WorldWideScience

Sample records for instrument failures equipment

  1. Isotope-equipped measuring instruments

    International Nuclear Information System (INIS)

    Miyagawa, Kazuo; Amano, Hiroshi

    1980-01-01

    In the steel industry, though the investment in isotope-equipped measuring instruments is small as compared with that in machinery, they play important role in the moisture measurement in sintering and blast furnaces, the thickness measurement in rolling process and others in automatic control systems. The economic aspect of the isotope-equipped measuring instruments is described on the basis of the practices in Kimitsu Works of Nippon Steel Corporation: distribution of such instruments, evaluation of economic effects, usefulness evaluation in view of raising the accuracy, and usefulness evaluation viewed from the failure of the isotope instruments. The evaluation of economic effects was made under the premise that the isotope-equipped measuring instruments are not employed. Then, the effects of raising the accuracy are evaluated for a γ-ray plate thickness gauge and a neutron moisture gauge for coke in a blast furnace. Finally, the usefulness was evaluated, assuming possible failure of the isotope-equipped measuring instruments. (J.P.N.)

  2. The evaluation of equipment and Instrumentation Reliability Factors on Power Reactor

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  4. 14 CFR 121.303 - Airplane instruments and equipment.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Airplane instruments and equipment. 121.303... Airplane instruments and equipment. (a) Unless otherwise specified, the instrument and equipment... airspeed limitation and item of related information in the Airplane Flight Manual and pertinent placards...

  5. 49 CFR 220.38 - Communication equipment failure.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Communication equipment failure. 220.38 Section 220.38 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD... § 220.38 Communication equipment failure. (a) Any radio or wireless communication device found not to be...

  6. Potentially damaging failure modes of high- and medium-voltage electrical equipment

    International Nuclear Information System (INIS)

    Hoy, H.C.

    1983-07-01

    The electrical equipment failures of both nuclear and nonnuclear public utilities were reviewed. Those failures that could pose an additional problem to surrounding and connected equipment were defined. The literature was searched; utilities, repair shops, and large electrical equipment users were contacted for failure information. The data were reviewed in detail, and failure modes were determined. Sample cascade failures are discussed. The failure rate of electrical equipment in utilities is historically quite low. Nuclear plants record too few failures to be statistically valid, but failures that have been recorded show that good design usually restricts the failure to a single piece of equipment

  7. Potentially damaging failure modes of high- and medium-voltage electrical equipment

    International Nuclear Information System (INIS)

    Hoy, H.C.

    1984-01-01

    The high- and medium-voltage electrical equipment failures of both nuclear and nonnuclear electric utilities have been reviewed for possible disruptive failure modes that would be of special concern in a nuclear power plant. The resulting emphasis was on the electrical faults of transformers, switchgear (circuit breakers), lightning (surge) arrestors, high-voltage cabling and buswork, control boards, and other electrical equipment that, through failure, can be the initiating event that may expand the original fault to nearby or associated equipment. Many failures of such equipment were found and documented, although the failure rate of electrical equipment in utilities is historically quite low. Nuclear plants record too few failures to be statistically valid, but failures that have been recorded show that good design usually restricts the failure to a single piece of equipment. Conclusions and recommendations pertaining to the design, maintenance, and operation of the affected electrical equipment are presented

  8. Diagnosis of Equipment Failures by Pattern Recognition

    DEFF Research Database (Denmark)

    Pau, L. F.

    1974-01-01

    The main problems in relation to automatic fault finding and diagnosis in equipments or production systems are discussed: 1) compression of the syndrome and observation spaces for better discrimination between failure modes; 2) simultaneous display of the failure patterns and the failure instants...

  9. Instrumentation qualification. Seismic qualification of C-E instrumentation equipment. Part One

    International Nuclear Information System (INIS)

    1977-05-01

    A summary of the C-E seismic qualification program utilized to demonstrate the seismic design adequacy of the instrumentation and control equipment used in C-E supplied Nuclear Steam Supply Systems (NSSS) is presented. The report is divided into two parts. Part One includes the equipment seismic requirements and a description of the qualification methods. Part Two lists the specific equipment by nuclear station in which it is used and the equipment test results are summarized in a standard data sheet format to facilitate review. The seismic requirements are based on individual contract commitments with C-E customers and the NRC Standard Review Plan, Section 3.10 ''Seismic Qualification of Category I Instrumentation and Electrical Equipment.'' Equipment is qualified for use in a seismic environment where damage potential to the equipment is less than or equal to that simulated seismic environment to which it has been qualified. The anticipated Safe Shutdown Earthquake (SSE) environment at the inservice location of equipment should be confirmed by each applicant as not exceeding that to which it is qualified

  10. Musical Sound, Instruments, and Equipment

    Science.gov (United States)

    Photinos, Panos

    2017-12-01

    'Musical Sound, Instruments, and Equipment' offers a basic understanding of sound, musical instruments and music equipment, geared towards a general audience and non-science majors. The book begins with an introduction of the fundamental properties of sound waves, and the perception of the characteristics of sound. The relation between intensity and loudness, and the relation between frequency and pitch are discussed. The basics of propagation of sound waves, and the interaction of sound waves with objects and structures of various sizes are introduced. Standing waves, harmonics and resonance are explained in simple terms, using graphics that provide a visual understanding. The development is focused on musical instruments and acoustics. The construction of musical scales and the frequency relations are reviewed and applied in the description of musical instruments. The frequency spectrum of selected instruments is explored using freely available sound analysis software. Sound amplification and sound recording, including analog and digital approaches, are discussed in two separate chapters. The book concludes with a chapter on acoustics, the physical factors that affect the quality of the music experience, and practical ways to improve the acoustics at home or small recording studios. A brief technical section is provided at the end of each chapter, where the interested reader can find the relevant physics and sample calculations. These quantitative sections can be skipped without affecting the comprehension of the basic material. Questions are provided to test the reader's understanding of the material. Answers are given in the appendix.

  11. Process Equipment Failure Mode Analysis in a Chemical Industry

    Directory of Open Access Journals (Sweden)

    J. Nasl Seraji

    2008-04-01

    Full Text Available Background and aims   Prevention of potential accidents and safety promotion in chemical processes requires systematic safety management in them. The main objective of this study was analysis of important process equipment components failure modes and effects in H2S and CO2  isolation from extracted natural gas process.   Methods   This study was done in sweetening unit of an Iranian gas refinery. Failure Mode and Effect Analysis (FMEA used for identification of process equipments failures.   Results   Totally 30 failures identified and evaluated using FMEA. P-1 blower's blade breaking and sour gas pressure control valve bearing tight moving had maximum risk Priority number (RPN, P-1 body corrosion and increasing plug lower side angle of reach DEAlevel control valve  in tower - 1 were minimum calculated RPN.   Conclusion   By providing a reliable documentation system for equipment failures and  incidents recording, maintaining of basic information for later safety assessments would be  possible. Also, the probability of failures and effects could be minimized by conducting preventive maintenance.

  12. 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

  13. Failure diagnosis aiding device for plant equipment

    International Nuclear Information System (INIS)

    Uhara, Yoshihiko.

    1990-01-01

    The present invention intends to improve the efficiency of trouble shooting for equipments of industrial plants such as nuclear power plants. The device of the present invention comprises an intelligence base and an inference mechanism base. The intelligence base comprises a rule base, an information storing section having a part frame and a working frame and a user's frame. The parts frame contains the failure rate on every parts and data on related operations. The working frame contains the importance and frequency of working. The user's frame contains parameters showing the extent of user's skills. The rule base, the parts frame and the working frame can be selected in accordance with the extent of the user's skill in the inference mechanism. With such a constitution, failures can be checked with the intelligence base in accordance with the knowledges for the failures of the equipments and the extent of user's skill by way of the inference mechanism. (I.S.)

  14. Safety shutdowns and failures of the RA reactor equipment; Sigurnosna zaustavljanja i kvarovi opreme na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    Mitrovic, S [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

    1966-07-01

    This report is an attempt of statistical analysis of the failures occurred during RA reactor operation. A list of failures occurred on the RA equipment during 1965 is included. Failures were related to the following systems: dosimetry system (22%), safety and control system (7%), heavy water system (2%), technical water (4%), helium system (2%), measuring instruments (30%), transport, ventilation, power supply systems (32%). A review of safety shutdowns from 1962 to 1966 is included as well, as a comparison with three similar reactors. Although the number of events used for statistical analysis was not adequate, it has been concluded that RA reactor operation was stable and reliable.

  15. Interfacing LabVIEW With Instrumentation for Electronic Failure Analysis and Beyond

    Science.gov (United States)

    Buchanan, Randy K.; Bryan, Coleman; Ludwig, Larry

    1996-01-01

    The Laboratory Virtual Instrumentation Engineering Workstation (LabVIEW) software is designed such that equipment and processes related to control systems can be operationally lined and controlled by the use of a computer. Various processes within the failure analysis laboratories of NASA's Kennedy Space Center (KSC) demonstrate the need for modernization and, in some cases, automation, using LabVIEW. An examination of procedures and practices with the Failure Analaysis Laboratory resulted in the conclusion that some device was necessary to elevate the potential users of LabVIEW to an operational level in minimum time. This paper outlines the process involved in creating a tutorial application to enable personnel to apply LabVIEW to their specific projects. Suggestions for furthering the extent to which LabVIEW is used are provided in the areas of data acquisition and process control.

  16. Operational planning optimization of steam power plants considering equipment failure in petrochemical complex

    International Nuclear Information System (INIS)

    Luo, Xianglong; Zhang, Bingjian; Chen, Ying; Mo, Songping

    2013-01-01

    Highlights: ► We develop a systematic programming methodology to address equipment failure. ► We classify different operation conditions into real periods and virtual periods. ► The formulated MILP models guarantee cost reduction and enough operation safety. ► The consideration of reserving operation redundancy is effective. - Abstract: One or more interconnected steam power plants (SPPs) are constructed in a petrochemical complex to supply utility energy to the process. To avoid large economic penalties or process shutdowns, these SPPs should be flexible and reliable enough to meet the process energy requirement under varying conditions. Unexpected utility equipment failure is inevitable and difficult to be predicted. Most of the conventional methods are based on the assumption that SPPs do not experience any kind of equipment failure. Unfortunately, a process shutdown cannot be avoided when equipment fails unexpectedly. In this paper, a systematic methodology is presented to minimize the total cost under normal conditions while reserving enough flexibility and safety for unexpected equipment failure conditions. The proposed method transforms the different conditions into real periods to indicate normal scenarios and virtual periods to indicate unexpected equipment failure scenarios. The optimization strategy incorporating various operation redundancy scheduling, the transition constraints from equipment failure conditions to normal conditions, and the boiler load increase behavior modeling are presented to save cost and guarantee operation safety. A detailed industrial case study shows that the proposed systematic methodology is effective and practical in coping with equipment failure conditions with only few additional cost penalties

  17. Failure Mode and Effect Analysis of Subsea Multiphase Pump Equipment

    Directory of Open Access Journals (Sweden)

    Oluwatoyin Shobowale Kafayat

    2014-07-01

    Full Text Available Finding oil and gas reserves in deep/harsh environment with challenging reservoir and field conditions, subsea multiphase pumping benefits has found its way to provide solutions to these issues. Challenges such as failure issues that are still surging the industry and with the current practice of information hiding, this issues becomes even more difficult to tackle. Although, there are some joint industry projects which are only accessible to its members, still there is a need to have a clear understanding of these equipment groups so as to know which issues to focus attention on. A failure mode and effect analysis (FMEA is a potential first aid in understanding this equipment groups. A survey questionnaire/interview was conducted with the oil and gas operating company and equipment manufacturer based on the literature review. The results indicates that these equipment’s group are similar with its onshore counterpart, but the difference is the robustness built into the equipment internal subsystems for subsea applications. The results from the manufacturer perspectives indicates that Helico-axial multiphase pump have a mean time to failure of more than 10 years, twin-screw and electrical submersible pumps are still struggling with a mean time to failure of less than 5 years.

  18. Failures by stress corrosion of electrical heating accessories, instrument leads and thermoelements of chromium nickel steel

    International Nuclear Information System (INIS)

    Schwarz, M.

    1982-01-01

    Measurement and control devices are being increasingly used for process control, monitoring and the safety of chemical plants. Pressure, temperature, through-put, moisture, composition and the like are continuously measured at many positions of the system. The supervision of the measuring equipment and hence the necessary exchanging ability of the devices during operation means good access to the plant. An extensive system of pipelines between the measuring equipment and the product lines to be supervised is the result. Common austenite 18 10 CrNi steel pipes of 12 mm diameter and 1 mm wall thickness are used for assembling and corrosion reasons in these pulse instrument leads. The failure of several instrument leads in a large scale plant at the beginning of the frost period interfers with the control. It was therefore necessary to find the exact cause; this is described in the present work. (orig.) [de

  19. Aseismatic design of electrical equipments and instruments for nuclear power stations

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  20. LESSONS LEARNED IN TESTING OF SAFEGUARDS EQUIPMENT

    International Nuclear Information System (INIS)

    Pepper, S.; Farnitano, M.; Carelli, J.; Hazeltine, J.; Bailey, D.

