing, Monitoring, Diagnosis, and Maintenance for Aged Electric Power and Energy System

    Science.gov (United States)

    Matsumoto, Satoshi

    This paper deals with the recent topics related to sensing, monitoring, and diagnosis for electric power equipment. Moreover the risk management for such equipments has been an object of study in many terms such as economical, technical aspects, safety and rest, CSR (Corporate Social Responsibility) etc. The relationship between the function of the economic engineering and the maintenance strategy for electric power system are reviewed.

  6. Automatic vibration monitoring system for the diagnostic inspection of the WWER-440 type nuclear power plants

    International Nuclear Information System (INIS)

    Hollo, E.; Siklossy, P.; Toth, Zs.

    1982-01-01

    In the Hungarian Research Institute for Electric Power Industry (VEIKI) an automatic vibration monitoring system for diagnostics and inspection of nuclear power plants of type WWER-440 was developed. The paper summarizes the results of this work and investigates the use of mechanical vibrations and oscillations induced by flow for fault diagnosis. The design of the hardware system, the present software possibilities, the laboratory experiments and the guidelines for future software developments are also described in detail. (A.L.)

  7. Monitoring Blood Sugar: The Importance of Checking Blood Sugar Levels

    Science.gov (United States)

    ... closer to the levels seen in people without diabetes) your child's HbA1c, the better controlled the blood sugars have ... Diabetes Hypoglycemia Diabetes Control: Why It's Important Your Child's Diabetes Health Care Team Helping Kids Deal With Injections ...

  8. Radio Frequency Based Water Level Monitor and Controller for ...

    African Journals Online (AJOL)

    Similarly, the control unit of the prototype performs automatic switching control of on and off on a single phase centrifugal water pump, 220volts, 0.5hp motor via a motor driver circuit (relay). It also incorporates a buzzer that beeps briefly when water level hits 100%, thus causing the pump to be switched off but when water ...

  9. The socio-economic monitoring of the Ignalina Nuclear Power Plant region: methodology, programme, implementation

    International Nuclear Information System (INIS)

    Baubinas, R.; Burneika, D.; Daugirdas, V.

    2002-01-01

    The article is devoted to the argumentation of the main principles of socio-economic monitoring of the Ignalina NPP region. The programme and the territorial levels of the monitoring as well as the main results of the trial of the programme are presented. (author)

  10. Research Based on the Acoustic Emission of Wind Power Tower Drum Dynamic Monitoring Technology

    Science.gov (United States)

    Zhang, Penglin; Sang, Yuan; Xu, Yaxing; Zhao, Zhiqiang

    Wind power tower drum is one of the key components of the wind power equipment. Whether the wind tower drum performs safety directly affects the efficiency, life, and performance of wind power equipment. Wind power tower drum in the process of manufacture, installation, and operation may lead to injury, and the wind load and gravity load and long-term factors such as poor working environment under the action of crack initiation or distortion, which eventually result in the instability or crack of the wind power tower drum and cause huge economic losses. Thus detecting the wind power tower drum crack damage and instability is especially important. In this chapter, acoustic emission is used to monitor the whole process of wind power tower drum material Q345E steel tensile test at first, and processing and analysis tensile failure signal of the material. And then based on the acoustic emission testing technology to the dynamic monitoring of wind power tower drum, the overall detection and evaluation of the existence of active defects in the whole structure, and the acoustic emission signals collected for processing and analysis, we could preliminarily master the wind tower drum mechanism of acoustic emission source. The acoustic emission is a kind of online, efficient, and economic method, which has very broad prospects for work. The editorial committee of nondestructive testing qualification and certification of personnel teaching material of science and technology industry of national defense, "Acoustic emission testing" (China Machine Press, 2005.1).

  11. Frequency Monitoring and Control during Power System Restoration Based on Wide Area Measurement System

    Directory of Open Access Journals (Sweden)

    Saber Nourizadeh

    2011-01-01

    Full Text Available Frequency control during power system restoration has not been strongly addressed. Operators are often concerned with the offline sizing of load and generation steps, but, nowadays, the introduction of Wide Area Measurement System (WAMS makes it possible to monitor the stability of power system online. The constraints of WAMS operation result in some changes in power system frequency control. This paper proposes a novel methodology for frequency control and monitoring during the early steps of power system restoration based on WAMS. Detailed load modeling is achieved based on the static load modeling approach. Power generators' modeling is also accomplished utilizing the single machine equivalent of the power system based on PMU measurements. Simulation results of the presented methodology on the 39 bus New England power system clearly show the effectiveness and applicability of the proposed method. The simulation results show that the presented approach has a completely acceptable precision and an outstanding speed with less than 0.05% error. The outstanding speed of the presented approach along with the result precision will result in a great promotion in power system restoration methodologies.

  12. The Autonomous Stress Indicator for Remotely Monitoring Power System State and Watching for Potential Instability

    Directory of Open Access Journals (Sweden)

    Geza Joos

    2009-02-01

    Full Text Available The proposed Autonomous Stress Indicator (ASI is a device that monitors the contents of the protection relays on a suspect weak power system bus and generates a performance level related to the degree of system performance degradation or instability. This gives the system operators some time (minutes to take corrective action. In a given operating area there would not likely be a need for an ASI on every bus. Note that the ASI does not trip any breakers; it is an INFORMATION ONLY device. An important feature is that the system operator can subsequently interrogate the ASI to determine the factor(s that led to the performance level that has been initially annunciated, thereby leading to a course of action. This paper traces the development of the ASI which is an ongoing project. The ASI could be also described as a stress-alert device whose function is to alert the System Operator of a stressful condition at its location. The characteristics (or essential qualities of this device are autonomy, selectivity, accuracy and intelligence. These will fulfill the requirements of the recommendation of the Canada –US Task Force in the August 2003 system collapse. Preliminary tests on the IEEE 39-bus model indicate that the concept has merit and development work is in progress. While the ASI can be applied to all power system operating conditions, its principal application is to the degraded state of the system where the System Operator must act to restore the system to the secure state before it migrates to a stage of collapse. The work of ASI actually begins with the Areas of Vulnerability and ends with the Predictive Module as described in detail in this paper. An application example of a degraded system using the IEEE 39-bus system is included.

  13. Sodium fast reactor power monitoring using {sup 20}F tagging agent

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R.; Normand, S. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, Centre de Saclay, 91191 Gif sur Yvette Cedex (France); Ban, G. [ENSICAEN, F-14050 Caen (France); Dumarcher, V.; Brau, H. P.; Barbot, L.; Domenech, T.; Kondrasovs, V.; Corre, G.; Frelin, A. M.; Montagu, T.; Dautremer, T.; Barat, E.

    2009-07-01

    This work deals with the use of gamma spectrometry to monitor the fourth generation sodium fast reactor (SFR) power. Simulation part has shown that power monitoring in short response time and with high accuracy is possible measuring delayed gamma emitters produced in the liquid sodium. An experimental test is under preparation at French SFR Phenix experimental reactor to validate simulation studies. Physical calculations have been done to correlate gamma activity to the released thermal power. Gamma emitter production rate in the reactor core was calculated with technical and nuclear data as sodium velocity, atomic densities, neutron spectra and incident neutron cross-sections of fission reactions, and also sodium activation reactions producing gamma emitters. Then, a thermal hydraulic transfer function was used for taking into account primary sodium flow in our calculations. Gamma spectra were then determined by Monte-Carlo simulations. The experiment will be set during the reactor 'ultimate testing'. The Delayed Neutron Detection (DND) system cell has been chosen as the best available primary sodium sample for gamma power monitoring on Phenix reactor due to short sodium transit time from reactor core to measurement sample and homogenized sampling in the reactor hot pool. The main gamma spectrometer is composed of a coaxial high purity germanium diode (HPGe) coupled with a transistor reset preamplifier. The signal is then processed by a digital signal processing system (called Adonis) which always gives optimum answer even for high count rate and various time activity measurements. For power monitoring problematic, use of a short decay period gamma emitter as the {sup 20}F will allow to obtain a very fast response system without cumulative and flow distortion effects. These works introduce advantages and performances of this new power monitoring system for future SFR. (authors)

  14. Biological monitors for low levels of ionising radiation

    International Nuclear Information System (INIS)

    Mohankumar, M.N.; Jeevanram, R.K.