    2001-01-01

    The International Atomic Energy Agency's (IAEA) Department of Safeguards uses complex instrumentation for the application of safeguards at nuclear facilities around the world. Often, this equipment is developed through cooperation with member state support programs because the Agency's requirements are unique and are not met by commercially available equipment. Before approving an instrument or system for routine inspection use, the IAEA subjects it to a series of tests designed to evaluate its reliability. In 2000, the IAEA began to observe operational failures in digital surveillance systems. In response to the observed failures, the IAEA worked with the equipment designer and manufacturer to determine the cause of failure. An action plan was developed to correct the performance issues and further test the systems to make sure that additional operational issues would not surface later. This paper addresses the steps taken to address operation issues related to digital image surveillance systems and the lessons learned during this process

  1. The development of special equipment amplitude detection instrument based on DSP

    International Nuclear Information System (INIS)

    Dai Sidan; Chen Ligang; Lan Peng; Wang Huiting; Zhang Liangxu; Wang Lin

    2014-01-01

    Development and industrial application of special equipment plays an important role in the development of nuclear energy process. Equipment development process need to do a lot of tests, amplitude detection is a key test,it can analysis the device's electromechanical and physical properties. In the industrial application, the amplitude detection can effectively reflect the operational status of the current equipment, the equipment can also be a certain degree of fault diagnosis, identify problems in a timely manner. The main development target in this article is amplitude detection of special equipment. This article describes the development of special equipment amplitude detection instrument. The instrument uses a digital signal processor (DSP) as the central processing unit, and uses the DSP + CPLD + high-speed AD technology to build a complete set of high-precision signal acquisition and analysis processing systems, rechargeable lithium battery as the powered device. It can do a online monitoring of special equipment amplitude, speed parameters by acquiring and analysing the tachometer signal in the special equipment, and locally display through the LCD screen. (authors)

  2. Acoustic Camera as a Fool for Identifying Machinery and Equipment Failures

    Directory of Open Access Journals (Sweden)

    Ľudmila Pavlikova

    2018-03-01

    Full Text Available Sound and noise are as old as humanity itself. They have accompanied civilization, evolution, and development for centuries. Music and speech represent not only the key elements of human life but also unpleasant feelings of noise that have always been an integral part of human existence. As industrial development has required more energy, powerful machinery, and equipment, there have been still noisier machines. Traffic has grown quickly due to the number and speed of vehicles. For that reason, an acoustic camera is used for the dynamic visualization of machinery and equipment noise as it analyses the sources of noise in details. Subsequently, qualified measures are introduced based on the results of the analysis. The paper considers launching another application. According to the proposed methodology, its use in identifying machinery and equipment failures and their maintenance is proved. The experiment was performed on a four-wheel lawn mower. The primary focus was on the identification of failures using an acoustic camera. The previous method allowed to quickly, precisely and efficiently identifying the failures in two out of five tested machines.

  3. Modeling the failure data of a repairable equipment with bathtub type failure intensity

    International Nuclear Information System (INIS)

    Pulcini, G.

    2001-01-01

    The paper deals with the reliability modeling of the failure process of large and complex repairable equipment whose failure intensity shows a bathtub type non-monotonic behavior. A non-homogeneous Poisson process arising from the superposition of two power law processes is proposed, and the characteristics and mathematical details of the proposed model are illustrated. A graphical approach is also presented, which allows to determine whether the proposed model can adequately describe a given failure data. A graphical method for obtaining crude but easy estimates of the model parameters is then illustrated, as well as more accurate estimates based on the maximum likelihood method are provided. Finally, two numerical applications are given to illustrate the proposed model and the estimation procedures

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

    International Nuclear Information System (INIS)

    Sugitani, S.; Nanba, M.

    2006-01-01

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

  5. Root cause analysis underscores the importance of understanding, addressing, and communicating cold chain equipment failures to improve equipment performance.

    Science.gov (United States)

    Lennon, Pat; Atuhaire, Brian; Yavari, Shahrzad; Sampath, Vidya; Mvundura, Mercy; Ramanathan, Nithya; Robertson, Joanie

    2017-04-19

    Vaccine cold chain equipment (CCE) in developing countries is often exposed to harsh environmental conditions, such as extreme temperatures and humidity, and is subject to many additional challenges, including intermittent power supply, insufficient maintenance capacity, and a scarcity of replacement parts. Together, these challenges lead to high failure rates for refrigerators, potentially damaging vaccines and adversely affecting immunization coverage. Providing a sustainable solution for improving CCE performance requires an understanding of the root causes of failure. Project teams conducted small-scale studies to determine the root causes of CCE failure in selected locations in Uganda and Mozambique. The evaluations covered 59 failed refrigerators and freezers in Uganda and 27 refrigerators in Mozambique. In Uganda, the vast majority of failures were due to a cooling unit fault in one widely used refrigerator model. In Mozambique, 11 of the 27 problems were attributable to solar refrigerators with batteries that were unable to hold a charge, and another eight problems were associated with a need to adjust thermostat settings. The studies showed that tracking and evaluation of equipment performance and failure can yield important, actionable information for a range of stakeholders, including local CCE technicians, the ministry of health, equipment manufacturers, and international partners such as the United Nations Children's Fund, World Health Organization, and Gavi, the Vaccine Alliance. Collaborative efforts to systematically collect and communicate data on CCE performance and causes of failure will help to improve the efficiency and reach of immunization programs in low- and middle-income countries. Copyright © 2016 The Author(s). Published by Elsevier Ltd.. All rights reserved.

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

    International Nuclear Information System (INIS)

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

    1987-01-01

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

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

    Science.gov (United States)

    Farmer, N. B.

    1974-01-01

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

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

    International Nuclear Information System (INIS)

    2000-01-01

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

  9. Instrumental parameters' determination in a fluorescences X-ray Philips PW 1400 equipment

    International Nuclear Information System (INIS)

    Martinez, J.M.; Fasio, I.; Baronio, N.; Viola, M.

    1987-01-01

    The instrumental parameters of a Philips PW 1400 equipment wavelengths dispersive are determined; fundamentally, those related to the equipment's accuracy (stability at a very short, short and long term drift) as well as to those related to the detection system (dead time, detector's cleaning and detection limit). (S.M.) [es

  10. Impact of proof test interval and coverage on probability of failure of safety instrumented function

    International Nuclear Information System (INIS)

    Jin, Jianghong; Pang, Lei; Hu, Bin; Wang, Xiaodong

    2016-01-01

    Highlights: • Introduction of proof test coverage makes the calculation of the probability of failure for SIF more accurate. • The probability of failure undetected by proof test is independently defined as P TIF and calculated. • P TIF is quantified using reliability block diagram and simple formula of PFD avg . • Improving proof test coverage and adopting reasonable test period can reduce the probability of failure for SIF. - Abstract: Imperfection of proof test can result in the safety function failure of safety instrumented system (SIS) at any time in its life period. IEC61508 and other references ignored or only elementarily analyzed the imperfection of proof test. In order to further study the impact of the imperfection of proof test on the probability of failure for safety instrumented function (SIF), the necessity of proof test and influence of its imperfection on system performance was first analyzed theoretically. The probability of failure for safety instrumented function resulted from the imperfection of proof test was defined as probability of test independent failures (P TIF ), and P TIF was separately calculated by introducing proof test coverage and adopting reliability block diagram, with reference to the simplified calculation formula of average probability of failure on demand (PFD avg ). Research results show that: the shorter proof test period and the higher proof test coverage indicate the smaller probability of failure for safety instrumented function. The probability of failure for safety instrumented function which is calculated by introducing proof test coverage will be more accurate.

  11. Evaluation tests of the Instrumentation and Control equipment to use in nuclear power plants: its contribution to the improvement and quality certification of the Brazilian equipment

    International Nuclear Information System (INIS)

    Menezes, R.H.M. de; Peluso, M.A.V.

    1984-01-01

    This work presents the procedures used to evaluate Instrumentation Control equipment and reports the experience of integration among instrument user, manufacturer and test institution. It covers tests for equipments for conventional user and for specific application in Nuclear Power Stations. (Author) [pt

  12. Failure Forewarning in NPP Equipment NERI2000-109 Final Project Report

    Energy Technology Data Exchange (ETDEWEB)

    Hively, LM

    2004-03-26

    The objective of this project is forewarning of machine failures in critical equipment at next-generation nuclear power plants (NPP). Test data were provided by two collaborating institutions: Duke Engineering and Services (first project year), and the Pennsylvania State University (Applied Research Laboratory) during the second and third project years. New nonlinear methods were developed and applied successfully to extract forewarning trends from process-indicative, time-serial data for timely, condition-based maintenance. Anticipation of failures in critical equipment at next-generation NPP will improve the scheduling of maintenance activities to minimize safety concerns, unscheduled non-productive downtime, and collateral damage due to unexpected failures. This approach provides significant economic benefit, and is expected to improve public acceptance of nuclear power. The approach is a multi-tiered, model-independent, and data-driven analysis that uses ORNL's novel nonlinear method to extract forewarning of machine failures from appropriate data. The first tier of the analysis provides a robust choice for the process-indicative data. The second tier rejects data of inadequate quality. The third tier removes signal artifacts that would otherwise confound the analysis, while retaining the relevant nonlinear dynamics. The fourth tier converts the artifact-filtered time-serial data into a geometric representation, that is then transformed to a discrete distribution function (DF). This method allows for noisy, finite-length datasets. The fifth tier obtains dissimilarity measures (DM) between the nominal-state DF and subsequent test-state DFs. Forewarning of a machine failure is indicated by several successive occurrences of the DM above a threshold, or by a statistically significant trend in the DM. This paradigm yields robust nonlinear signatures of degradation and its progression, allowing earlier and more accurate detection of the machine failure.

  13. Standardization and improvement of safety for radioisotope equipped instruments

    International Nuclear Information System (INIS)

    Sumi, Tetsuo

    1980-01-01

    The safety for radioisotope-equipped instruments is considered. The one is the safety for the source assembly. The radioisotopes employed for radioisotope-equipped instruments are sealed sources which are used in the state of being contained in the enclosures. Many of the enclosures are provided with shutter mechanism for the purpose of emitting radiation only during the period required. If the possible troubles that might lead to the accidents are sampled out of the results of field operation of radiation instruments, and the safety measures for source enclosures are considered in connection with these troubles, it is no exaggeration to say that the safety for source enclosures has been maintained by preventing the critical accidents by the management of users and the cooperation of manufactures though there were the chance for investigating the safety in the common field and the establishment of JIS Z 4614 standard. Another consideration is concerned with the measures to improve the safety. No accident in the past never guarantees no accident in the future. Accumulation of experience is most effective for those measures, and the more experiences the better. It may be most effective that the manufacturers disclose their experiences each other from the wide outlook overcoming the barrier of trade secret. Fortunately, such consciousness has risen since a few years ago, and the investigation group is doing the works in the Japan Radioisotope Association. On the other hand, the reasonable revision of the radiation injury prevention law is desired. (Wakatsuki, Y.)

  14. Assessment of the causes of failures of roto-dynamic equipment in Cirus

    International Nuclear Information System (INIS)

    Rao, K.N.; Singh, S.; Ganeshan, P.

    1994-01-01

    As a part of Cirus reactor life extension program study, a service life evaluation of critical roto-dynamic equipment in Cirus such as primary coolant pumps, and their concrete foundation structures, pressurised water loop pumps, main air compressors and supply and exhaust fans, was performed. An assessment of the causes of failures of roto-dynamic equipment in Cirus was done. Based on assessment of the degradation mitigating features and comparison to similar roto-dynamic equipment and their concrete foundation structures, it was concluded that life extension of these roto-dynamic equipment and their structures is feasible. To support this conclusion a program involving: a) non-destructive testing, b) surveillance and monitoring and, c) preventive maintenance is recommended. (author). 4 refs

  15. Structuring free form verbal descriptions in equipment failure reports

    International Nuclear Information System (INIS)

    Huzdovich, J.

    1983-01-01

    Information is encoded for convenience in computer sort/search routines used to manage a large number of records. The codes in use for equipment failure reports are limited due to practical considerations, and this limitation forces the reporter to leave out information to satisfy the coding requirements. The free form verbal descriptions, as found in the Generating Availability Data System (GADS) and the Nuclear Plant Reliability Data System (NPRDS), allow for reporting of this non-codable information. A systematic approach to constructing the verbal description based on rules of grammar, especially syntax, results in a structured narrative suitable for computer data management schemes. In addition, the reporter has a full range of descriptive terminology and does not have to select subjectively from a predetermined, limited vocabulary to describe the event. This paper introduces a concept that places in perspective the integration of structured, formal reporting and free form verbal description. A second benefit of this structured narrative is the systematic development of failure mode/failure cause relationships in the event

  16. Specification and acceptance testing of nuclear medicine equipment

    International Nuclear Information System (INIS)

    Wegst, A.V.; Erickson, J.J.