    1995-01-01

    The biological effects of high doses of ionising radiation are well understood and the methods of measurement of these doses well established. However the effects due to extremely low doses remain by and large uncertain. This is because of the fact that at such low doses no gross symptoms are seen. In fact, at these levels the occurrence of double strand breaks leading to the formation of chromosomal aberrations like dicentrics is rare and chances of mutation due to base damage are negligible. Hence neither chromosomal aberration studies nor mutational assays are useful for detecting doses of the order of a few milligray. Results of exhaustive work done by various laboratories indicate that below 20 mGy the chromosomal aberration technique based on scoring of dicentrics cannot distinguish between a linear or a threshold model. However indirect methods like unscheduled DNA synthesis (UDS) and sister chromatid exchanges (SCEs) appear to be promising for the detection of radiation exposures due to low levels of radiation. This report reviews the available literature on the biological effects of low levels of ionising radiation and highlights the merits and demerits of the various methods employed in the measurement of UDS and SCE. The phenomenon of radio-adaptive response (RAR) and its relation to DNA repair is also discussed. (author)

  15. Biological monitors for low levels of ionising radiation

    Energy Technology Data Exchange (ETDEWEB)

    Mohankumar, M N; Jeevanram, R K [Safety Research and Health Physics Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

    1996-12-31

    The biological effects of high doses of ionising radiation are well understood and the methods of measurement of these doses well established. However the effects due to extremely low doses remain by and large uncertain. This is because of the fact that at such low doses no gross symptoms are seen. In fact, at these levels the occurrence of double strand breaks leading to the formation of chromosomal aberrations like dicentrics is rare and chances of mutation due to base damage are negligible. Hence neither chromosomal aberration studies nor mutational assays are useful for detecting doses of the order of a few milligray. Results of exhaustive work done by various laboratories indicate that below 20 mGy the chromosomal aberration technique based on scoring of dicentrics cannot distinguish between a linear or a threshold model. However indirect methods like unscheduled DNA synthesis (UDS) and sister chromatid exchanges (SCEs) appear to be promising for the detection of radiation exposures due to low levels of radiation. This report reviews the available literature on the biological effects of low levels of ionising radiation and highlights the merits and demerits of the various methods employed in the measurement of UDS and SCE. The phenomenon of radio-adaptive response (RAR) and its relation to DNA repair is also discussed. (author). 98 refs., 11 figs., 4 tabs.

  16. Assessment of environmental gamma radiation levels in the environs of Narora Atomic Power Station (NAPS)

    International Nuclear Information System (INIS)

    Shetty, P.G.; Takale, R.A.; Swarnkar, M.; Sahu, S.K.; Pandit, G.G.; Puranik, V.D.

    2011-01-01

    As a part of the assessment of the environmental impact of the Indian nuclear power programme, radiation surveys are being carried out on continuous basis in the environs of all the nuclear facilities in India using Thermoluminescent Dosimeters. This paper discusses the environmental gamma radiation levels based on the analysis of data generated for year 1989-2009 at twenty-eight locations currently being monitored in and around the environs of NAPS using passive dosimeter. Of these, six are within the exclusion zone (1.6 km) while the remaining twenty two locations are spread over an aerial distance of twenty six km from reactor stack. The annual background gamma levels for NAPS site beyond 1.6 km exclusion zone based on twenty-two monitoring locations are evaluated and seen to be 1.20 ± 0.15 mGy/a. This is comparable with earlier reported pre-operational value 1.24 ± 0.26 mGy/a. From this it can be said that the reactor operations have not contributed to any increase in the gamma radiation levels in the environs of the NAPS region. (author)

  17. Use of a microprocessor in a remote working level monitor

    International Nuclear Information System (INIS)

    Keefe, D.J.; McDowell, W.P.; Groer, P.G.

    1976-01-01

    The instrument described measures the short-lived 222 Rn-daughter concentrations and the Working Level (WL) in sealed ''hot chambers'' located in uranium mines. Radiation-induced pulses from two separate sensors are transmitted through 500 ft. cables to a microprocessor, which processes the pulses and controls the operation of the system. A read-only memory stores a fixed program which is used to calculate the desired concentrations. The results are printed as pCi/l (Rn-daughter concentrations) and WL

  18. Inspection of nuclear power plant piping welds by in-process acoustic emission monitoring

    International Nuclear Information System (INIS)

    Prine, D.W.

    1976-01-01

    The results of using in-process acoustic emission monitoring on nuclear power plant piping welds are discussed. The technique was applied to good and intentionally flawed test welds as well as production welds, and the acoustic emission results are compared to standard NDT methods and selected metallographic cross-sections

  19. Regular control of monitors for effluents from nuclear power plant stacks

    International Nuclear Information System (INIS)

    Stroem, L.

    1979-01-01

    The report describes a test procedure for emission monitoring devices for nuclear power plants. The follosing procedures are described, inspection, determination of the air flow through the stack, measurement and adjustment of the flow in the stack loop, measurement and adjustment of flow and density in the measuring loop, calibration of the gas detector, efficiency of sampling of methyliodide and aerosol. (K.K.)

  20. Building and application of the plant condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.

    2013-01-01

    To achieve the stable operation of nuclear power plants, we developed the plant condition monitoring system based on the heat and mass balance calculation. This system has adopted the heat balance model based on the actual plant data to find the symptoms of the disorder of the equipment by heat balance changes in the turbine system. (author)

  1. Development and application of the plant condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.

    2014-01-01

    To achieve the stable operation of nuclear power plants, we developed the plant condition monitoring system based on the heat and mass balance calculation. In this system, it is a significant feature to adopt the sophisticated heat balance model based on the actual plant data to find the symptoms of anomalies in the turbine system from heat balance changes. (author)

  2. Backfitting of existing nuclear power plants with particulate, iodine and noble gas monitors

    International Nuclear Information System (INIS)

    Marley, M.R.; Geiger, E.L.

    1978-01-01

    A stand-alone microcomputer complete with hardware and software to measure airborne particulate iodine and noble gases is described. This system meets the need at power plants and effluent monitoring. The equipment will accommodate up to 192 channels of input

  3. Radioactivity in the vicinity of Sizewell nuclear power station: marine environmental monitoring, 1983

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1984-01-01

    Regular monitoring of radioactivity in the aquatic environment of the British Isles has continued. A report presents the results of this program in relation to the Sizewell nuclear power station for 1983, so as to supplement the most recently available full report which is for 1982. (author)

  4. 76 FR 55137 - Monitoring the Effectiveness of Maintenance at Nuclear Power Plants

    Science.gov (United States)

    2011-09-06

    ... the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/ . Regulatory guides are not... Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for... comment draft regulatory guide (DG) DG-1278, ``Monitoring the Effectiveness of Maintenance at Nuclear...

  5. Monitoring levels of deoxynivalenol in wheat flour of Brazilian varieties

    Directory of Open Access Journals (Sweden)

    Cristiano L Silva

    2015-03-01

    Full Text Available Deoxynivalenol (DON is a mycotoxin produced by Fusarium graminearum and its intake represents a severe risk to human and animal health. The objective of this study was to evaluate levels of DON in wheat (Triticum aestivum L. flour from two representative locations of south Brazil. Experiments were carried out in Pato Branco (Paraná and Coxilha (Rio Grande do Sul in a randomized complete block design with three replicates. Levels of DON were measured by high-performance liquid chromatography coupled with mass spectrometry (HPLC-MS/MS. This mycotoxin was detected in 97% of samples, ranging from 200 to 4140 u,g kg-1. Only 17% of samples presented DON beyond of the maximum allowed by the Brazilian Health Surveillance Agency up to the year 2012; even though, Fusarium head blight (FHB epidemics were slight low in the growing season that the study was performed. According to our knowledge, this is the first report showing genetic variability of Brazilian cultivars to DON contamination and some genotypes have potential to be exploited as a source of low accumulation of this toxin.

  6. DIMOS: a new generation of nuclear power plant process monitoring systems

    International Nuclear Information System (INIS)

    Vlaminck, M. de; Gilliot, B.; Remacle, J.

    1993-01-01

    A new generation of nuclear power plant supervision systems is described, called DIMOS (DIstributed MOnitoring System). It was installed in August 1991 at the Doel nuclear power plant and is now monitoring reactors 1 and 2. The system represents one of the largest and most advanced process monitoring systems in operation. DIMOS has successfully provided the solution to the old system's limitations such as functional deficiencies, low response time, management and coherence of the data, maintenance costs, spare parts, and system availability. The use of the software development methodologies HOOD and ADA have not only allowed a rapid integration and installation of a robust system, but will also make further developments and improvements possible with maximum flexibility. (Z.S.) 2 figs

  7. Monitoring Disaster-Related Power Outages Using NASA Black Marble Nighttime Light Product

    Science.gov (United States)

    Wang, Z.; Román, M. O.; Sun, Q.; Molthan, A. L.; Schultz, L. A.; Kalb, V. L.

    2018-04-01

    Timely and accurate monitoring of disruptions to the electricity grid, including the magnitude, spatial extent, timing, and duration of net power losses, is needed to improve situational awareness of disaster response and long-term recovery efforts. Satellite-derived Nighttime Lights (NTL) provide an indication of human activity patterns and have been successfully used to monitor disaster-related power outages. The global 500 m spatial resolution National Aeronautics and Space Administration (NASA) Black Marble NTL daily standard product suite (VNP46) is generated from Visible Infrared Imaging Radiometer Suite (VIIRS) Day/Night Band (DNB) onboard the NASA/National Oceanic and Atmospheric Administration (NOAA) Suomi National Polar-orbiting Partnership (Suomi- NPP) satellite, which began operations on 19 January 2012. With its improvements in product accuracy (including critical atmospheric and BRDF correction routines), the VIIRS daily Black Mable product enables systematic monitoring of outage conditions across all stages of the disaster management cycle.

  8. MONITORING DISASTER-RELATED POWER OUTAGES USING NASA BLACK MARBLE NIGHTTIME LIGHT PRODUCT

    Directory of Open Access Journals (Sweden)

    Z. Wang

    2018-04-01

    Full Text Available Timely and accurate monitoring of disruptions to the electricity grid, including the magnitude, spatial extent, timing, and duration of net power losses, is needed to improve situational awareness of disaster response and long-term recovery efforts. Satellite-derived Nighttime Lights (NTL provide an indication of human activity patterns and have been successfully used to monitor disaster-related power outages. The global 500 m spatial resolution National Aeronautics and Space Administration (NASA Black Marble NTL daily standard product suite (VNP46 is generated from Visible Infrared Imaging Radiometer Suite (VIIRS Day/Night Band (DNB onboard the NASA/National Oceanic and Atmospheric Administration (NOAA Suomi National Polar-orbiting Partnership (Suomi- NPP satellite, which began operations on 19 January 2012. With its improvements in product accuracy (including critical atmospheric and BRDF correction routines, the VIIRS daily Black Mable product enables systematic monitoring of outage conditions across all stages of the disaster management cycle.

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

    International Nuclear Information System (INIS)

    Lee, Sang Hak; Kim, Chung Tae

    1997-01-01

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

  10. Design and fabrication of self-powered in-core neutron flux monitor assembly

    International Nuclear Information System (INIS)

    Chung, M.K.; Cho, S.W.; Kang, H.D.; Cho, K.K.; Cho, B.S.; Kang, S.S.

    1980-01-01

    This is the final report on the prototypical fabrication of an in-core neutron flux monitor detector assembly for a specific power reactor conducted by KAERI from July 1, 1978 to December 31, 1979. It is well known that power reactors require a large number of in-core neutron flux detector for reactor regulation and the structures of detector assemblies are different from reactor to reactor. Therefore, from the nature of this project, it should be noted here that the target model of the prototypical farbrication of an in-core neutron flux monitor detector assembly is a VFD-2 System for Wolsung CANDU. It is concluded that fabrication of in-core neutron flux monitor detector assembly for CANDU reactor is technically feasible and will bring economical benefit as much as 50 % of the unit price if they are fabricated in Korea by using partially materials which are available from local market. (author)

  11. Data support system for controlling decentralised nuclear power industry facilities through uninterruptible condition monitoring

    Directory of Open Access Journals (Sweden)

    Povarov Vladimir

    2018-01-01

    Full Text Available The article describes the automated uninterruptible multi-parameter system for monitoring operational vulnerability of critical NPP components, which differs from existing ones by being universally applicable for analysing mechanical damage of nuclear power unit components. The system allows for performing routine assessment of metal structures. The assessment of strained condition of a deteriorating component is based on three-dimensional finite element simulation with calculations adjusted with reference to in-situ measurements. A program for calculation and experimental analysis of maximum load and durability of critical area forms the core of uninterruptible monitoring system. The knowledge base on performance of the monitored components in different operating conditions and the corresponding comprehensive analysis of strained condition and deterioration rates compose the basis of control system data support, both for operating nuclear power units and robotic maintenance and repair systems.

  12. A Review of the Condition Monitoring of Capacitors in Power Electronic Converters

    DEFF Research Database (Denmark)

    Soliman, Hammam Abdelaal Hammam; Wang, Huai; Blaabjerg, Frede

    2015-01-01

    Capacitor is one of the reliability critical components in power electronic systems. In the last two decades, many efforts in the academic research have been devoted to the condition monitoring of capacitors to estimate their health status. Industry applications demand more reliable power...... electronics products with preventive maintenance. Nevertheless, most of the developed capacitor condition monitoring technologies are rarely adopted by industry due to the complexity, increased cost and other relevant issues. An overview of the prior-art research in this area is therefore needed to justify....... Therefore, this paper firstly classifies the capacitor condition monitoring methods into three categories, then the respective technology evolution from 1993 to 2015 is summarized. Remarks on the state-of-the-art research and the future opportunities targeting for practical industry applications are given....

  13. A Review of the Condition Monitoring of Capacitors in Power Electronic Converters

    DEFF Research Database (Denmark)

    Soliman, Hammam Abdelaal Hammam; Wang, Huai; Blaabjerg, Frede

    2016-01-01

    Capacitors are one type of reliability-critical components in power electronic systems. In the last two decades, many efforts in academic research have been devoted to the condition monitoring of capacitors to estimate their health status. Industry applications are demanding more reliable power...... electronics products with preventive maintenance. Nevertheless, most of the developed capacitor condition monitoring technologies are rarely adopted by industry due to the complexity, increased cost, and other relevant issues. An overview of the prior-art research in this area is therefore needed to justify......, this paper first classifies the capacitor condition monitoring methods into three categories, then the respective technology evolution in the last two decades is summarized. Finally, the state-of-the-art research and the future opportunities targeting for industry applications are given....

  14. Thermo-power in Brazil: diagnosis of control and monitoring of gas emissions

    International Nuclear Information System (INIS)

    Xavier, E.E.; Magrini, Alessandra; Rosa, L.P.; Santos, M.A. dos

    2004-01-01

    In parallel to Brazil's recent supply crisis, the privatization process of its power sector has drastically reshaped the nation's energy matrix. From a profile based mainly on hydro-power generation, this sector is being reshaped through a thermo-power plant construction program whose environmental repercussions will certainly be felt over the next few years. This paper offers a description of the thermo-power segment currently in operation, under construction and on the drawing board in Brazil, followed by the results of a diagnosis of the control and monitoring of the gas emissions by this segment. The methodology used for the exploratory analysis and to prepare the diagnosis consists of surveys through questionnaires completed by companies owning the thermo-power plants. After consolidating, processing and analyzing the findings reached through the replies sent in by the companies, it is concluded that thermo-power plants currently in operation lack control systems that would help reduce atmospheric pollution, and are not equipped with monitoring systems for these emissions. The thermo-power plants currently under construction and on the drawing board indicate a trend towards including these systems in their project designs, due to more stringent licensing processes

  15. Distributed applications monitoring at system and network level

    CERN Document Server

    Aderholz, Michael; Augé, E; Bagliesi, G; Banistoni, G; Barone, L; Boschini, M; Brunengo, A; Bunn, J J; Butler, J; Campanella, M; Capiluppi, P; D'Amato, M; Darneri, M; Di Mattia, A; Dorokhov, A E; Gagliardi, F; Gaines, I; Gasparini, U; Ghiselli, A; Gordon, J; Grandi, C; Gálvez, P; Harris, F; Holtman, K; Karimäki, V; Karita, Y; Klem, J T; Legrand, I; Leltchouk, M; Linglin, D; Lubrano, P; Luminari, L; McArthur, I C; Michelotto, M; Morita, Y; Nazarenko, A; Newman, H; O'Dell, Vivian; O'Neale, S W; Osculati, B; Pepé, M; Perini, L; Pinfold, James L; Pordes, R; Prelz, F; Putzer, A; Resconi, S; Robertson, L; Rolli, S; Sasaki, T; Sato, H; Schaffer, R D; Schalk, T L; Servoli, L; Sgaravatto, M; Shiers, J; Silvestris, L; Siroli, G P; Sliwa, K; Smith, T; Somigliana, R; Stanescu, C; Stockinger, H E; Ugolotti, D; Valente, E; Vistoli, C; Wilkinson, R P; Willers, Ian Malcolm; Williams, D O

    2001-01-01

    Most distributed applications are based on architectural models that do not involve real-time knowledge of network status and of their network usage. Moreover the new "network aware" architectures are still under development and their design is not yet complete. We considered, as a use case, an application using ODBMS (Objectivity /DB) for the distributed analysis of experimental data. The dynamic usage of system and network resources at host and application levels has been measured in different client/server configurations, and on several LAN and WAN layouts. The aim was to study the application efficiency and behavior versus the network characteristics and conditions. The most interesting results of the LAN and WAN tests are described. System bottlenecks and limitations have been identified, and efficient working conditions in the different scenarios have been defined. The behavior observed when moving away from the optimal working conditions is also described.

  16. An energy-harvesting power supply for underwater bridge scour monitoring sensors

    Science.gov (United States)

    Wang, Yuli; Li, Yingjie; He, Longzhuang; Shamsi, Pourya; Zheng, Yahong R.