    1984-01-01

    The purchase of nuclear medicine equipment is of prime importance in the operation of a clinical service. Failure to properly evaluate the potential uses of the instrumentation and the various operational characteristics of the equipment can often result in the purchase of inappropriate or inferior instruments. The magnitude of the purchase in terms of time and financial investments make it imperative that the purchase be approached in a systematic manner. Consideration of both the intended clinical functions and personnel requirements is important. It is necessary also to evaluate the ability of the equipment vendor to support the instrumentation after the purchase has been completed and the equipment installed in the clinical site. The desired specifications of the instrument characteristics should be stated in terms that can be verified by acceptance testing. The complexity of modern instrumentation and the sensitivity of it to the environment require the buyer to take into account the potential problems of controlling the temperature, humidity, and electrical power of the installation site. If properly and systematically approached, the purchase of new nuclear medicine instrumentation can result in the acquisition of a powerful diagnostic tool which will have a useful lifetime of many years. If not so approached, it may result in the expenditure of a large amount of money and personnel time without the concomitant return in useful clinical service. (author)

  17. Real-time instrument-failure detection in the LOFT pressurizer using functional redundancy

    International Nuclear Information System (INIS)

    Tylee, J.L.

    1982-07-01

    The functional redundancy approach to detecting instrument failures in a pressurized water reactor (PWR) pressurizer is described and evaluated. This real-time method uses a bank of Kalman filters (one for each instrument) to generate optimal estimates of the pressurizer state. By performing consistency checks between the output of each filter, failed instruments can be identified. Simulation results and actual pressurizer data are used to demonstrate the capabilities of the technique

  18. Lessons learned in testing of Safeguards equipment

    International Nuclear Information System (INIS)

    Pepper, Susan; Farnitano, Michael; Carelli, Joseph

    2001-01-01

    Full text: During the 1990s, the IAEA Department of Safeguards began a transition from analog to digital equipment. This included surveillance equipment, seals, NDA measurement systems, and other instruments. The transition to digital equipment was intended to facilitate compatibility between and integration of instruments, remote communication of data, improved data storage, and modernization. Many of the instruments are designed to operate on battery power during loss of facility power, and therefore, are designed to consume minimal power. In 2000, the IAEA experienced a number of failures in digital image surveillance (DIS) equipment. A study of the performance data revealed that the failures occurred in 'high risk' environments where the systems were exposed to neutrons. As a supporter of IAEA equipment development and implementation, the U.S. Support Program worked with the IAEA, the equipment designer, and the equipment manufacturer in special meetings on DIS to determine the cause of the failures. It was as a result of these meetings that single event upset (SEU) was determined to be the root cause of the failures. The meeting participants also identified a list of actions to improve the reliability of DIS systems. As a result of the DIS meetings and the identified actions, the U.S. Support Program approved a request from the IAEA and established Task E.125, 'Remote Monitoring and Unattended Digital Surveillance Systems.' This task is an umbrella task intended to provide a mechanism for response to IAEA needs related to improving the reliability of unattended, remote monitoring and DIS equipment. Subtasks approved under this task include: E.125.1, 'SDIS Software Consolidation and DCM-14 Audit' - This subtask involves the consolidation of a number of individual upgrades to the SDIS and review of the DCM-14 software. As the sponsor of the design of the DCM-14 by Dr. Neumann, the German Support Program is also a participant in this subtask; E.125.2, 'DIS

  19. Process pump operating problems and equipment failures, F-Canyon Reprocessing Facility, Savannah River Plant

    International Nuclear Information System (INIS)

    Durant, W.S.; Starks, J.B.; Galloway, W.D.

    1987-02-01

    A compilation of operating problems and equipment failures associated with the process pumps in the Savannah River Plant F-Canyon Fuel Reprocessing Facility is presented. These data have been collected over the 30-year operation of the facility. An analysis of the failure rates of the pumps is also presented. A brief description of the pumps and the data bank from which the information was sorted is also included

  20. Electronic equipment packaging technology

    CERN Document Server

    Ginsberg, Gerald L

    1992-01-01

    The last twenty years have seen major advances in the electronics industry. Perhaps the most significant aspect of these advances has been the significant role that electronic equipment plays in almost all product markets. Even though electronic equipment is used in a broad base of applications, many future applications have yet to be conceived. This versatility of electron­ ics has been brought about primarily by the significant advances that have been made in integrated circuit technology. The electronic product user is rarely aware of the integrated circuits within the equipment. However, the user is often very aware of the size, weight, mod­ ularity, maintainability, aesthetics, and human interface features of the product. In fact, these are aspects of the products that often are instrumental in deter­ mining its success or failure in the marketplace. Optimizing these and other product features is the primary role of Electronic Equipment Packaging Technology. As the electronics industry continues to pr...

  1. MONITORING OF THE PERFORMANCE EFFICIENCY OF THE EQUIPMENT AT THE ENTERPRISES OF AVIATION INSTRUMENTATION

    Directory of Open Access Journals (Sweden)

    Petr P. Dobrov

    2016-01-01

    Full Text Available The article elaborates the proposals to improve the systems for monitoring performance of the equipment at the enterprises of aviation instrument. The relevance of the study due to the fact that the aviation instrument-making industry of the Russian Federation can play a role as a key factor in enhancing the competitiveness of the national economy. Currently, the global aviation market is fairly saturated, it competition is not between individual companies and between the aviation powers. The role of an efficient industrial production is largely dependent on the amount, structure, technical condition and the level of utilization of fixed assets. Specificity of high-tech high-tech production presupposes the existence of a specific fleet of expensive and unique equipment; a high degree of novelty products, single or small-scale type of production that determines the high cost of production of a unit of production; high demands on the staff . The paper noted that the production capacity is an essential tool for production planning process, which allows to determine the optimal work shifts Park main technological equipment and production program to justify the enterprises of sphere of aviation instrument. On the basis of the modification of OEE method, a stochastic model is proposed, which allows to display the efficiency of the productive capacity of the high-tech enterprises of sphere of aviation instrument in the form of multi-dimensional size and much more accurately identify the relationship between its elements.

  2. Development of instrumentation in the transport phenomena research in thermal equipment

    International Nuclear Information System (INIS)

    Carvalho Tofani, P. de; Ladeira, L.C.D.

    1983-11-01

    The results obtained from the effort on the acquisition of know-how in experimental reactor thermal during the last years, through the approach of relevant aspects of basic research on transport phenomena applicable to nuclear reactor analysis and conventional thermal equipment based in the simultaneous development of instrumentation and experimental methods are presented. (E.G.) [pt

  3. Recovery from equipment failures in ATC: Determination of contextual factors

    International Nuclear Information System (INIS)

    Subotic, Branka; Ochieng, Washington Y.; Straeter, Oliver

    2007-01-01

    Human reliability assessment (HRA) currently uses various approaches to determine and quantify human error. These approaches are increasingly being employed in various safety-critical domains, such as air traffic management and its ground component air traffic control. HRA research over the years has shown the important role of the context in which human errors take place. Recent techniques now put more emphasis on the definition of key contextual factors and their impact on the reliability of human performance. This paper presents a review of the current understanding of contextual factors in various industries. It uses this together with results from controller interviews to identify the contextual factors relevant to controller recovery from equipment failures in air traffic control. These factors should be used in conjunction with an appropriate method to analyse the performance of a controller during the process of recovery from failures

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-03-01

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

  5. 42 CFR 493.1252 - Standard: Test systems, equipment, instruments, reagents, materials, and supplies.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Test systems, equipment, instruments... SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY... storage of reagents and specimens, accurate and reliable test system operation, and test result reporting...

  6. A Study on Estimating the Next Failure Time of Compressor Equipment in an Offshore Plant

    Directory of Open Access Journals (Sweden)

    SangJe Cho

    2016-01-01

    Full Text Available The offshore plant equipment usually has a long life cycle. During its O&M (Operation and Maintenance phase, since the accidental occurrence of offshore plant equipment causes catastrophic damage, it is necessary to make more efforts for managing critical offshore equipment. Nowadays, due to the emerging ICTs (Information Communication Technologies, it is possible to send health monitoring information to administrator of an offshore plant, which leads to much concern on CBM (Condition-Based Maintenance. This study introduces three approaches for predicting the next failure time of offshore plant equipment (gas compressor with case studies, which are based on finite state continuous time Markov model, linear regression method, and their hybrid model.

  7. Face haulage equipment failure analysis. Volume I. Technical information and conclusions. Final technical report as of November 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Patterson, W.N.; Orona, F.

    1980-11-01

    Face haulage equipment used in conjunction with continuous miners (shuttle cars, diesel haulers, battery scoops, and bridge conveyors) was investigated by recording section delay reports for computer analysis to determine the effect of haulage equipment failures and downtime on productivity, pinpoint the causes of machine failures and downtime, and develop the possible design and operational changes required to reduce machine failures and downtime and increase section productivity. For the mobile vehicle type of haulage (shuttle car, diesel hauler, and battery scoop) failure of one unit in multiple unit haulage operations would not normally stop section production. Bridge conveyors as a haulage system provide continuous haulage of section production but when any part of the bridge system fails, the section production is stopped. In the course of this program, it was determined through the use of daily section shift reports on 200 machines that face haulage equipment is responsible for about 40 to 56 minutes of lost section production time per shift. The most prevalent failure for shuttle cars was found to be the trailing cable umbilical. Bridge conveyors had the most trouble with the conveyor subsystem. Discussions of these and other recorded failures are developed with possible solutions outlined for future implementation. This report only covers the face haulage element of the continuous miner system. Companion reports were developed for the continuous miner and roof bolter elements under separate task orders.

  8. Results of evaluation of quality control measurement instrument of x-ray diagnostic equipment by non-invasive method

    International Nuclear Information System (INIS)

    Laan, Flavio T. van der; Elbern, Alvin W.

    1996-01-01

    This work shows the results of the tests realized on Santa Rita Hospital (Porto Alegre), using a non invasive quality control measurement instrument, developed in this University for fast measurement of essential parameters of X-rays diagnostic equipment. In the tests we used a diagnostics Siemens X ray, model Heliofos 4E as our standard equipment. The linearity test of sensor probe and the exposure rate calibration was performed, with a Palmer Dosimeter. For the kVp and exposure time we used a RTI commercial instrument. (author)

  9. Complex of the equipment for instrumental element analysis

    International Nuclear Information System (INIS)

    Borisov, G.I.; Komkov, M.M.; Kuz'michev, V.A.

    1986-01-01

    Complex of the equipment for instrumental element analysis at the IR-8 reactor is designed, fabricated and taken into operation. The complex is provided with a multichannel system of vacuum pneumatic transport with radiation positions in the reactor horizontal tangential channel for neutron-activation analysis by short-lived isotopes; specialized dry vertical channels in a beryllium reflector of the reactor and remote system of radioactive sample replacement for neutron-activation analysis by long-lived isotopes; a specialized horizontal tangential channel for neutron beam extraction by means of a beryllium converter and remote device for studied sample replacement under radiation and measurement of prompt γ-radiation for neutron-radiation analysis; a measuring center using minicomputers for experimental data accumulation and processing and analysis control

  10. Assessment of Equipment Capability to Perform Reliably under Severe Accident Conditions

    International Nuclear Information System (INIS)

    2017-07-01

    The experience from the last 40 years has shown that severe accidents can subject electrical and instrumentation and control (I&C) equipment to environmental conditions exceeding the equipment’s original design basis assumptions. Severe accident conditions can then cause rapid degradation or damage to various degrees up to complete failure of such equipment. This publication provides the technical basis to consider when assessing the capability of electrical and I&C equipment to perform reliably during a severe accident. It provides examples of calculation tools to determine the environmental parameters as well as examples and methods that Member States can apply to assess equipment reliability.

  11. On a method of evaluation of failure rate of equipment and pipings under excess-earthquake loadings

    International Nuclear Information System (INIS)

    Shibata, H.; Okamura, H.

    1979-01-01

    This paper deals with a method of evaluation of the failure rate of equipment and pipings in nuclear power plants under an earthquake which is exceeding the design basis earthquake. If we put the ratio of the maximum ground acceleration of an earthquake to that of the design basis earthquake as n, then the failure rate or the probability of failure is the function of n as p(n). The purpose of this study is establishing the procedure of evaluation of the relation n vs. p(n). (orig.)

  12. Proof-testing strategies induced by dangerous detected failures of safety-instrumented systems

    International Nuclear Information System (INIS)

    Liu, Yiliu; Rausand, Marvin

    2016-01-01

    Some dangerous failures of safety-instrumented systems (SISs) are detected almost immediately by diagnostic self-testing as dangerous detected (DD) failures, whereas other dangerous failures can only be detected by proof-testing, and are therefore called dangerous undetected (DU) failures. Some items may have a DU- and a DD-failure at the same time. After the repair of a DD-failure is completed, the maintenance team has two options: to perform an insert proof test for DU-failure or not. If an insert proof test is performed, it is necessary to decide whether the next scheduled proof test should be postponed or performed at the scheduled time. This paper analyzes the effects of different testing strategies on the safety performance of a single channel of a SIS. The safety performance is analyzed by Petri nets and by approximation formulas and the results obtained by the two approaches are compared. It is shown that insert testing improves the safety performance of the channel, but the feasibility and cost of the strategy may be a hindrance to recommend insert testing. - Highlights: • Identify the tests induced by detected failures. • Model the testing strategies following DD-failures. • Propose analytical formulas for effects of strategies. • Simulate and verify the proposed models.