    2018-03-01

    The natural force of scouring has become one of the most critical risk endangering the endurance of bridges, thus leading to the necessity of deploying underwater monitoring sensors to actively detect potential scour holes under bridges. Due to the difficulty in re-charging batteries for underwater sensors, super capacitors with energy harvesting (EH) means are exploited to prolong the sustainability of underwater sensors. In this paper, an energy harvesting power supply based on a helical turbine is proposed to power underwater monitoring sensors. A small helical turbine is designed to convert water flow energy to electrical energy with favorable environmental robustness. A 3-inch diameter, 2.5-inch length and 3-bladed helical turbine was designed with two types of waterproof coupling with the sensor housing. Both designs were prototyped and tested under different flow conditions and we get valid voltage around 0.91 V which is enough to power monitoring sensor. The alternating current (AC) electrical energy generated by the helical turbine is then rectified and boosted to drive a DC charger for efficiently charging one super capacitor. The charging circuit was designed, prototyped and tested thoroughly with the helical turbine harvester. The results were promising, that the overall power supply can power an underwater sensor node with wireless transceivers for long-term operations

  17. Power Balance AODV Routing Algorithm of WSN in Precision Agriculture Environment Monitoring

    Directory of Open Access Journals (Sweden)

    Xiaoqin Qin

    2013-11-01

    Full Text Available As one of important technologies of IOT (Internet of Things, WSN (Wireless Sensor Networks has been widely used in precision agriculture environment monitoring. WSN is a kind of energy-constrained network, but power balance is not taken into account in traditional routing protocols. A novel routing algorithm, named Power Balance Ad hoc On-Demand Distance Vector (PB-AODV, is proposed on cross-layer design. In the route discovery process of PB-AODV, routing path is established by the Received Signal Strength Indication (RSSI value. The optimal transmitting power, which is computed according to RSSI value, power threshold and node’s surplus energy, is encapsulated into Route Reply Packet. Hence, the sender node can adjust its transmission power to save energy according to the Route Reply Packet. Simulation results show that the proposed algorithm is effective for load balancing, and increases the WSN’s lifetime 14.3% consequently.

  18. Monitoring systems online of oil for transformers of nuclear power plants

    International Nuclear Information System (INIS)

    Sarandeses, S.

    2014-01-01

    The nuclear power plants are showing their concern due to the existence of recent failures related to the bulky transformers of power. These transformers are not security, but are important for the production of power as its failure can cause transient on the floor, reactor scram or shooting, that can cause interruptions in the production of energy or might force us to reduce the power of production The analysis of gases dissolved in transformer oil is recognized as a trial key to identify a submerged transformer failure in oil. With this analysis it is not possible to ensure that there is no damage in the transformer, but the probability of risk of this type of failure can be reduced. The industry recommended to equip the new large power transformers with oil online monitoring systems and in some cases also be It recommended its use in existing transformers. (Author)

  19. Operation status display and monitoring system for BWR nuclear power plant

    International Nuclear Information System (INIS)

    Wakabayashi, Yasuo; Hayakawa, Hiroyasu; Kawamura, Atsuo; Kaneda, Mitsunori.

    1982-01-01

    Lately, the development of the system has been made for BWR plants, which monitors the operating status not only in normal operation but also in abnormal state and also for plant safety. Recently, the improvement of man-machine interface has been tried through the practical use of technique which displays data collectively on a CRT screen relating them mutually. As one of those results, the practical use of an electronic computer and color CRT display for No. 1 unit in the Fukushima No. 2 Nuclear Power Station (2F-1), Tokyo Electric Power Co., is described. Also, new centralized control panels containing such systems were used for the 1100 MWe BWR nuclear power plants now under construction, No. 3 unit of the Fukushima No. 2 Power Station and No. 1 unit of Kashiwazaki-Kariwa Nuclear Power Station (2F-3 and K-1, respectively). The display and monitoring system in 2F-1 plant is the first one in which a computer and color CRTs were practically employed for a BWR plant in Japan, and already in commercial operation. The advanced operating status monitoring system, to which the result of evaluation of the above system was added, was incorporated in the new centralized control panels presently under production for 2F-3 and K-1 plants. The outline of the system, the functions of an electronic computer, plant operating status monitor, surveillance test guide, the automation of plant operation and auxiliary operation guide are reported for these advanced monitoring system. It was confirmed that these systems are useful means to improve the man-machine communication for plant operation minitoring. (Wakatsuki, Y.)

  20. Concept of a new method for fatigue monitoring of nuclear power plant components

    International Nuclear Information System (INIS)

    Zafosnik, M.; Cizelj, L.

    2007-01-01

    Fatigue is one of the well-understood aging mechanisms affecting mechanical components in many industrial facilities including nuclear power plants. Operational experience of nuclear power plants worldwide to date confirmed adequate design of safety related components against fatigue. In some cases however, for example when the plant life extension is envisioned, it may be very useful to monitor the remaining fatigue life of safety related components. Nuclear power plants components are classified into safety classes regarding their importance in mitigating the consequences of hypothetic accidents. Service life of components subjected to fatigue loading can be estimated with Usage Factor uk. A concept of the new method aiming both at monitoring the current state of the component and predicting its remaining lifetime in the life-extension conditions is presented. The method is based on determination of partial Usage Factor of components in which operating transients will be considered and compared to design transients. (author)

  1. Monitoring and operational support on nuclear power plants using an artificial intelligence system

    International Nuclear Information System (INIS)

    Bianchi, P.H.; Baptista Filho, B.D.

    2009-01-01

    The monitoring task in nuclear power plants is of crucial importance with respect to safety and efficient operation. The operators have a wide range of variables to observe and analyze; the quantity of variables and their behavior determine the time they have to take correct decisions. The complexity of such aspects in a nuclear power plant influences both, the plant operational efficiency and the general safety issues. This paper describes an experimental system developed by the authors which aims to assist the operators of nuclear power plants to take quick and safe decisions. The system maps the status of plant and helps the operators to make quick judgments by using artificial intelligence methods. The method makes use of a small set of monitored variables and presents a map of the plant status in a friendly manner. This system uses an architecture that has multiple self-organizing maps to perform these tasks. (author)

  2. Monitoring and operational support on nuclear power plants using an artificial intelligence system

    Energy Technology Data Exchange (ETDEWEB)

    Bianchi, Paulo H.; Baptista Filho, Benedito D., E-mail: phbianchi@gmail.co, E-mail: bdbfilho@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2009-07-01

    The monitoring task in nuclear power plants is of crucial importance with respect to safety and efficient operation. The operators have a wide range of variables to observe and analyze; the quantity of variables and their behavior determine the time they have to take correct decisions. The complexity of such aspects in a nuclear power plant influences both, the plant operational efficiency and the general safety issues. This paper describes an experimental system developed by the authors which aims to assist the operators of nuclear power plants to take quick and safe decisions. The system maps the status of plant and helps the operators to make quick judgments by using artificial intelligence methods. The method makes use of a small set of monitored variables and presents a map of the plant status in a friendly manner. This system uses an architecture that has multiple self-organizing maps to perform these tasks. (author)

  3. Monitoring of radionuclides in the environs of the Finnish nuclear power stations in 1988

    International Nuclear Information System (INIS)

    Klemola, S.; Ilus, E.; Sjoeblom, K.L.; Arvela, H.; Blomqvist, L.

    1991-03-01

    Monitoring of radionuclides around Finnish nuclear power plants continued in 1988 with the regular programmes. About 1000 samples were analysed from both terrestrial and aquatic environments.The dominant artificial radioactive substances in the vicinity of power plants were still the fallout nuclides from the Chernobyl accident, but the concentrations in all the objects monitored are lower than in the previous year. Trace amounts of activation products originating from the airborne releases of local power plants were detected in some air and deposition samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms. However, their contribution to the radiation doses received by the the public was very small. (orig.)

  4. Water levels in continuously monitored wells in the Yucca Mountain area, Nevada, 1985--88

    International Nuclear Information System (INIS)

    Luckey, R.R.; Lobmeyer, D.H.; Burkhardt, D.J.

    1993-01-01

    Water levels have been monitored hourly in 15 wells completed in 23 depth intervals in the Yucca Mountain area, Nevada. Water levels were monitored using pressure transducers and were recorded by data loggers. The pressure transducers were periodically calibrated by raising and lowering them in the wells. The water levels were normally measured at approximately the same time that the transducers were calibrated. Where the transducer output appeared reasonable, it was converted to water levels using the calibrations and manual water- level measurements. The amount of transducer output that was converted to water levels ranged from zero for several intervals to about 98 percent for one interval. Fourteen of the wells were completed in Tertiary volcanic rocks and one well was completed in Paleozoic carbonate rocks. Each well monitored from one to four depth intervals. Water-level fluctuation caused by barometric pressure changes and earth tides were observed

  5. A METHOD OF COMPLEX AUTOMATED MONITORING OF UKRAINIAN POWER ENERGY SYSTEM OBJECTS TO INCREASE ITS OPERATION SAFETY

    Directory of Open Access Journals (Sweden)

    Ye.I. Sokol

    2016-05-01

    Full Text Available The paper describes an algorithm of the complex automated monitoring of Ukraine’s power energy system, aimed at ensuring safety of its personnel and equipment. This monitoring involves usage of unmanned aerial vehicles (UAVs for planned and unplanned registration status of power transmission lines (PTL and high-voltage substations (HVS. It is assumed that unscheduled overflights will be made in emergency situations on power lines. With the help of the UAV, pictures of transmission and HVS will be recorded from the air in the optical and infrared ranges, as well as strength of electric (EF and magnetic (MF fields will be measured along the route of flight. Usage specially developed software allows to compare the recorded pictures with pre-UAV etalon patterns corresponding to normal operation of investigated transmission lines and the HVSs. Such reference pattern together with the experimentally obtained maps of HVS’s protective grounding will be summarized in a single document – a passport of HVS and PTL. This passport must also contain the measured and calculated values of strength levels of EF and MF in the places where staff of power facilities stay as well as layout of equipment, the most vulnerable to the effects of electromagnetic interference. If necessary, as part of ongoing monitoring, recommendations will be given on the design and location of electromagnetic screens, reducing the levels of electromagnetic interference as well as on location of lightning rods, reducing probability lightning attachment to the objects. The paper presents analytic expressions, which formed the basis of the developed software for calculation of the EF strength in the vicinity of power lines. This software will be used as a base at UAV navigation along the transmission lines, as well as to detect violations in the transmission lines operation. Comparison of distributions of EF strength calculated with the help of the elaborated software with the known

  6. Architecture and design of third Qinshan nuclear power plant risk monitor

    Energy Technology Data Exchange (ETDEWEB)

    Wang, F.; Li, Y.; Wang, J.; Wang, J.; Hu, L. [Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); School of Nuclear Science and Technology, Univ. of Science and Technology of China, No.350 Shushanhu Road, Shushan District, Hefei, Anhui, 230031 (China)

    2012-07-01

    Risk monitor is a real-time analysis tool to determine the point-in-time risk based on actual plant configuration, which is an important application of PSA (Probabilistic Safety Assessment). In this study the status and development trend of risk monitor were investigated and a risk monitor named TQRM (Third Qinshan nuclear power plant Risk Monitor) was developed. The B/S architecture and the two key computing methods pre-solved and resolving PSA model method adopted in TQRM were introduced. The functions and technical features were also presented. Now TQRM has been on-line for more than one year and used in the operation and maintenance of TQNPP. The experience demonstrates that TQRM's results are accurate and real-time, the architecture is stable, and it could be extended and maintained conveniently for any other Risk-Informed Application. (authors)

  7. 15. Internal symposium on recent progress of nondestructive inspection and monitoring technologies for nuclear power plants

    International Nuclear Information System (INIS)

    1994-01-01

    At the symposium, lectures were given on the recent development of the nondestructive inspection technology for nuclear power plants, the trend regarding the nondestructive inspection in foreign countries (Japan-Germany atomic energy seminar), the present state and subjects of the monitoring technology in BWR plants, the present state and subjects of the monitoring technology in PWR plants, and the present state and the subjects for hereafter of the defect evaluation method in the equipment of light water reactors. The data on the ultrasonic flaw detection in aluminum alloy welded joints were obtained. The German inspection technology is similar to that in Japan and other countries. The research on the plant synthetic monitoring and diagnosis system is reported. The monitoring systems for abnormal state in operation, troubles and the secular change of equipment are reported. The evaluation of the flaws in nuclear piping is reported. The summaries of the lectures are collected in this book. (K.I.)

  8. A Study of KHNP Nuclear Power Plant Technology Level Evaluation

    International Nuclear Information System (INIS)

    Yang, Seung Han; Lee, Sung Jin; Kim, Yo Han

    2016-01-01

    KHNP's 2030 mid and long term plan goal in technology field is securing global No. 1 NPP technology level. Quantifying technology level for this purpose, technology level at present should be surveyed. Technology level of South Korea has been surveyed by KISTEP (Korea Institute of S and T Evaluation and Planning) every two year but the technology level of KHNP has not been surveyed by any organization including KHNP itself. Also the size of technology surveyed by KISTEP was too broad to quantifying technology level of KHNP. In this paper, technology level of KHNP and South Korea are presented. In this study, NPP related technologies were divided into Level I and Level II technologies and conducted a survey for each Level II technologies using Delphi questionnaire survey that is widely used in technology level evaluation. The results of technology level and gap will be used from strategic point of view and also as a reference data for technology improvement planning

  9. A Study of KHNP Nuclear Power Plant Technology Level Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Seung Han; Lee, Sung Jin; Kim, Yo Han [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    KHNP's 2030 mid and long term plan goal in technology field is securing global No. 1 NPP technology level. Quantifying technology level for this purpose, technology level at present should be surveyed. Technology level of South Korea has been surveyed by KISTEP (Korea Institute of S and T Evaluation and Planning) every two year but the technology level of KHNP has not been surveyed by any organization including KHNP itself. Also the size of technology surveyed by KISTEP was too broad to quantifying technology level of KHNP. In this paper, technology level of KHNP and South Korea are presented. In this study, NPP related technologies were divided into Level I and Level II technologies and conducted a survey for each Level II technologies using Delphi questionnaire survey that is widely used in technology level evaluation. The results of technology level and gap will be used from strategic point of view and also as a reference data for technology improvement planning.

  10. Use of self-powered detectors of near containment gamma monitoring

    International Nuclear Information System (INIS)

    Kemp, J.; LaFontaine, M.; Sharma, H.

    2001-01-01

    A study was conducted during the period April to May 1988, to select a self-powered detector (SPD) with an appropriate emitter for measuring the gamma radiation dose rate in near-containment. The selected SPD would be used in the containment monitoring systems for the Ringhals and Forsmark reactors in Sweden. In-containment gamma radiation (81 keV to ∼3 MeV energy range) could result from the release of gaseous fission-product nuclides of bromine, krypton, iodine and xenon. Associated dose rates can range from 10 to 10 6 Gy/h. Tests were performed on platinum and vanadium emitter SPDs 1 using 60 Co, 192 Ir and X-ray gamma/photon sources. A gamma energy dependent polarity change in the signal from the Pt SPD (signal goes from positive to negative as energy drops below 100 keV), coupled with a non-linear response, eliminated that design from further study in this application. The vanadium SPDs produced a linear, negative signal irrespective of the impingent gamma energy level. The gamma sensitivity of the 18 V SPDs tested in the program, ranged from -1.07 x 10 -14 A/Gy/h to -1.87 x 10 -14 A/Gy/h per metre emitter length. (author)

  11. Feminized Power and Adversarial Advocacy: Levelling Arguments or Analyzing Them?

    Science.gov (United States)

    Condit, Celeste Michelle

    1989-01-01

    Examines the journalistic analysis of the 1988 Presidential Debates from a feminist perspective in order to identify the revisions needed in the debate process. Provides historical background of feminized power and adversarial advocacy. (MM)

  12. Determination of the intensity of a power jump session by means of heart rate monitoring

    Directory of Open Access Journals (Sweden)

    Talita Grossl

    2008-07-01

    Full Text Available http://dx.doi.org/10.5007/1980-0037.2008v10n2p129 A Power Jump (PJ session is considered to be a safe and easy class that also involves intermittent exercises that prolong the time to exhaustion. However, there is not enough information about this subject in the literature. The purpose of this study was to determine the intensity of a PJ session by means of heart rate (HR monitoring. Eleven physically active females participated in the study (age: 21.7 ± 1.9 years; body mass: 59.3 ± 4.8 kg; height: 162.6 ± 5.6 cm; percentage body fat: 22.6 ± 3.2 %. Participants were asked to perform an incremental test (IT, in order to obtain values for oxygen uptake (VO2, maximal heart rate (HRmax, heart rate deflection point (HRDP and energy expenditure (EE. The HR of the subjects was monitored during a special type of Power Jump session called “mix nine” on two different occasions. According to the HRDP values, physiological domains could be divided into three exercise intensity classes: moderate, heavy and severe. Descriptive statistics were adopted (mean ± SD. Student’s t test was used to compare HR and EE between PJ1 and PJ2. For comparisons between domains, two-way ANOVA and the Scheffé test were used. The level of significance was set at p<0.05. Mean HRmax obtained during the IT was 195±10bpm. The velocities, HR and %HRmax corresponding to HRDP and 80% of HRDP were 10.1±0.95km.h-1, 178±7bpm and 91.7±4.0%; and 8.1±0.76km.h-1, 143±5bpm and 73.4±3.2%, respectively. Values for HRmean and EE were significantly different when PJ1 (161±11bpm, 386±58.2kcal and PJ2 (156±10bpm, 355.1±53.8kcal were compared. The times spent in each exercise intensity domain were: heavy 51±14.5%; severe 27±19.7% and moderate 23±8.7%. These results show that the subjects spent most of the time in the heavy exercise domain which, in turn, appears to be the most indicated for improving aerobic capacity.