  13. Failure Analysis Of The Bolt From Turn Table Tightening On The Heavy Lifting Equipment System

    International Nuclear Information System (INIS)

    Hatta, IIham

    2000-01-01

    This paper provides the results of failure analysis of the bolt from the turn table tightening which usually using on the heavy lifting equipment or as a equipment tor the material handling with the maximum load about 25 ton. The process of the failure analysis from the series of laboratory testing such as chemical composition, tensile testing, hardness, fracture surtace and microstructure. The results of the analysis we see this bolt have suffered fatigue failure and the initiation, cracking from the manufacture defect. This defect in the form like the folding on the screw surface which maybe happen at the screw forming process. This folding as a part of metal which not bonding together, so could act as a initial crack, and got the creasing of the strength too which cause from oxidation and decarburization at the moment of heat treatment process. So this material got the changein the strength too which oxidation and decarburization at the moment of heat treatment process. So this material got the change in the microstructure, from the martensite temper to the coarse ferrite and finally reduces the strength of the bolt

  14. Detection of instrument or component failures in a nuclear plant by Luenberger observers

    International Nuclear Information System (INIS)

    Wilburn, N.P.; Colley, R.W.; Alexandro, F.J.; Clark, R.N.

    1985-01-01

    A diagnostic system, which will distinguish between instrument failures (flowmeters, etc.) and component failures (valves, filters, etc.) that show the same symptoms, has been developed for nuclear Plants using Luenberger observers. Luenberger observers are online computer based modules constructed following the technology of Clark [3]. A seventh order model of an FFTF subsystem was constructed using the Advanced Continuous Simulation Language (ACSL) and was used to show through simulation that Luenberger observers can be applied to nuclear systems

  15. Development of KSC program for investigating and generating field failure rates. Reliability handbook for ground support equipment

    Science.gov (United States)

    Bloomquist, C. E.; Kallmeyer, R. H.

    1972-01-01

    Field failure rates and confidence factors are presented for 88 identifiable components of the ground support equipment at the John F. Kennedy Space Center. For most of these, supplementary information regarding failure mode and cause is tabulated. Complete reliability assessments are included for three systems, eight subsystems, and nine generic piece-part classifications. Procedures for updating or augmenting the reliability results are also included.

  16. Instrument failure detection of flow measurement in the feedwater system of the Paks Nuclear Power Plant, Hungary

    International Nuclear Information System (INIS)

    Racz, A.

    1990-12-01

    The applicability of two different methods for early detection of instrument failures of the flow measurement in feedwater systems are investigated. Both methods are based on Kalman filtering technique of stochastic processes. The reliability of the model for description of a feedwater system is checked by comparing calculated values with measured data. Possible instrument failures are simulated in order to show the capability of the proposed procedures. A practical measurement system arrangement is suggested. (author) 10 refs.; 16 figs.; 4 tabs

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

    International Nuclear Information System (INIS)

    Seegmiller, D.S.

    1984-01-01

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

  18. Nuclear instrument maintenance - problems, solutions, and obstacles

    International Nuclear Information System (INIS)

    Vuister, P.H.

    1983-01-01

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

  19. A comparative study on the HW reliability assessment methods for digital I and C equipment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Hoan Sung; Sung, T. Y.; Eom, H. S.; Park, J. K.; Kang, H. G.; Lee, G. Y. [Korea Atomic Energy Research Institute, Taejeon (Korea); Kim, M. C. [Korea Advanced Institute of Science and Technology, Taejeon (Korea); Jun, S. T. [KHNP, Taejeon (Korea)

    2002-03-01

    It is necessary to predict or to evaluate the reliability of electronic equipment for the probabilistic safety analysis of digital instrument and control equipment. But most databases for the reliability prediction have no data for the up-to-date equipment and the failure modes are not classified. The prediction results for the specific component show different values according to the methods and databases. For boards and systems each method shows different values than others also. This study is for reliability prediction of PDC system for Wolsong NPP1 as a digital I and C equipment. Various reliability prediction methods and failure databases are used in calculation of the reliability to compare the effects of sensitivity and accuracy of each model and database. Many considerations for the reliability assessment of digital systems are derived with the results of this study. 14 refs., 19 figs., 15 tabs. (Author)

  20. Study on Instrument Fault Detection using OLM Techniques for PHM Application in NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hwan; Park, Gee Yong; Kim, Jung Taek; Hur, Seop [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The diagnosis system is relatively being mature owing to many research. Among the various models, this paper introduces some On-Line Monitoring (OLM) models for instrument health monitoring and review applicability on NPPs. In recent years, many researchers are being focused on the prognostics which is predicting the future failure of instruments or equipment by using the status monitoring data. By using the prognostic techniques, we can expect a lot of advantages such as ease of control, power optimization, or optimal use of maintenance resources. And we have performed the test for detecting fault of safety-critical instruments and analyzed the fault detection sensitivity for various instrument failure modes using OLM techniques. OLM techniques using data-driven based model such AAKR or AANN can be useful tools for securing integrity of safety-critical instrument that should always keep healthy conditions for the plant safety.

  1. Integrated Instrumentation and Sensor Systems Enabling Condition-Based Maintenance of Aerospace Equipment

    Directory of Open Access Journals (Sweden)

    Richard C. Millar

    2012-01-01

    Full Text Available The objective of the work reported herein was to use a systems engineering approach to guide development of integrated instrumentation/sensor systems (IISS incorporating communications, interconnections, and signal acquisition. These require enhanced suitability and effectiveness for diagnostics and health management of aerospace equipment governed by the principles of Condition-based maintenance (CBM. It is concluded that the systems engineering approach to IISS definition provided clear benefits in identifying overall system requirements and an architectural framework for categorizing and evaluating alternative architectures, relative to a bottom up focus on sensor technology blind to system level user needs. CBM IISS imperatives identified include factors such as tolerance of the bulk of aerospace equipment operational environments, low intrusiveness, rapid reconfiguration, and affordable life cycle costs. The functional features identified include interrogation of the variety of sensor types and interfaces common in aerospace equipment applications over multiplexed communication media with flexibility to allow rapid system reconfiguration to adapt to evolving sensor needs. This implies standardized interfaces at the sensor location (preferably to open standards, reduced wire/connector pin count in harnesses (or their elimination through use of wireless communications.

  2. Controller recovery from equipment failures in air traffic control: A framework for the quantitative assessment of the recovery context

    International Nuclear Information System (INIS)

    Subotic, Branka; Schuster, Wolfgang; Majumdar, Arnab; Ochieng, Washington

    2014-01-01

    Air Traffic Control (ATC) involves a complex interaction of human operators (primarily air traffic controllers), equipment and procedures. On the rare occasions when equipment malfunctions, controllers play a crucial role in the recovery process of the ATC system for continued safe operation. Research on human performance in other safety critical industries using human reliability assessment techniques has shown that the context in which recovery from failures takes place has a significant influence on the outcome of the process. This paper investigates the importance of context in which air traffic controller recovery from equipment failures takes place, defining it in terms of 20 Recovery Influencing Factors (RIFs). The RIFs are used to develop a novel approach for the quantitative assessment of the recovery context based on a metric referred to as the Recovery Context Indicator (RCI). The method is validated by a series of simulation exercises conducted at a specific ATC Centre. The proposed method is useful to assess recovery enhancement approaches within ATC centres

  3. 21 CFR 111.117 - What quality control operations are required for equipment, instruments, and controls?

    Science.gov (United States)

    2010-04-01

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

  4. 75 FR 26180 - Effects on Broadband Communications Networks of Damage To or Failure of Network Equipment or...

    Science.gov (United States)

    2010-05-11

    ... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Chapter I [PS Docket No. 10-92; FCC 10-62] Effects on... the National Broadband Plan, the Federal Communications Commission (Commission or FCC) adopted this... networks and to explore potential measures to reduce network vulnerability to failures in network equipment...

  5. IEEE gathers nuclear part failure data via Delphi poll

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    A description is given of a nuclear power plant component failure rate manual being prepared by the Institute of Electrical and Electronics Engineers. The manual will contain separate chapters on the following equipment categories: annunciator modules; batteries and chargers; blowers, circuit-breakers, interrupters, and relays; motors and generators; heaters; transformers; valve operators and actuators; instruments, controls, and sensors; and cables, raceways, joints, and terminations

  6. Instrument reliability for high-level nuclear-waste-repository applications

    International Nuclear Information System (INIS)

    Rogue, F.; Binnall, E.P.; Armantrout, G.A.

    1983-01-01

    Reliable instrumentation will be needed to evaluate the characteristics of proposed high-level nuclear-wasted-repository sites and to monitor the performance of selected sites during the operational period and into repository closure. A study has been done to assess the reliability of instruments used in Department of Energy (DOE) waste repository related experiments and in other similar geological applications. The study included experiences with geotechnical, hydrological, geochemical, environmental, and radiological instrumentation and associated data acquisition equipment. Though this paper includes some findings on the reliability of instruments in each of these categories, the emphasis is on experiences with geotechnical instrumentation in hostile repository-type environments. We review the failure modes, rates, and mechanisms, along with manufacturers modifications and design changes to enhance and improve instrument performance; and include recommendations on areas where further improvements are needed

  7. The effect of smoke from plastics on digital communications equipment

    International Nuclear Information System (INIS)

    Tanaka, T.J.; Chapin, J.T.

    1998-01-01

    Smoke from plastics can cause immediate problems in electrical equipment in the form of shorting and increased leakage currents, as well as long-term corrosion (metal loss). The short-term problems can be especially serious for critical control instrumentation such as that found in nuclear reactors or telecommunications systems. The US Nuclear Regulatory Commission and Sandia National Laboratories are sponsoring a program to determine the modes and probabilities of digital equipment failure during exposure to smoke and up to 24 hours after the exposure. Early tests on computer systems have shown that the most common immediate problems are temporary and are likely to be caused by increased leakage currents. High-voltage circuits are especially vulnerable since the charged particles in smoke are drawn to those surfaces. To study failure probabilities, smoke exposure tests with real-time measurements will be carried out to determine how the electrical properties of the environment are affected by smoke concentration and content. Digital communication cable will be included in the tests because temporary shorts that cannot be detected through dc measurements may cause interruptions in communications between computers. The reaction of the equipment to changed electrical properties of the environment will be modeled. Equipment that can be used for testing and modeling is being solicited

  8. Instrument Control (iC) - An Open-Source Software to Automate Test Equipment.

    Science.gov (United States)

    Pernstich, K P

    2012-01-01

    It has become common practice to automate data acquisition from programmable instrumentation, and a range of different software solutions fulfill this task. Many routine measurements require sequential processing of certain tasks, for instance to adjust the temperature of a sample stage, take a measurement, and repeat that cycle for other temperatures. This paper introduces an open-source Java program that processes a series of text-based commands that define the measurement sequence. These commands are in an intuitive format which provides great flexibility and allows quick and easy adaptation to various measurement needs. For each of these commands, the iC-framework calls a corresponding Java method that addresses the specified instrument to perform the desired task. The functionality of iC can be extended with minimal programming effort in Java or Python, and new measurement equipment can be addressed by defining new commands in a text file without any programming.

  9. 75 FR 49870 - Effects on Broadband Communications Networks of Damage to or Failure of Network Equipment or...

    Science.gov (United States)

    2010-08-16

    ... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Chapter I [PS Docket No. 10-92; DA 10-1357] Effects on Broadband Communications Networks of Damage to or Failure of Network Equipment or Severe Overload AGENCY... with rubber bands or fasteners. Any envelopes must be disposed of before entering the building...

  10. Nuclear instrument upgrade at Connecticut Yankee Atomic Power Station

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  11. Performance monitoring of safeguards equipment

    International Nuclear Information System (INIS)

    Sirisena, K.; Peltoranta, M.; Goussarov, V.; Vodrazka, P.

    1999-01-01

    SGTCS is responsible for monitoring and reporting the performance of the SG equipment. Performance monitoring (PM) has been implemented in most important safeguards equipment operating unattended in nuclear facilities. Inspectors acquire equipment performance data in facilities. After inspection, the data package is submitted to SGTCS for processing and analysis. The performance data is used for identification of systems or components, which should be changed in the field and for identification of modules which, should be diagnosed at HQ in order to determine the cause of failure. Moreover, the performance data is used for preventive maintenance and spares distribution planning, and to provide statistics for official reports and management decision making. An important part of the performance monitoring is reporting. Equipment performance reports contain information about equipment inventory, utilization, failure types, failure distribution, and reliability. Trends in performance are given in graphical form in cases, where past data is available. Reliability estimates such as expected times between failures are provided. The automated reporting tools are obtainable through EMIS database application. (author)

  12. Welding of sule elements for nuclear reactors with solid state YAG laser using instrumentated testing equipments

    International Nuclear Information System (INIS)

    Bourgault, F.; Lacoste, J.; Schley, R.; Kluzinski, C.; Piednoir, P.