  13. The fault monitoring and diagnosis knowledge-based system for space power systems: AMPERES, phase 1

    Science.gov (United States)

    Lee, S. C.

    1989-01-01

    The objective is to develop a real time fault monitoring and diagnosis knowledge-based system (KBS) for space power systems which can save costly operational manpower and can achieve more reliable space power system operation. The proposed KBS was developed using the Autonomously Managed Power System (AMPS) test facility currently installed at NASA Marshall Space Flight Center (MSFC), but the basic approach taken for this project could be applicable for other space power systems. The proposed KBS is entitled Autonomously Managed Power-System Extendible Real-time Expert System (AMPERES). In Phase 1 the emphasis was put on the design of the overall KBS, the identification of the basic research required, the initial performance of the research, and the development of a prototype KBS. In Phase 2, emphasis is put on the completion of the research initiated in Phase 1, and the enhancement of the prototype KBS developed in Phase 1. This enhancement is intended to achieve a working real time KBS incorporated with the NASA space power system test facilities. Three major research areas were identified and progress was made in each area. These areas are real time data acquisition and its supporting data structure; sensor value validations; development of inference scheme for effective fault monitoring and diagnosis, and its supporting knowledge representation scheme.

  14. Nuclear steam power plant cycle performance calculations supported by power plant monitoring and results computer

    International Nuclear Information System (INIS)

    Bettes, R.S.

    1984-01-01

    The paper discusses the real time performance calculations for the turbine cycle and reactor and steam generators of a nuclear power plant. Program accepts plant measurements and calculates performance and efficiency of each part of the cycle: reactor and steam generators, turbines, feedwater heaters, condenser, circulating water system, feed pump turbines, cooling towers. Presently, the calculations involve: 500 inputs, 2400 separate calculations, 500 steam properties subroutine calls, 200 support function accesses, 1500 output valves. The program operates in a real time system at regular intervals

  15. Empirical LTE Smartphone Power Model with DRX Operation for System Level Simulations

    DEFF Research Database (Denmark)

    Lauridsen, Mads; Noël, Laurent; Mogensen, Preben

    2013-01-01

    An LTE smartphone power model is presented to enable academia and industry to evaluate users’ battery life on system level. The model is based on empirical measurements on a smartphone using a second generation LTE chipset, and the model includes functions of receive and transmit data rates...... and power levels. The first comprehensive Discontinuous Reception (DRX) power consumption measurements are reported together with cell bandwidth, screen and CPU power consumption. The transmit power level and to some extent the receive data rate constitute the overall power consumption, while DRX proves...

  16. Power Grid Construction Project Portfolio Optimization Based on Bi-level programming model

    Science.gov (United States)

    Zhao, Erdong; Li, Shangqi

    2017-08-01

    As the main body of power grid operation, county-level power supply enterprises undertake an important emission to guarantee the security of power grid operation and safeguard social power using order. The optimization of grid construction projects has been a key issue of power supply capacity and service level of grid enterprises. According to the actual situation of power grid construction project optimization of county-level power enterprises, on the basis of qualitative analysis of the projects, this paper builds a Bi-level programming model based on quantitative analysis. The upper layer of the model is the target restriction of the optimal portfolio; the lower layer of the model is enterprises’ financial restrictions on the size of the enterprise project portfolio. Finally, using a real example to illustrate operation proceeding and the optimization result of the model. Through qualitative analysis and quantitative analysis, the bi-level programming model improves the accuracy and normative standardization of power grid enterprises projects.

  17. Air-Flow-Driven Triboelectric Nanogenerators for Self-Powered Real-Time Respiratory Monitoring.

    Science.gov (United States)

    Wang, Meng; Zhang, Jiahao; Tang, Yingjie; Li, Jun; Zhang, Baosen; Liang, Erjun; Mao, Yanchao; Wang, Xudong

    2018-06-04

    Respiration is one of the most important vital signs of humans, and respiratory monitoring plays an important role in physical health management. A low-cost and convenient real-time respiratory monitoring system is extremely desirable. In this work, we demonstrated an air-flow-driven triboelectric nanogenerator (TENG) for self-powered real-time respiratory monitoring by converting mechanical energy of human respiration into electric output signals. The operation of the TENG was based on the air-flow-driven vibration of a flexible nanostructured polytetrafluoroethylene (n-PTFE) thin film in an acrylic tube. This TENG can generate distinct real-time electric signals when exposed to the air flow from different breath behaviors. It was also found that the accumulative charge transferred in breath sensing corresponds well to the total volume of air exchanged during the respiration process. Based on this TENG device, an intelligent wireless respiratory monitoring and alert system was further developed, which used the TENG signal to directly trigger a wireless alarm or dial a cell phone to provide timely alerts in response to breath behavior changes. This research offers a promising solution for developing self-powered real-time respiratory monitoring devices.

  18. A methodology for on-line fatigue life monitoring of Indian nuclear power plant components

    International Nuclear Information System (INIS)

    Mukhopadhyay, N.K.; Dutta, B.K.; Kushawaha, H.S.

    1992-01-01

    Fatigue is one of the most important aging effects of nuclear power plant components. Information about accumulation of fatigue helps in assessing structural degradation of the components. This assists in-service inspection and maintenance and may also support future life extension program of a plant. In the present report a methodology is being proposed for monitoring on line fatigue life of nuclear power plant components using available plant instrumentations. Major factors affecting fatigue life of a nuclear power plant components are the fluctuations of temperature, pressure and flow rate. Green's function technique is used in on line fatigue monitoring as computation time is much less than finite element method. A code has been developed which computes temperature and stress Green's functions in 2-D and axisymmetric structure by finite element method due to unit change in various fluid parameters. A post processor has also been developed which computes the temperature and stress responses using corresponding Green's functions and actual fluctuation in fluid parameters. In this post processor, the multiple site problem is solved by superimposing single site Green's function technique. It is also shown that Green's function technique is best suited for on line fatigue life monitoring of nuclear power plant components. (author). 6 refs., 43 figs

  19. Level 1 shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

    International Nuclear Information System (INIS)

    Halada, P.; Cillik, I.; Stojka, T.; Kuzma, M.; Prochaska, J.; Vrtik, L.

    2004-01-01

    The paper presents general approach, used methods and form of documentation of the results that have been applied within the shutdown and low power PSA (SPSA) study for Mochovce NPP, Unit 1, Slovakia. The SPSA project was realized by VUJE Trnava Inc., Slovakia in 2001-2002 years. The Level 1 SPSA study for Mochovce NPP Unit 1 covers internal events as well as internal (fires, floods and heavy load drop) and external (aircraft crash, extreme meteorological conditions, seismic event and influence of surrounding industry) hazards. Mochovce NPP consists of two operating units equipped with VVER 440/V213 reactors safety upgraded before construction finishing and operation start. 87 safety measures based on VVER 440 operational experience and international mission insights were implemented to enhance its operational and nuclear safety. The SPSA relates to full power PSA (FPSA) as a continuation of the effort to create a harmonized level 1 PSA model for all operational modes of the plant with the goal to use it for further purposes as follows: Real Time Risk Monitor, Maintenance Optimization, Technical Specifications Optimization, Living PSA. (author)

  20. BEST-4, Fuel Cycle and Cost Optimization for Discrete Power Levels

    International Nuclear Information System (INIS)

    1973-01-01

    1 - Nature of physical problem solved: Determination of optimal power strategy for a fuel cycle, for discrete power levels and n temporal stages, taking into account replacement energy costs and de-rating. 2 - Method of solution: Dynamic programming. 3 - Restrictions on the complexity of the problem: Restrictions may arise from number of power levels and temporal stages, due to machine limitations

  1. Monitoring and studies of environmental cumulative dose of Guangdong Da Ya Bay nuclear-power station by thermoluminescent dosimetry

    International Nuclear Information System (INIS)

    Wan Yusong; Li Shili; Yang Lin; Feng Zhanglin; Kong Lingfeng; Yu Jinglan

    1999-01-01

    The author presents the environmental γ radiation routine monitoring by TLD in Guangdong Da Ya Bay Nuclear Power Station and its peripheral 50 km area, which has been put into commercial operation since 1994. The year's monitoring result indicates that there is no obvious change of the total environmental γ radiation in Da Ya Bay Nuclear Power Station and its peripheral 50 km area. But the influence of gas release γ radiation was monitored in 1995 at the monitoring points in the area of 0∼1 km from the nuclear power station

  2. Aquatic indicator organisms as a tool to monitor discharges from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Outola, Iisa; Vartti, Vesa-Pekka; Klemola, Seppo [STUK - Radiation and Nuclear Safety Authority, P.O. Box 14, 00881 Helsinki (Finland)