    1985-09-01

    The instrumentation of the equipment for carrying out safety tests on fuel elements for nuclear reactors requires special thermocouples adapted to the prevailing agressive medium. The investigations described deal essentially with the operational and metallurgical weldability tests out on the safety test zircaloy piping in the pressurized water circuit (PHEBUS-programme) [fr

  13. Instrument Failure, Stress, and Spatial Disorientation Leading to a Fatal Crash With a Large Aircraft.

    Science.gov (United States)

    Tribukait, Arne; Eiken, Ola

    2017-11-01

    An aircraft's orientation relative to the ground cannot be perceived via the sense of balance or the somatosensory system. When devoid of external visual references, the pilot must rely on instruments. A sudden unexpected instrument indication is a challenge to the pilot, who might have to question the instrument instead of responding with the controls. In this case report we analyze, from a human-factors perspective, how a limited instrument failure led to a fatal accident. During straight-ahead level flight in darkness, at 33,000 ft, the commander of a civil cargo airplane was suddenly confronted by an erroneous pitch-up indication on his primary flight display. He responded by pushing the control column forward, making a bunt maneuver with reduced/negative Gz during approximately 15 s. The pilots did not communicate rationally or cross-check instruments. Recordings of elevator and aileron positions suggest that the commander made intense efforts to correct for several extreme and erroneous roll and pitch indications. Gz displayed an increasing trend with rapid fluctuations and peaks of approximately 3 G. After 50 s the aircraft entered a turn with decreasing radius and finally hit the ground in an inverted attitude. A precipitate maneuvring response can, even if occurring in a large aircraft at high altitude, result in a seemingly inexorable course of events, ending with a crash. In the present case both pilots were probably incapacitated by acute psychological stress and spatial disorientation. Intense variations in Gz may have impaired the copilot's reading of the functioning primary flight display.Tribukait A, Eiken O. Instrument failure, stress, and spatial disorientation leading to a fatal crash with a large aircraft. Aerosp Med Hum Perform. 2017; 88(11):1043-1048.

  14. Availability analysis of the nuclear instrumentation of a research reactor

    International Nuclear Information System (INIS)

    Vianna Filho, Alfredo Marques

    2016-01-01

    The maintenance of systems and equipment is a central question related to Production Engineering. Although systems are not fully reliable, it is often necessary to minimize the failure occurrence likelihood. The failures occurrences can have disastrous consequences during a plane flight or operation of a nuclear power plant. The elaboration of a maintenance plan has as objective the prevention and recovery from system failures, increasing reliability and reducing the cost of unplanned shutdowns. It is also important to consider the issues related to organizations safety, especially those dealing with dangerous technologies. The objective of this thesis is to propose a method for maintenance analysis of a nuclear research reactor, using a socio-technical approach, and focused on existing conditions in Brazil. The research reactor studied belongs to the federal government and it is located in the city of Rio de Janeiro. The specific objective of this thesis is to develop the availability analysis of one of the principal systems of the research reactor, the nuclear instrumentation system. In this analysis, were taken into account not only the technical aspects of the modules related to nuclear instrumentation system, but also the human and organizational factors that could affect the availability of the nuclear instrumentation system. The results showed the influence of these factors on the availability of the nuclear instrumentation system. (author)

  15. 14 CFR 91.213 - Inoperative instruments and equipment.

    Science.gov (United States)

    2010-01-01

    ... specific operations by this part. (c) A person authorized to use an approved Minimum Equipment List issued... a master minimum equipment list has not been developed; or (ii) Small rotorcraft, nonturbine-powered small airplane, glider, or lighter-than-air aircraft for which a Master Minimum Equipment List has been...

  16. Annual report of the group for maintenance of electronic equipment

    International Nuclear Information System (INIS)

    Popovic, B.

    1965-01-01

    Maintenance and repair of the RA reactor control and safety systems were uniformly distributed during the whole year and were done according to the annual plan. A series of repairs of he electronic equipment as well as exchange of electronic components and elec tonic tubes. The testing and calibration of control and protection circuits were done regularly according to the needs and operation state of the reactor and according to the instructions. Inspections, repairs and reconstructions well as operating characteristics of individual elements as well as complete electronic circuits during 1965 have shown da the systems of control and safety are still in good condition. Somewhat higher number of failures due to aging of electronic tubes is a regular consequence of equipment and instrumentation aging [sr

  17. Instrument Control (iC) – An Open-Source Software to Automate Test Equipment

    Science.gov (United States)

    Pernstich, K. P.

    2012-01-01

    It has become common practice to automate data acquisition from programmable instrumentation, and a range of different software solutions fulfill this task. Many routine measurements require sequential processing of certain tasks, for instance to adjust the temperature of a sample stage, take a measurement, and repeat that cycle for other temperatures. This paper introduces an open-source Java program that processes a series of text-based commands that define the measurement sequence. These commands are in an intuitive format which provides great flexibility and allows quick and easy adaptation to various measurement needs. For each of these commands, the iC-framework calls a corresponding Java method that addresses the specified instrument to perform the desired task. The functionality of iC can be extended with minimal programming effort in Java or Python, and new measurement equipment can be addressed by defining new commands in a text file without any programming. PMID:26900522

  18. Electrical equipment qualification

    International Nuclear Information System (INIS)

    Farmer, W.S.

    1983-01-01

    Electrical equipment qualification research programs being carried out by CEA, JAERI, and Sandia Laboratories are discussed. Objectives of the program are: (1) assessment of accident simulation methods for electrical equipment qualification testing; lower coarse (2) evaluation of equipment aging and accelerated aging methods; (3) determine radiation dose spectrum to electrical equipment and assess simulation methods for qualification; (4) identify inadequacies in electrical equipment qualification procedures and standards and potential failure modes; and (5) provide data for verifying and improving standards, rules and regulatory guides

  19. Preliminary studies on the impact of smoke on digital equipment

    International Nuclear Information System (INIS)

    Tanaka, T.J.; Korsah, K.; Antonescu, C.

    1995-01-01

    Last year the USNRC initiated a program at Sandia National Laboratories to determine the potential impact of smoke on advanced safety-related digitial instrumentation. In recognition of the fact that the reliability of safety-related equipment during or shortly after a fire in a nuclear power plant is more risk significant than long-term effects, we are concentrating on short-term failures. We exposed a multiplexer module board to three different types of smoke to determine whether the smoke would affect its operation. The operation of the multiplexer board was halted by one out of the three smoke exposures. In coordination with Oak Ridge National Laboratory, an experimental digital safety system was also smoke tested. The series of tests showed that smoke can cause potentially serious failures of a safety system. Most of these failures were intermittent and showed that smoke can temporarily interrupt communication between digital systems

  20. Use and maintenance of nuclear medicine instruments in Southeast Asia

    International Nuclear Information System (INIS)

    1983-02-01

    Nuclear medicine instruments are rather sophisticated. They are difficult to maintain in effective working condition, especially in developing countries. The present document describes a survey conducted in Bangladesh, India, Malaysia, Pakistan, Philippines, Singapore, Sri Lanka and Thailand from October 1977 to March 1978, on the use and maintenance of nuclear medicine equipment. The survey evaluated the existing problems of instrument maintenance in the 8 countries visited. The major instruments in use were (1) scintillation probe counters, (2) well scintillation counters and (3) rectilinear cameras. Gamma camera was not widely available in the region at the time of the survey. Most of the surveyed instruments were kept in a detrimental environment resulting in a high failure rate, that caused the relatively high instrument unavailability of 11%. Insufficient bureaucratic handling of repair cases, difficulties with the supply of spare- and replacement parts and lack of training proved to be the main reasons for long periods of instrument inoperation. Remedial actions, based on the survey data, have been initiated

  1. Evaluating performance characteristics of x-ray equipment and film systems without the use of electronic measurement and/or special instruments

    International Nuclear Information System (INIS)

    Bianchi, M.F.; DeNitto, C.; Liscio, A.; Scala, N.

    2004-01-01

    Measurement and control of characteristics of NDT equipment and system that produce output to be interpreted by inspector is one of the most important tools for NDT reliability. Control activity should be based on: initial accurate measurement and calibration; periodical check to assure maintenance of calibration status; and, immediate verification and corrective action when any malfunctioning is suspected. 'Self-calibration' intended as capability of NDT facility to calibrate and control its own equipment and systems is very important for continuous and reliable activity. Typical approach based on this philosophy is ASTM E317 'Standard Practice for Evaluating Performance Characteristics of Ultrasonic Pulse-Echo Examination Instruments and Systems Without the Use of Electronic Measurement Instruments' that is applicable to shop or field conditions. Is 'Self-calibration' applicable to radiographic system too? Many characteristics can be self-determined according to existing practices and methods, but other ones require assistance and cooperation of supplier both for film system and x-ray equipment. A certified film system being controlled by pre-exposed filmstrips can be adopted as 'measurement device' for X-ray output concerning both intensity and contrast. Basically x-ray equipment manufacturer performs initial accurate measurement and calibration using electronic measurement and/or special instrumentation as necessary. Then specific film set on 'low-price' blocks and specimens is produced according to standard practice whose guidelines are supplied by this paper. Film set, blocks, specimens and results referred to specific film system will be the reference kit for periodical check in NDT facility. This paper supplies some guidelines for standard practice based on testing using mainly GE Inspection Technologies radiographic system being available in Avio facilities. (author)

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  3. Instrumentation and equipment for monitoring and controlling NPP post-accident situations. Working material. Proceedings of a specialists' meeting held in Dimitrovgrad, Russian Federation, 12-15 September 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The objectives of the Specialist's Meeting were: To provide an international forum for presentation and discussion on experience with instrumentation and equipment for monitoring and controlling NPP post-accident situations; to share experience on the design and improvements in the subject area; to identify and describe advanced features for safety and post-accident management improvements. In order to facilitate a structure discussion and not to omit important problem areas, papers on the following subjects were considered to be within the scope of the Specialist's Meeting: Analysis of existing post-accident instrumentation (in terms of range, qualification and redundancy) to support post-accident management. Requirements for post accident instrumentation and equipment - operating experience, regulations, standards; experience in upgrading of the existing instrumentation; instrumentation and equipment for emergency management systems (emergency rooms and national centers); post-accident computerized aids to assist operators; post-accident operating procedures; R and D in post-accident instrumentation, future trends. The present volume contains: (1) the papers presented by national delegates; (2) programme of the meeting; (3) description of the RIAR research facilities; and (4) list of participants. Refs, figs and tabs

  4. Seismic qualification of non-safety class equipment whose failure would damage safety class equipment

    International Nuclear Information System (INIS)

    LaSalle, F.R.

    1991-01-01

    Both Code of Federal Regulations, Title 10, Part 50, and US Department of Energy Order 6340.1A have requirements to assess the interaction of non-safety and safety class structures and equipment during a seismic event to maintain the safety function. At the Hanford Site, a cost effective program has been developed to perform the evaluation of non-safety class equipment. Seismic qualification is performed by analysis, test, or upgrading of the equipment to ensure the integrity of safety class structures and equipment. This paper gives a brief overview and synopsis that address design analysis guidelines including applied loading, damping values, component anchorage, allowable loads, and stresses. Test qualification of equipment and walkdown acceptance criteria for heating ampersand ventilation (H ampersand V) ducting, conduit, cable tray, missile zone of influence, as well as energy criteria are presented

  5. The application and practice of predictive maintenance at CANDU equipment management

    International Nuclear Information System (INIS)

    Yu Guangting

    2014-01-01

    The equipment in Qinshan CANDU unit is characterized by large number and complex structure. Some equipment failure has no relation with the operation time, it is impossible to avoid the failure of these equipment only by periodical maintenance. To improve the equipment reliability, increase the equipment usability and decrease the maintenance cost, for important equipment related to nuclear safety and generating electricity, it is required to perform condition monitoring and the predictive maintenance (PdM). According to different characteristics of equipment, it is required to use suitable equipment condition monitoring method, content and frequency. In this way, some potential equipment failure can be found, preventive maintenance can be arranged in advance, and equipment maintenance management can be optimized. (author)

  6. Development of an equipment diagnostic system that evaluates sensor drift

    International Nuclear Information System (INIS)

    Kanada, Masaki; Arita, Setsuo; Tada, Nobuo; Yokota, Katsuo

    2011-01-01

    The importance of condition monitoring technology for equipment has increased with the introduction of condition-based maintenance in nuclear power plants. We are developing a diagnostic system using process signals for plant equipment, such as pumps and motors. It is important to enable the diagnostic system to distinguish sensor drift and equipment failure. We have developed a sensor drift diagnostic method that combines some highly correlative sensor signals by using the MT (Mahalanobis-Taguchi) method. Furthermore, we have developed an equipment failure diagnostic method that measures the Mahalanobis distance from the normal state of equipment by the MT method. These methods can respectively detect sensor drift and equipment failure, but there are the following problems. In the sensor drift diagnosis, there is a possibility of misjudging the sensor drift when the equipment failure occurs and the process signal changes because the behavior of the process signal is the same as that of the sensor drift. Oppositely, in the equipment failure diagnosis, there is a possibility of misjudging the equipment failure when the sensor drift occurs because the sensor drift influences the change of process signal. To solve these problems, we propose a diagnostic method combining the sensor drift diagnosis and the equipment failure diagnosis by the MT method. Firstly, the sensor drift values are estimated by the sensor drift diagnosis, and the sensor drift is removed from the process signal. It is necessary to judge the validity of the estimated sensor drift values before removing the sensor drift from the process signal. We developed a method for judging the validity of the estimated sensor drift values by using the drift distribution based on the sensor calibration data. And then, the equipment failure is diagnosed by using the process signals after removal of the sensor drifts. To verify the developed diagnostic system, several sets of simulation data based on abnormal cases

  7. Development of KSC program for investigating and generating field failure rates. Volume 2: Recommended format for reliability handbook for ground support equipment

    Science.gov (United States)

    Bloomquist, C. E.; Kallmeyer, R. H.