    2014-07-01

    There are four operating nuclear power plant units in Finland at two separate locations. The units started operation during 1977-1980. The surveillance of radioactive substances in the vicinities of the nuclear power plant is carried out under the permanent monitoring programs. Some 1000 samples are taken annually from the surroundings of the power plants to confirm that the discharges from the power plants are within permissible release limits and to monitor the dispersion of discharges in the environment. Aquatic indicator organisms (macro-algae, periphyton, mussels, crustacean, submerged aquatic plants) are included in the monitoring program. The indicator organisms are valuable monitoring objects both in normal and emergency situations because they accumulate effectively and often very rapidly radioactive substances from the medium. Six different species (Periphyton, Fucus vesiculosus, Myriophyllum spicatum, Potamogeton pectinatus, Saduria entomon, Macoma Baltica/Mytilus edulis) are collected regularly. Number of sampling location for each species varies from 1 to 7. Some species are collected continuously, some 1-2 times in a year. In this study we have evaluated the monitoring results for the aquatic indicator organisms for the period of 2005-2010 concerning concentration of discharge nuclides. Our aim was to answer the following questions using the monitoring data from aquatic organisms: 1) Which radionuclides are released to the marine environment and how often do we detect them? 2) How far from the nuclear power plants discharge radionuclides are detected? 3) How concentration of discharge radionuclides has changed with time in aquatic organisms? The number of discharge nuclides detected in the aquatic indicator samples was 11. Most of them were only detected in few samples, but {sup 58}Co, {sup 60}Co, {sup 54}Mn and {sup 110m}Ag were detected more frequently. Most of the observations above detection limits were made within the 5 km distance from the

  3. Real time power consumption monitoring for energy efficiency analysis in micro EDM milling

    DEFF Research Database (Denmark)

    Tristo, Gianluca; Bissacco, Giuliano; Lebar, Andrej

    2015-01-01

    for manufacturing sustainability. Electrical discharge machining (EDM) is considered an attractive solution for the manufacturing of microcomponents. In this paper, a low cost and modular data acquisition system, based on open-hardware and open-source software, for online energy consumption monitoring, is presented......Sustainability has become a major concern in many countries and is leading to strict regulations regarding the impact of products and services during their manufacturing, use, and disposal. Power consumption monitoring in manufacturing companies can lead to a reduction of machine tools energy...

  4. Increasing the Performance and Reliability of Power Boiler by Monitoring Thermal and Strength Parameters

    Directory of Open Access Journals (Sweden)

    Sobota Tomasz

    2017-01-01

    Full Text Available The paper presents a method for determination of thermo-flow parameters for steam boilers. This method allows to perform the calculations of the boiler furnace chamber and heat flow rates absorbed by superheater stages. These parameters are important for monitoring the performance of the power unit. Knowledge of these parameters allows determining the degree of the furnace chamber slagging. The calculation can be performed in online mode and use to monitoring of steam boiler. The presented method allows to the operation of steam boiler with high efficiency.

  5. A contribution to thermoluminescence dosemeter system optimisation applied to environmental monitoring around nuclear power plants

    International Nuclear Information System (INIS)

    Dies, X.; Ortega, X.; Rosell, J.

    1990-01-01

    The factors that constitute a thermoluminescence dosimetric system have been studied and optimised, with the intention of defining strategies for improving precision and accuracy of TL dosimetry systems for environmental monitoring. An optimisation technique based on fractional factorial designs permitted a reduction in the number of necessary experiments and clarified interactions between various factors. The model for fading over time showed that TL response in LiF:Mg,Ti dosemeters was independent of time between irradiation and readout, and this was applied to fading corrections in nuclear power plant environmental monitoring. (author)

  6. An Internet of Things Approach to Electrical Power Monitoring and Outage Reporting

    Energy Technology Data Exchange (ETDEWEB)

    Koch, Daniel B [ORNL

    2017-01-01

    The so-called Internet of Things concept has captured much attention recently as ordinary devices are connected to the Internet for monitoring and control purposes. One enabling technology is the proliferation of low-cost, single board computers with built-in network interfaces. Some of these are capable of hosting full-fledged operating systems that provide rich programming environments. Taken together, these features enable inexpensive solutions for even traditional tasks such as the one presented here for electrical power monitoring and outage reporting.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

  8. Blind test results - measure of incessant progress in personnel monitoring services at Kudankulam Nuclear Power Project

    International Nuclear Information System (INIS)

    Jashi, K.B.; Ashok Kumar, A.; Pandaram, P.

    2018-01-01

    Personnel Monitoring Services (PMS) at Thermoluminescent Dosimeter (TLD) laboratory, Kudankulam Nuclear Power Project (KKNPP) involve monitoring of about 1500 radiation workers of KKNPP for external radiation exposure on monthly basis. Quality assurance in PMS provides an overall estimate of accuracy which depends not only upon the dosimeter quality and reader performance but also on data interpretation, applicable software and the system. Therefore it measures the effectiveness of quality control mechanism. Blind test is an effective tool to check the performance of the processor without their knowledge during routine processing of the service cards

  9. Applications of neural networks to monitoring and decision making in the operation of nuclear power plants

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1990-01-01

    Application of neural networks to monitoring and decision making in the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: (1) diagnosing specific abnormal conditions or problems in nuclear power plants, (2) detection of the change of mode of operation of the plant, (3) validating signals coming from detectors, (4) review of ''noise'' data from TVA's Sequoyah Nuclear Power Plant, and (5) examination of the NRC's database of ''Letter Event Reports'' for correlation of sequences of events in the reported incidents. Each of these projects and its status are described briefly in this paper. This broad based program has as its objective the definition of the state-of-the-art in using neural networks to enhance the performance of commercial nuclear power plants

  10. A New Remote Monitoring System Application in Laser Power Based on LabVIEW

    Directory of Open Access Journals (Sweden)

    Liu Gaoqiang

    2016-01-01

    Full Text Available In this paper, a new remote monitoring system based on LabVIEW was proposed to measure laser power automatically and remotely. This system consists of four basic components: an DH-JG2 optical power meter, a NI-USB 6008 data acquisition card, a personal computer (PC, and HP laserJet 1020 Plus printer. Since power output of laser is generally so unstable that abnormal work situation could not retroaction to inspectors right away, new system was designed to solve this problem. The detection system realized function of remote control by TCP protocol and mobile phone. Laser power curve that is measured by detection system demonstrated that the design has a good performance in real-time detection and operability.

  11. Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1993 and 1994

    Energy Technology Data Exchange (ETDEWEB)

    Klemola, S.; Ilus, E.; Ikaeheimonen, T.K

    1998-08-01

    Monitoring of radioactive substances around Finnish nuclear power plants continued in 1993-1994 in accordance with the regular programmes. Some 1000 samples are analysed annually from the terrestrial and aquatic environments of the two power plant sites. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air, deposition and soil samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments. However, the concentrations were so low that they did not significantly increase the radiation burden in the environment. The dominant artificial radionuclides in the vicinity of the power plants remained the cesium isotopes, especially {sup 137}Cs but also {sup 134}Cs, originating from the Chernobyl accident. (orig.) 14 refs.

  12. Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1993 and 1994

    International Nuclear Information System (INIS)

    Klemola, S.; Ilus, E.; Ikaeheimonen, T.K.

    1998-08-01

    Monitoring of radioactive substances around Finnish nuclear power plants continued in 1993-1994 in accordance with the regular programmes. Some 1000 samples are analysed annually from the terrestrial and aquatic environments of the two power plant sites. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air, deposition and soil samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments. However, the concentrations were so low that they did not significantly increase the radiation burden in the environment. The dominant artificial radionuclides in the vicinity of the power plants remained the cesium isotopes, especially 137 Cs but also 134 Cs, originating from the Chernobyl accident. (orig.)

  13. Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1991-1992

    Energy Technology Data Exchange (ETDEWEB)

    Ikaeheimonen, T.K.; Klemola, S.; Ilus, E.; Sjoeblom, K.-L.

    1995-06-01

    Surveillance of radioactive substances around Finnish nuclear power plants continued in 1991-1992 according to regular monitoring programmes, in which about 1000 samples were analysed annually from terrestrial and aquatic environments of the two power plants. Trace amounts of activation products originating from the airborne releases of the local power plants were detected in several air, deposition and soil samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments. However, the concentrations were so low that they did not markedly increase the radiation burden in the environment. The dominant artificial radionuclides in the vicinity of the power plants remained the cesium isotopes, {sup 137}Cs and {sup 134}Cs, originating from the Chernobyl accident. (orig.) (21 figs., 40 tabs.).