    1972-01-01

    Field failure rates and confidence factors are presented for 88 identifiable components of the ground support equipment at the John F. Kennedy Space Center. For most of these, supplementary information regarding failure mode and cause is tabulated. Complete reliability assessments are included for three systems, eight subsystems, and nine generic piece-part classifications. Procedures for updating or augmenting the reliability results presented in this handbook are also included.

  8. Improved GLR method to instrument failure detection

    International Nuclear Information System (INIS)

    Jeong, Hak Yeoung; Chang, Soon Heung

    1985-01-01

    The generalized likehood radio(GLR) method performs statistical tests on the innovations sequence of a Kalman-Buchy filter state estimator for system failure detection and its identification. However, the major drawback of the convensional GLR is to hypothesize particular failure type in each case. In this paper, a method to solve this drawback is proposed. The improved GLR method is applied to a PWR pressurizer and gives successful results in detection and identification of any failure. Furthmore, some benefit on the processing time per each cycle of failure detection and its identification can be accompanied. (Author)

  9. The Caregiver Contribution to Heart Failure Self-Care (CACHS): Further Psychometric Testing of a Novel Instrument.

    Science.gov (United States)

    Buck, Harleah G; Harkness, Karen; Ali, Muhammad Usman; Carroll, Sandra L; Kryworuchko, Jennifer; McGillion, Michael

    2017-04-01

    Caregivers (CGs) contribute important assistance with heart failure (HF) self-care, including daily maintenance, symptom monitoring, and management. Until CGs' contributions to self-care can be quantified, it is impossible to characterize it, account for its impact on patient outcomes, or perform meaningful cost analyses. The purpose of this study was to conduct psychometric testing and item reduction on the recently developed 34-item Caregiver Contribution to Heart Failure Self-care (CACHS) instrument using classical and item response theory methods. Fifty CGs (mean age 63 years ±12.84; 70% female) recruited from a HF clinic completed the CACHS in 2014 and results evaluated using classical test theory and item response theory. Items would be deleted for low (.95) endorsement, low (.7) corrected item-total correlations, significant pairwise correlation coefficients, floor or ceiling effects, relatively low latent trait and item information function levels ( .5), and differential item functioning. After analysis, 14 items were excluded, resulting in a 20-item instrument (self-care maintenance eight items; monitoring seven items; and management five items). Most items demonstrated moderate to high discrimination (median 2.13, minimum .77, maximum 5.05), and appropriate item difficulty (-2.7 to 1.4). Internal consistency reliability was excellent (Cronbach α = .94, average inter-item correlation = .41) with no ceiling effects. The newly developed 20-item version of the CACHS is supported by rigorous instrument development and represents a novel instrument to measure CGs' contribution to HF self-care. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  10. Research on Application of FMECA in Missile Equipment Maintenance Decision

    Science.gov (United States)

    Kun, Wang

    2018-03-01

    Fault mode effects and criticality analysis (FMECA) is a method widely used in engineering. Studying the application of FMEA technology in military equipment maintenance decision-making, can help us build a better equipment maintenance support system, and increase the using efficiency of weapons and equipment. Through Failure Modes, Effects and Criticality Analysis (FMECA) of equipment, known and potential failure modes and their causes are found out, and the influence on the equipment performance, operation success, personnel security are determined. Furthermore, according to the synthetical effects of the severity of effects and the failure probability, possible measures for prevention and correction are put forward. Through replacing or adjusting the corresponding parts, corresponding maintenance strategy is decided for preventive maintenance of equipment, which helps improve the equipment reliability.

  11. Determination of water chemistry parameters which influence on failure intensity of RBMK equipment

    Energy Technology Data Exchange (ETDEWEB)

    Kovalev, S.M.; Kritski, V.G.; Berezina, I.G.; Stjazhkin, P.S.; Olejnik, P.V. [All-Russian Design and Scientific Research Inst. of Complex Power Technology (VNIPIET), St. Petersburg (Russian Federation)

    2002-07-01

    The coolant quality has an effect on intensity of austenitic stainless steel intergranular corrosion. The correlation between rate of intergranular stress corrosion cracking and water electro-conductivity (on generalized data) for non-stabilized stainless steel 304SS type and stabilized stainless steel X18H10T type is shown in Fig. 1. The cracking rate is increased with electro-conductivity rise and this is equivalently to reduction of pipelines lifetime, increase of amount and depth of cracks in welds. The increased values of water electro-conductivity correspond to high concentrations of iron corrosion product, corrosion-active anions (chlorides, sulphates et. al.), arrived to circulation circuit due to failure of equipment elements, for example, of condenser tubes or during start-up. (author)

  12. Cooling of electronic equipment

    DEFF Research Database (Denmark)

    A. Kristensen, Anders Schmidt

    2003-01-01

    Cooling of electronic equipment is studied. The design size of electronic equipment decrease causing the thermal density to increase. This affect the cooling which can cause for example failures of critical components due to overheating or thermal induced stresses. Initially a pin fin heat sink...

  13. Instrumentation Cables Test Plan

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-01

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

  14. Nuclear equipment recalsification based on the service experience

    International Nuclear Information System (INIS)

    Geambasu, A.; Segarceanu, D.

    2000-01-01

    The paper presents some considerations concerning the need of comparison between equipment performance proven by test and the service experience in Cernavoda Nuclear Plant. Service performance dana obtain partly from service failures (failures times) and partly from service experience without failure (running times) can be statistically analyzed to obtain predictions of the number of failures of unfailed units in specified period of time, means time to first failure, means time of median failure, a.s.o. These informations can be used during the operation of Nuclear Power Plant to estimate when a equipment should be replaced with a new one in order to prevent getting to the life end point. (author)

  15. Non-process instrumentation surveillance and test reduction

    International Nuclear Information System (INIS)

    Ferrell, R.; LeDonne, V.; Donat, T.; Thomson, I.; Sarlitto, M.

    1993-12-01

    Analysis of operating experience, instrument failure modes, and degraded instrument performance has led to a reduction in Technical Specification surveillance and test requirements for nuclear power plant process instrumentation. These changes have resulted in lower plant operations and maintenance (O ampersand M) labor costs. This report explores the possibility of realizing similar savings by reducing requirements for non-process instrumentation. The project team reviewed generic Technical Specifications for the four major US nuclear steam supply system (NSSS) vendors (Westinghouse, General Electric, Combustion Engineering, and Babcock ampersand Wilcox) to identify nonprocess instrumentation for which surveillance/test requirements could be reduced. The team surveyed 10 utilities to identify specific non-process instrumentation at their plants for which requirements could be reduced. The team evaluated utility analytic approaches used to justify changes in surveillance/test requirements for process equipment to determine their applicability to non-process instrumentation. The report presents a prioritized list of non-process instrumentation systems suitable for surveillance/test requirements reduction. The top three systems in the list are vibration monitors, leak detection monitors, and chemistry monitors. In general, most non-process instrumentation governed by Technical Specification requirements are candidates for requirements reduction. If statistical requirements are somewhat relaxed, the analytic approaches previously used to reduce requirements for process instrumentation can be applied to non-process instrumentation. The report identifies as viable the technical approaches developed and successfully used by Southern California Edison, Arizona Public Service, and Boston Edison

  16. Program plan for correction of US instrument degradation or failure in the Upper Plenum Test Facility (UPTF) in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Rhee, G.S.; Chen, Y.S.; Shotkin, L.M.

    1987-07-01

    This report documents, as of September, 1986, the investigation of the failure or degradation of some of the advanced two-phase flow instruments supplied by the United States Nuclear Regulatory Commission (USNRC) to the German Upper Plenum Test Facility (UPTF). These instruments include Tie-Plate Drag Bodies (DBs), Breakthrough Detectors (BTDs), Loop Drag Disc (DD) paddles, Fluid Distribution Grid (FDG) sensors, and Liquid Level Detector (LLD) sensors. The exact causes for these instrument degradations or failures are not known, but several potential causes have been identified. For DBs and BTDs, the primary mechanism for the degradation appears to be a leakage in the Inconel 600 strain gage encapsulation and the subsequent burnout of the strain gage elements. Excessive loads appear to be the cause of the degradation or failure of the drag discs. The degradation cause for most of the FDGs and LLDs may be either steam/water erosion or mechanical abrasion of the sapphire sensor tips. However, some of the FDG tips were found to be cracked also. The corrective actions are being directed towards identification of the primary causes for the instrument degradation or failure and methods of preventing recurrance and toward minimizing the impact on the test program. All possible action items are being reviewed to arrange them in terms of priority and the likelihood of success so that the best results can be obtained under the constraints of a fixed amount of resources and limited time

  17. Case Based Asset Maintenance for the Electric Equipment

    International Nuclear Information System (INIS)

    Kim, Ji-Hyeon; Jung, Jae-Cheon; Chang, Young-Woo; Chang, Hoon-Seon; Kim, Jae-Cheol; Kim, Hang-Bae; Kim, Kyu-Ho; Hur, Yong; Lee, Dong-Chul

    2006-01-01

    The electric equipment maintenance strategies are changing from PM(Preventive Maintenance) or CM(Corrective Maintenance) to CBM(Condition Based Maintenance). The main benefits of CBM are reduced possibility of service failures of critical equipment and reduced costs or maintenance work. In CBM, the equipment status need to be monitored continuously and a decision should be made whether an equipment need to be repaired or replaced. For the maintenance decision making, the CBR(Case Base Reasoning) system is introduced. The CBR system receives the current equipment status and retrieves the case based historic database to determine any possible equipment failure under current conditions. In retrieving the case based historic data, the suggested DSS(Decision Support System) uses a reasoning engine with an equipment/asset ontology that describes the equipment subsumption relationships

  18. To Strengthen the Instrument and Equipment Management of Laboratories in Colleges and Universities%加强实验室仪器设备的科学管理

    Institute of Scientific and Technical Information of China (English)

    李培天

    2001-01-01

    高等学校实验室仪器设备管理水平的高低对教学质量和办学效益的好坏有直接影响。管理得好,就会充分发挥其作用,提高教学质量和办学效益;否则,就会闲置浪费,甚至造成损失。%The instrument and equipment management of laboratories in colleges and universities directly affectsthe quality of teaching and the benefit of running a school. With good management, the instrument and equipment will be brought into full play, therefore improve the quality of teaching and the benefit of running aschool; otherwise, the instrument and equipment will be lain idle and wasted even lost to some extent.

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

    International Nuclear Information System (INIS)

    1989-01-01

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

  20. Low-rise shear wall failure modes

    International Nuclear Information System (INIS)

    Farrar, C.R.; Hashimoto, P.S.; Reed, J.W.

    1991-01-01

    A summary of the data that are available concerning the structural response of low-rise shear walls is presented. This data will be used to address two failure modes associated with the shear wall structures. First, data concerning the seismic capacity of the shear walls with emphasis on excessive deformations that can cause equipment failure are examined. Second, data concerning the dynamic properties of shear walls (stiffness and damping) that are necessary to compute the seismic inputs to attached equipment are summarized. This case addresses the failure of equipment when the structure remains functional. 23 refs

  1. The qualification of electrical components and instrumentations relevant to safety

    CERN Document Server

    Zambardi, F

    1989-01-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and ...

  2. Failure mode taxonomy for assessing the reliability of Field Programmable Gate Array based Instrumentation and Control systems

    International Nuclear Information System (INIS)

    McNelles, Phillip; Zeng, Zhao Chang; Renganathan, Guna; Chirila, Marius; Lu, Lixuan

    2017-01-01

    Highlights: • The use FPGAs in I&C systems in Nuclear Power Plants is an important issue (IAEA). • OECD-NEA published a failure mode taxonomy for software-based digital I&C systems. • This paper extends the OECD-NEA taxonomy to model FPGA-based systems. • FPGA failure modes, failure effects, uncovering methods are categorized/described. • Provides an example of modelling an FPGA-Based RTS/ESFAS using the FPGA taxonomy. - Abstract: Field Programmable Gate Arrays (FPGAs) are a form of programmable digital hardware configured to perform digital logic functions. This configuration (programming) is performed using Hardware Description Language (HDL), making FPGAs a form of HDL Programmed Device (HPD). In the nuclear field, FPGAs have seen use in upgrades and replacements of obsolete Instrumentation and Control (I&C) systems. This paper expands upon previous work that resulted in extensive FPGA failure mode data, to allow for the application of the OECD-NEA failure modes taxonomy. The OECD-NEA taxonomy presented a method to model digital (software-based) I&C systems, based on the hardware and software failure modes, failure uncovering effects and levels of abstraction, using a Reactor Trip System/Engineering Safety Feature Actuation System (RTS/ESFAS) as an example system. To create the FPGA taxonomy, this paper presents an additional “sub-component” level of abstraction, to demonstrate the effect of the FPGA failure modes and failure categories on an FPGA-based system. The proposed FPGA taxonomy is based on the FPGA failure modes, failure categories, failure effects and uncovering situations. The FPGA taxonomy is applied to the RTS/ESFAS test system, to demonstrate the effects of the anticipated FPGA failure modes on a digital I&C system, and to provide a modelling example for this proposed taxonomy.