  14. Online Monitoring of Concrete Structures in Nuclear Power Plants: Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Mahadevan, Sankaran [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cai, Guowei [Idaho National Lab. (INL), Idaho Falls, ID (United States); Agarwal, Vivek [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-03-01

    The existing fleet of nuclear power plants in the United States have initial operating licenses of 40 years, and many of these plants have applied for and received license extensions. As plant structures, systems, and components age, their useful life—considering both structural integrity and performance—is reduced as a result of deterioration of the materials. Assessment and management of aging concrete structures in nuclear plants require a more systematic approach than simple reliance on existing code-based design margins of safety. Structural health monitoring is required to produce actionable information regarding structural integrity that supports operational and maintenance decisions. The online monitoring of concrete structures project conducted under the Advanced Instrumentation, Information, and Control Technologies Pathway of the Light Water Reactor Sustainability program at Idaho National Laboratory is seeking to develop and demonstrate capabilities for concrete structures health monitoring. Through this research project, several national laboratories and Vanderbilt University propose to develop a framework of research activities for the health monitoring of nuclear power plant concrete structures that includes the integration of four elements—damage modeling, monitoring, data analytics, and uncertainty quantification. This report briefly discusses activities in this project during October-December, 2014. The most significant activity during this period was the organizing of a two-day workshop on research needs in online monitoring of concrete structures, hosted by Vanderbilt University in November 2014. Thirty invitees from academia, industry and government participated in the workshop. The presentations and discussions at the workshop surveyed current activities related to concrete structures deterioration modeling and monitoring, and identified the challenges, knowledge gaps, and opportunities for advancing the state of the art; these

  15. Frameworks to monitor and predict resource usage in the ATLAS High Level Trigger

    CERN Document Server

    Martin, Tim; The ATLAS collaboration

    2016-01-01

    The ATLAS High Level Trigger Farm consists of around 30,000 CPU cores which filter events at up to 100 kHz input rate. A costing framework is built into the high level trigger, this enables detailed monitoring of the system and allows for data-driven predictions to be made utilising specialist datasets. This talk will present an overview of how ATLAS collects in-situ monitoring data on both CPU usage and dataflow over the data-acquisition network during the trigger execution, and how these data are processed to yield both low level monitoring of individual selection-algorithms and high level data on the overall performance of the farm. For development and prediction purposes, ATLAS uses a special `Enhanced Bias' event selection. This mechanism will be explained along with how is used to profile expected resource usage and output event-rate of new physics selections, before they are executed on the actual high level trigger farm.

  16. Frameworks to monitor and predict rates and resource usage in the ATLAS High Level Trigger

    CERN Document Server

    AUTHOR|(INSPIRE)INSPIRE-00219969; The ATLAS collaboration

    2017-01-01

    The ATLAS High Level Trigger Farm consists of around 40,000 CPU cores which filter events at an input rate of up to 100 kHz. A costing framework is built into the high level trigger thus enabling detailed monitoring of the system and allowing for data-driven predictions to be made utilising specialist datasets. An overview is presented in to how ATLAS collects in-situ monitoring data on CPU usage during the trigger execution, and how these data are processed to yield both low level monitoring of individual selection-algorithms and high level data on the overall performance of the farm. For development and prediction purposes, ATLAS uses a special ‘Enhanced Bias’ event selection. This mechanism is explained along with how it is used to profile expected resource usage and output event rate of new physics selections, before they are executed on the actual high level trigger farm.

  17. Ethical issues in using Twitter for population-level depression monitoring: a qualitative study.

    Science.gov (United States)

    Mikal, Jude; Hurst, Samantha; Conway, Mike

    2016-04-14

    Recently, significant research effort has focused on using Twitter (and other social media) to investigate mental health at the population-level. While there has been influential work in developing ethical guidelines for Internet discussion forum-based research in public health, there is currently limited work focused on addressing ethical problems in Twitter-based public health research, and less still that considers these issues from users' own perspectives. In this work, we aim to investigate public attitudes towards utilizing public domain Twitter data for population-level mental health monitoring using a qualitative methodology. The study explores user perspectives in a series of five, 2-h focus group interviews. Following a semi-structured protocol, 26 Twitter users with and without a diagnosed history of depression discussed general Twitter use, along with privacy expectations, and ethical issues in using social media for health monitoring, with a particular focus on mental health monitoring. Transcripts were then transcribed, redacted, and coded using a constant comparative approach. While participants expressed a wide range of opinions, there was an overall trend towards a relatively positive view of using public domain Twitter data as a resource for population level mental health monitoring, provided that results are appropriately aggregated. Results are divided into five sections: (1) a profile of respondents' Twitter use patterns and use variability; (2) users' privacy expectations, including expectations regarding data reach and permanence; (3) attitudes towards social media based population-level health monitoring in general, and attitudes towards mental health monitoring in particular; (4) attitudes towards individual versus population-level health monitoring; and (5) users' own recommendations for the appropriate regulation of population-level mental health monitoring. Focus group data reveal a wide range of attitudes towards the use of public

  18. Fungal levels in houses in the Fukushima Daiichi Nuclear Power Plant evacuation zone after the Great East Japan Earthquake.

    Science.gov (United States)

    Shinohara, Naohide; Tokumura, Masahiro; Hashimoto, Kazuhiro; Asano, Katsuyoshi; Kawakami, Yuji

    2017-10-01

    Residences located within 20 km of the damaged Fukushima Daiichi Nuclear Power Plant were evacuated shortly after the Great East Japan Earthquake. The levels of airborne and surface fungi were measured in six houses in the evacuation zone in August 2012 and February 2013. Airborne fungal levels in all of the houses in the summer were higher than the environmental standard levels for residential houses published in Architectural Institute of Japan (>1000 colony-forming units [CFU]/m 3 ). In two houses whose residents rarely returned to visit, fungal levels were extremely high (>52,000 CFU/m 3 ). Although fungal levels in the winter were much lower than those in the summer, they were still higher than environmental standard levels in several houses. Indoor fungal levels were significantly inversely related to the frequency with which residents returned, but they were not correlated with the air exchange rates, temperature, humidity, or radiation levels. Cladosporium spp. and Penicillium spp. were detected in every house. Aspergillus section Circumdati (Aspergillus ochraceus group) was also detected in several houses. These fungi produced ochratoxin A and ochratoxin B, which have nephrotoxic and carcinogenic potential. The present study suggests that further monitoring of fungal levels is necessary in houses in the Fukushima Daiichi Nuclear Power Plant evacuation zone, and that some houses may require fungal disinfection. The results suggest that residents' health could be at risk owing to the high levels of airborne fungi and toxic fungi Aspergillus section Circumdati. Therefore, monitoring and decontamination/disinfection of fungi are strongly recommended before residents are allowed to return permanently to their homes. In addition, returning to home with a certain frequency and adequate ventilation are necessary during similar situations, e.g., when residents cannot stay in their homes for a long period, because fungal levels in houses in the Fukushima Daiichi

  19. Promoting health equity: WHO health inequality monitoring at global and national levels

    Directory of Open Access Journals (Sweden)

    Ahmad Reza Hosseinpoor

    2015-09-01

    Full Text Available Background: Health equity is a priority in the post-2015 sustainable development agenda and other major health initiatives. The World Health Organization (WHO has a history of promoting actions to achieve equity in health, including efforts to encourage the practice of health inequality monitoring. Health inequality monitoring systems use disaggregated data to identify disadvantaged subgroups within populations and inform equity-oriented health policies, programs, and practices. Objective: This paper provides an overview of a number of recent and current WHO initiatives related to health inequality monitoring at the global and/or national level. Design: We outline the scope, content, and intended uses/application of the following: Health Equity Monitor database and theme page; State of inequality: reproductive, maternal, newborn, and child health report; Handbook on health inequality monitoring: with a focus on low- and middle-income countries; Health inequality monitoring eLearning module; Monitoring health inequality: an essential step for achieving health equity advocacy booklet and accompanying video series; and capacity building workshops conducted in WHO Member States and Regions. Conclusions: The paper concludes by considering how the work of the WHO can be expanded upon to promote the establishment of sustainable and robust inequality monitoring systems across a variety of health topics among Member States and at the global level.

  20. Promoting health equity: WHO health inequality monitoring at global and national levels.

    Science.gov (United States)

    Hosseinpoor, Ahmad Reza; Bergen, Nicole; Schlotheuber, Anne

    2015-01-01

    Health equity is a priority in the post-2015 sustainable development agenda and other major health initiatives. The World Health Organization (WHO) has a history of promoting actions to achieve equity in health, including efforts to encourage the practice of health inequality monitoring. Health inequality monitoring systems use disaggregated data to identify disadvantaged subgroups within populations and inform equity-oriented health policies, programs, and practices. This paper provides an overview of a number of recent and current WHO initiatives related to health inequality monitoring at the global and/or national level. We outline the scope, content, and intended uses/application of the following: Health Equity Monitor database and theme page; State of inequality: reproductive, maternal, newborn, and child health report; Handbook on health inequality monitoring: with a focus on low- and middle-income countries; Health inequality monitoring eLearning module; Monitoring health inequality: an essential step for achieving health equity advocacy booklet and accompanying video series; and capacity building workshops conducted in WHO Member States and Regions. The paper concludes by considering how the work of the WHO can be expanded upon to promote the establishment of sustainable and robust inequality monitoring systems across a variety of health topics among Member States and at the global level.