  3. Smart instrumentation development at Los Alamos

    International Nuclear Information System (INIS)

    Erkkila, B.

    1984-01-01

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

  4. Failure modes of low-rise shear walls

    International Nuclear Information System (INIS)

    Farrar, C.R.; Reed, J.W.; Salmon, M.W.

    1993-01-01

    A summary of available data concerning the structural response of low-rise shear walls is presented. These data will be used to address two failure modes associated with shear wall structures. First, the data concerning the seismic capacity of the shear walls are examined, with emphasis on excessive deformations that can cause equipment failure. Second, the data concerning the dynamic properties of shear walls (stiffness and damping) that are necessary for computing the seismic inputs to attached equipment are summarized. This case addresses the failure of equipment when the structure remains functional

  5. The methodology of root cause analysis for equipment failure and its application at Guangdong nuclear power stations

    International Nuclear Information System (INIS)

    Gao Ligang; Lu Qunxian

    2004-01-01

    The methodology of Equipment Failure Root Cause Analysis (RCA) is described, as a systematic analysis methodology, it includes 9 steps. Its process is explained by some real examples, and the 6 precautions applying RCA is pointed out. The paper also summarizes the experience of RCA application at Daya Bay Nuclear Power Station, and the 7 key factors for RCA success is emphasized, that mainly concerns organization, objective, analyst, analysis technique, external technical supporting system, corrective actions developing and monitoring system for corrective actions. (authors)

  6. On-line testing of nuclear plant temperature and pressure instrumentation and other critical plant equipment. IAEA regional workshop. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    Under European regional TC project RER/4/011, IAEA and VUJE Training centre organized a workshop on On-line Testing of Nuclear Power Plant Temperature and Pressure Instrumentation and Other Critical Plant Equipment in Trnava, Slovak Republic, from 25 to 29 May 1998. The objective of the workshop was to review the state-of-the-art in NPP instrumentation, cover typical instrumentation problems and solutions, describe technical and regulatory requirements for verifying the performance of nuclear power plant instrumentation, describe new methods developed and applied in NPPs for on-line verification and performance of instrumentation and present new techniques using existing instrumentation to identify the on-set problems in the plant electrical, mechanical and thermal hydraulic systems. Particular emphasis was placed on temperature measurements by Resistance Temperature Detectors (RTDs) and thermocouples and pressure measurements using motion-balanced and forced-balanced pressure transmitters. This proceedings includes papers presented by the invited speakers and the participants each with an abstract as wells as a summary of the Round-Table discussions Refs, figs, tabs

  7. On-line testing of nuclear plant temperature and pressure instrumentation and other critical plant equipment. IAEA regional workshop. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Under European regional TC project RER/4/011, IAEA and VUJE Training centre organized a workshop on On-line Testing of Nuclear Power Plant Temperature and Pressure Instrumentation and Other Critical Plant Equipment in Trnava, Slovak Republic, from 25 to 29 May 1998. The objective of the workshop was to review the state-of-the-art in NPP instrumentation, cover typical instrumentation problems and solutions, describe technical and regulatory requirements for verifying the performance of nuclear power plant instrumentation, describe new methods developed and applied in NPPs for on-line verification and performance of instrumentation and present new techniques using existing instrumentation to identify the on-set problems in the plant electrical, mechanical and thermal hydraulic systems. Particular emphasis was placed on temperature measurements by Resistance Temperature Detectors (RTDs) and thermocouples and pressure measurements using motion-balanced and forced-balanced pressure transmitters. This proceedings includes papers presented by the invited speakers and the participants each with an abstract as wells as a summary of the Round-Table discussions

  8. Virtual Instrumentation in Biomedical Equipment

    Directory of Open Access Journals (Sweden)

    Tiago Faustino Andrade

    2013-01-01

    Full Text Available Nowadays, the assessment of body composition by estimating the percentage of body fat has a great impact in many fields such as nutrition, health, sports, chronic diseases and others. The main purpose for this work is the development of a virtual instrument that permits more effective assessment of body fat, automatic data processing, recording results and storage in a database, with high potential to conduct new studies, http://lipotool.com.

  9. FUNDAMENTALS OF RELIABILITY OF ELECTRIC POWER SYSTEM AND EQUIPMENT

    OpenAIRE

    Engr. Anumaka; Michael Chukwukadibia

    2011-01-01

    Today, the electric power system consists of complex interconnected network which are prone to different problems that militates against the reliability of the power system. Inadequate reliability in the power system causes problems such as high failure rate of power system installations and consumer equipment, transient and intransient faults, symmetrical faults etc. This paper provides an extensive review of the powers system and equipment reliability and related failure patterns in equipment.

  10. Renewal of radiological equipment.

    Science.gov (United States)

    2014-10-01

    In this century, medical imaging is at the heart of medical practice. Besides providing fast and accurate diagnosis, advances in radiology equipment offer new and previously non-existing options for treatment guidance with quite low morbidity, resulting in the improvement of health outcomes and quality of life for the patients. Although rapid technological development created new medical imaging modalities and methods, the same progress speed resulted in accelerated technical and functional obsolescence of the same medical imaging equipment, consequently creating a need for renewal. Older equipment has a high risk of failures and breakdowns, which might cause delays in diagnosis and treatment of the patient, and safety problems both for the patient and the medical staff. The European Society of Radiology is promoting the use of up-to-date equipment, especially in the context of the EuroSafe Imaging Campaign, as the use of up-to-date equipment will improve quality and safety in medical imaging. Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or renewal. This plan should look forward a minimum of 5 years, with annual updates. Teaching points • Radiological equipment has a definite life cycle span, resulting in unavoidable breakdown and decrease or loss of image quality which renders equipment useless after a certain time period.• Equipment older than 10 years is no longer state-of-the art equipment and replacement is essential. Operating costs of older equipment will be high when compared with new equipment, and sometimes maintenance will be impossible if no spare parts are available.• Older equipment has a high risk of failure and breakdown, causing delays in diagnosis and treatment of the patient and safety problems both for the patient and the medical staff.• Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or replacement. This plan should look forward a

  11. Improved methods for dependent failure analysis in PSA

    International Nuclear Information System (INIS)

    Ballard, G.M.; Games, A.M.

    1988-01-01

    The basic design principle used in ensuring the safe operation of nuclear power plant is defence in depth. This normally takes the form of redundant equipment and systems which provide protection even if a number of equipment failures occur. Such redundancy is particularly effective in ensuring that multiple, independent equipment failures with the potential for jeopardising reactor safety will be rare events. However the achievement of high reliability has served to highlight the potentially dominant role of multiple, dependent failures of equipment and systems. Analysis of reactor operating experience has shown that dependent failure events are the major contributors to safety system failures and reactor incidents and accidents. In parallel PSA studies have shown that the results of a safety analysis are sensitive to assumptions made about the dependent failure (CCF) probability for safety systems. Thus a Westinghouse Analysis showed that increasing system dependent failure probabilities by a factor of 5 led to a factor 4 increase in core. This paper particularly refers to the engineering concepts underlying dependent failure assessment touching briefly on aspects of data. It is specifically not the intent of our work to develop a new mathematical model of CCF but to aid the use of existing models

  12. Meeting the challenges of managing substation equipment assets

    Energy Technology Data Exchange (ETDEWEB)

    Shaver, J. [CEA Technologies (Canada)

    2005-06-01

    Best practices for monitoring and assessing substation equipment are discussed. Scheduled time-based maintenance is the most common, but recent evidence indicates that despite it being the most expensive, it may not always identify potential failures. The author recommends developing decision-making tools that take into account obsolescence, reliability, safety and environmental issues, as well as operating, repair and carrying costs, as absolutely necessary for consistent and intelligent decision-making. Given the high cost of research, the author recommends developing such tools through pooling of skills and collaboration with other utilities, as the preferred way to develop best practices. The Life Cycle Management of Substation Equipment and Apparatus Interest Group of CEA Technologies Inc is one such group that was formed to help utilities facilitate their research and technology development endeavours. The group's current focus is on developing equipment diagnostics and life optimization through the development of validation tools for predicting remaining life and/or extending life. Brief descriptions of these, and other completed project are given. Completed projects described include developing tools for predicting remaining life of transformers, power connectors and disconnect switches, safety protocol for restoration of substations involved with fires/explosions, and compiling a critical review of diagnostic instruments designed to assess transformer conditions.

  13. Equipment support for the implementation of safeguards

    International Nuclear Information System (INIS)

    Arlt, R.; Bosler, G.; Goldfarb, M.; Schanfein, M.; Whichello, J.

    2001-01-01

    Full text: The provision of effective, reliable, and user-friendly equipment needed for the implementation of safeguards is one of the main objectives of the Division of Technical Services (SOTS) in the Department of Safeguards. As an outcome of a review by an independent external consultant firm, the instrumentation sections of the SGTS were reorganized in January 2001 into two new sections, the Section for NDA Systems and Seals (TNS) and Section for Installed Systems (TIE). Each section has 'cradle-to-grave' responsibilities for development, implementation, maintenance, and decommissioning of safeguards instruments and measurement systems. Unattended assay, monitoring and surveillance instruments are the responsibility of TIE while attended nondestructive assay (NDA) instruments and seals are handled by TNS. The principal goals of both sections are to define equipment requirements based on Departmental needs, to coordinate Support Programme tasks concerning development and implementation activities, to provide system engineering of commercial components, manage laboratory and to do field testing and prove system suitability for defined safeguards applications. In addition both sections coordinate equipment and supply needs for the Department, including acquisition, preparation, servicing, installation, commissioning, troubleshooting, maintenance and repair, ensuring their availability when needed. As required, TIE and TNS provide specialized field support to the Operations Divisions. Each section is working to standardize equipment as much as possible and reduce the number of instruments performing the same function. This reduces both inspector and technician training, required parts inventories, and overall life-cycle costs. Development based on User Needs from the Operations Divisions follows a strict quality control program that includes a thorough qualification testing procedure with the last phase being field-testing under actual facility conditions. A

  14. Reactor instrumentation. Definition of the single failure criterion

    International Nuclear Information System (INIS)

    1980-12-01

    The standard defines the single failure criterion which is used in other IEC publications on reactor safety systems. The purpose of the single failure criterion is the assurance of minimum redundancy. (orig./HP) [de

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

    International Nuclear Information System (INIS)

    Hecker, L.A.

    1982-01-01

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

  16. Expected damage to accelerator equipment due to the impact of the full LHC beam: beam instrumentation, experiments and simulations

    CERN Document Server

    Burkart, Florian

    The Large Hadron Collider (LHC) is the biggest and most powerful particle accelerator in the world, designed to collide two proton beams with particle momentum of 7 TeV/c each. The stored energy of 362MJ in each beam is sufficient to melt 500 kg of copper or to evaporate about 300 liter of water. An accidental release of even a small fraction of the beam energy can cause severe damage to accelerator equipment. Reliable machine protection systems are necessary to safely operate the accelerator complex. To design a machine protection system, it is essential to know the damage potential of the stored beam and the consequences in case of a failure. One (catastrophic) failure would be, if the entire beam is lost in the aperture due to a problem with the beam dumping system. This thesis presents the simulation studies, results of a benchmarking experiment, and detailed target investigation, for this failure case. In the experiment, solid copper cylinders were irradiated with the 440GeV proton beam delivered by the ...

  17. On the basic research of design analysis and testing based on the failure rate for pipings and equipment under earthquake conditions

    International Nuclear Information System (INIS)

    Shibata, H.

    1980-01-01

    This paper deals with the evaluation method of the failure rate of pipings and equipment of nuclear power plants under destructive earthquakes and a new design concept in this stand point of view. These researches are supported by various studies related to this subject, which have been done by the author since 1966. In this paper, the history of the development, the summaries of these studies and their significances to the practice will be described briefly. The surveys on damages of industrial facilities caused by recent destructive earthquakes are the basical study for this subject. And the continuous response observation of model structures of a plant complex to natural earthquakes is another important basic study to know the stochastic nature and significance of response analysis for the anti-earthquake design of nuclear power plants. By having the exact knowledges on these subjects, the author has been developing the evaluation procedure of the failure rate of pipings and equipment under destructive earthquake conditions, a new design method 'counter-input design' and others. Now his effort is going towards establishing their practical procedure after finishing the basic researches. (orig.)

  18. Reliability performance of standby equipment with periodic testing

    International Nuclear Information System (INIS)

    Sim, S.H.

    1985-11-01

    In this report, the reliability performance of standby equipment subjected to periodic testing is studied. analytical expressions have been derived for reliability measures, such as the man accumulated operating time to failure, the expected number of tests between two consecutive failures, the mean time to failure following an emergency start-up and the probability of failing to complete an emergency mission of a specified duration. These results are useful for the reliability assessment of standby equipment such as combustion turbine units of the emergency power supply system, and of the Class III power system at a nuclear generating station

  19. 33 CFR 105.250 - Security systems and equipment maintenance.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Security systems and equipment... systems and equipment maintenance. (a) Security systems and equipment must be in good working order and... include procedures for identifying and responding to security system and equipment failures or...

  20. 33 CFR 104.260 - Security systems and equipment maintenance.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Security systems and equipment... systems and equipment maintenance. (a) Security systems and equipment must be in good working order and... procedures for identifying and responding to security system and equipment failures or malfunctions. ...

  1. Criticality safety concerns of uranium deposits in cascade equipment

    International Nuclear Information System (INIS)

    Plaster, M.J.

    1996-01-01

    The Paducah and Portsmouth Gaseous Diffusion Plants enrich uranium in the 235 U isotope by diffusing gaseous uranium hexafluoride (UF 6 ) through a porous barrier. The UF 6 gaseous diffusion cascade utilized several thousand open-quotes stagesclose quotes of barrier to produce highly enriched uranium (HEU). Historically, Portsmouth has enriched the Paducah Gaseous Diffusion Plant's product (typically 1.8 wt% 235 U) as well as natural enrichment feed stock up to 97 wt%. Due to the chemical reactivity of UF 6 , particularly with water, the formation of solid uranium deposits occur at a gaseous diffusion plant. Much of the equipment operates below atmospheric pressure, and deposits are formed when atmospheric air enters the cascade. Deposits may also be formed from UF 6 reactions with oil, UF 6 reactions with the metallic surfaces of equipment, and desublimation of UF 6 . The major deposits form as a result of moist air in leakage due to failure of compressor casing flanges, blow-off plates, seals, expansion joint convolutions, and instrument lines. This report describes criticality concerns and deposit disposition

  2. Origins of eponymous orthopaedic equipment.

    Science.gov (United States)

    Meals, Clifton; Wang, Jeffrey

    2010-06-01

    Orthopaedists make great use of eponymous equipment, however the origins of these tools are unknown to many users. This history enriches, enlightens, and enhances surgical education, and may inspire modern innovation. We explored the origins of common and eponymous orthopaedic equipment. We selected pieces of equipment named for their inventors and in the broadest use by modern orthopaedists. We do not describe specialized orthopaedic implants and instruments owing to the overwhelming number of these devices. The history of this equipment reflects the coevolution of orthopaedics and battlefield medicine. Additionally, these stories evidence the primacy of elegant design and suggest that innovation is often a process of revision and refinement rather than sudden inspiration. Their history exposes surgical innovators as brilliant, lucky, hardworking, and sometimes odd. These stories amuse, enlighten, and may inspire modern orthopaedists to develop creative solutions of their own. The rich history of the field's eponymous instruments informs an ongoing tradition of innovation in orthopaedics.

  3. Fuel failure detection and location methods in CAGRs

    International Nuclear Information System (INIS)

    Harris, A.M.

    1982-06-01

    The release of fission products from AGR fuel failures and the way in which the signals from such failures must be detected against the background signal from uranium contamination of the fuel is considered. Theoretical assessments of failure detection are used to show the limitations of the existing Electrostatic Wire Precipitator Burst Can Detection system (BCD) and how its operating parameters can be optimised. Two promising alternative methods, the 'split count' technique and the use of iodine measurements, are described. The results of a detailed study of the mechanical and electronic performance of the present BCD trolleys are given. The limited experience of detection and location of two fuel failures in CAGR using conventional and alternative methods is reviewed. The larger failure was detected and located using the conventional BCD equipment with a high confidence level. It is shown that smaller failures may not be easy to detect and locate using the current BCD equipment, and the second smaller failure probably remained in the reactor for about a year before it was discharged. The split count technique used with modified BCD equipment was able to detect the smaller failure after careful inspection of the data. (author)

  4. ISSUES ASSOCIATED WITH PROBABILISTIC FAILURE MODELING OF DIGITAL SYSTEMS

    International Nuclear Information System (INIS)

    CHU, T.L.; MARTINEZ-GURIDI, G.; LIHNER, J.; OVERLAND, D.

    2004-01-01

    The current U.S. Nuclear Regulatory Commission (NRC) licensing process of instrumentation and control (I and C) systems is based on deterministic requirements, e.g., single failure criteria, and defense in depth and diversity. Probabilistic considerations can be used as supplements to the deterministic process. The National Research Council has recommended development of methods for estimating failure probabilities of digital systems, including commercial off-the-shelf (COTS) equipment, for use in probabilistic risk assessment (PRA). NRC staff has developed informal qualitative and quantitative requirements for PRA modeling of digital systems. Brookhaven National Laboratory (BNL) has performed a review of the-state-of-the-art of the methods and tools that can potentially be used to model digital systems. The objectives of this paper are to summarize the review, discuss the issues associated with probabilistic modeling of digital systems, and identify potential areas of research that would enhance the state of the art toward a satisfactory modeling method that could be integrated with a typical probabilistic risk assessment

  5. Instrumentation Report No. 2: identification, evaluation, and remedial actions related to transducer failures at the spent fuel test-climax

    Energy Technology Data Exchange (ETDEWEB)

    Patrick, W.C.; Carlson, R.C.; Rector, N.L.

    1981-11-30

    The Spent Fuel Test-Climax (SFT-C) is a test of the feasibility of safe and reliable short-term storage and retrieval of spent fuel from commercial nuclear reactors. In support of operational and technical goals of the test, about 850 channels of instrumentation have been installed at the SFT-C. Failure of several near-field instruments began less than six months after emplacement of 11 canisters of spent fuel and activation of six thermally similar simulators. The failed units were linear potentiometers (used to make displacement measurements) and vibrating wire stressmeters (used to make change-in-stress measurements). This report discusses the observed problems and remedial actions taken to date.

  6. Instrumentation Report No. 2: identification, evaluation, and remedial actions related to transducer failures at the spent fuel test-climax

    International Nuclear Information System (INIS)

    Patrick, W.C.; Carlson, R.C.; Rector, N.L.

    1981-01-01

    The Spent Fuel Test-Climax (SFT-C) is a test of the feasibility of safe and reliable short-term storage and retrieval of spent fuel from commercial nuclear reactors. In support of operational and technical goals of the test, about 850 channels of instrumentation have been installed at the SFT-C. Failure of several near-field instruments began less than six months after emplacement of 11 canisters of spent fuel and activation of six thermally similar simulators. The failed units were linear potentiometers (used to make displacement measurements) and vibrating wire stressmeters (used to make change-in-stress measurements). This report discusses the observed problems and remedial actions taken to date

  7. Risk matrix model for rotating equipment

    Directory of Open Access Journals (Sweden)

    Wassan Rano Khan

    2014-07-01

    Full Text Available Different industries have various residual risk levels for their rotating equipment. Accordingly the occurrence rate of the failures and associated failure consequences categories are different. Thus, a generalized risk matrix model is developed in this study which can fit various available risk matrix standards. This generalized risk matrix will be helpful to develop new risk matrix, to fit the required risk assessment scenario for rotating equipment. Power generation system was taken as case study. It was observed that eight subsystems were under risk. Only vibration monitor system was under high risk category, while remaining seven subsystems were under serious and medium risk categories.

  8. Failure analysis – basic step of applying Reliability Centered Maintenance in general aviation

    Directory of Open Access Journals (Sweden)

    Martin BUGAJ

    2012-01-01

    Full Text Available Performing a reliability analysis on a product or system can actually include a number of different analyses to determine how reliable the product or system is. A reliability centered maintenance program consists of a set of scheduled tasks generated on the basis of specific reliability characteristics of the equipment they are designed to protect. Complex equipment is composed of a vast number of parts and assemblies. All these items can be expected to fail at one time or another, but some of the failures have more serious consequences than others. Certain kinds of failures have a direct effect on operating safety, and others affect the operational capability of the equipment. The consequences of a particular failure depend on the design of the item and the equipment in which it is installed. Although the environment in which the equipment is operated is sometimes an additional factor, the impact of failures on the equipment, and hence their consequences for the operating organization, are established primarily by the equipment designer. Failure consequences are therefore a primary inherent reliability characteristic.

  9. Electrical and control equipment in nuclear power plants. Problems when replacing aging equipment

    International Nuclear Information System (INIS)

    Nordling, Anna; Haakansson, Goeran

    2012-01-01

    Interoperability between different technical systems is more complicated when old and new technology meet, such as between analog and digital technology. New electrical and I and C equipment is selected with consideration to simplify and improve the compatibility and interoperability. The original construction of nuclear power plants with electricity and I and C equipment had more natural interfaces. Generally experienced guidance, to the management of interoperability and interfaces, feels insufficient. Skills transfer programs are identified as a major need, as more and more important personnel are retiring and important information is lost with them. Lack of appropriate skills directly affects the ability to produce accurate and complete requirements specification. Failure modes of newer electrical and I and C equipment are perceived as more complex than the older equipment. When choosing equipment, attempts are made to minimize unnecessary features, to reduce the number of potential failure modes. There is a lack of consistent understanding of the meaning of robustness in electrical technology and I and C technology, in the nuclear plant engineering departments. The overall picture is that the robustness has worsened since the facilities were built. The Swedish nuclear power plants have an internal organizational structure with separated client and support organization. This splits the nuclear organization into two distinct parts which threaten to separate the two entities focus. Engineering departments at the Swedish nuclear power plants express a need for increased expertise in the client organization (blocks). Competence requested is for example, system knowledge to facilitate and enhance the quality of the initial analysis performed in the blocks. Suppliers receive more recently larger turnkey projects, both to minimize costs but also to minimize the interfaces and co-function problems. This, however, heightens demands for knowledge transfer between

  10. Predictive Maintenance of Power Substation Equipment by Infrared Thermography Using a Machine-Learning Approach

    Directory of Open Access Journals (Sweden)

    Irfan Ullah

    2017-12-01

    Full Text Available A variety of reasons, specifically contact issues, irregular loads, cracks in insulation, defective relays, terminal junctions and other similar issues, increase the internal temperature of electrical instruments. This results in unexpected disturbances and potential damage to power equipment. Therefore, the initial prevention measures of thermal anomalies in electrical tools are essential to prevent power-equipment failure. In this article, we address this initial prevention mechanism for power substations using a computer-vision approach by taking advantage of infrared thermal images. The thermal images are taken through infrared cameras without disturbing the working operations of power substations. Thus, this article augments the non-destructive approach to defect analysis in electrical power equipment using computer vision and machine learning. We use a total of 150 thermal pictures of different electrical equipment in 10 different substations in operating conditions, using 300 different hotspots. Our approach uses multi-layered perceptron (MLP to classify the thermal conditions of components of power substations into “defect” and “non-defect” classes. A total of eleven features, which are first-order and second-order statistical features, are calculated from the thermal sample images. The performance of MLP shows initial accuracy of 79.78%. We further augment the MLP with graph cut to increase accuracy to 84%. We argue that with the successful development and deployment of this new system, the Technology Department of Chongqing can arrange the recommended actions and thus save cost in repair and outages. This can play an important role in the quick and reliable inspection to potentially prevent power substation equipment from failure, which will save the whole system from breakdown. The increased 84% accuracy with the integration of the graph cut shows the efficacy of the proposed defect analysis approach.

  11. Nuclear electronic equipment for control and monitoring panel. Procedure guide for on-site tests of nuclear reactor instruments

    International Nuclear Information System (INIS)

    1975-10-01

    By the use of a procedure for on-site testing of nuclear reactor instruments it should be possible to judge their ability to guarantee the reactor safety and availability at the moment of divergence or during operation. Such a procedure must therefore be created as a work implement for the quick and reliable installation of electronic devices necessary for nuclear reactor control and supervision. A standard document is proposed for this purpose, allowing a ''test programme'' to be set up before the equipment is installed on the site [fr

  12. Report of the Instrumentation Service - Annex C

    International Nuclear Information System (INIS)

    Mikic, N.; Majstorovic, D.

    1993-01-01

    This report describes the tasks and organizational structure of the Instrumentation service. The most important task of this Service is control and maintenance of the reactor control and protection instruments, operation control, and dosimetry system. Besides data about this basic instrumentation, the report includes data about control and maintenance of other electronic equipment, inspection of the reactor vessel and spent fuel storage pool and describes activities related to renewal of the equipment [sr

  13. Report of the Instrumentation Service - Annex C

    International Nuclear Information System (INIS)

    Majstorovic, D.

    1986-01-01

    This report describes the tasks and organizational structure of the Instrumentation service. The most important task of this Service is control and maintenance of the reactor control and protection instruments, operation control, and dosimetry system. Besides data about this basic instrumentation, the report includes data about control and maintenance of other electronic equipment, inspection of the reactor vessel and spent fuel storage pool and describes activities related to renewal of the equipment [sr

  14. Report of the Instrumentation Service - Annex C

    International Nuclear Information System (INIS)

    Majstorovic, D.

    1988-01-01

    This report describes the tasks and organizational structure of the Instrumentation service. The most important task of this Service is control and maintenance of the reactor control and protection instruments, operation control, and dosimetry system. Besides data about this basic instrumentation, the report includes data about control and maintenance of other electronic equipment, inspection of the reactor vessel and spent fuel storage pool and describes activities related to renewal of the equipment [sr

  15. Improvements and Revamping of In-Core Instrumentation Systems

    International Nuclear Information System (INIS)

    Garam, Eric De

    1993-01-01

    The results of the improvements done by Fumarate Tia in these domains are really satisfying and it is clear that the problems of leakage existing in the old units on the thermocouples sealing systems and on the seal table of the income instrumentation, cannot exist on the French Units or on the units equipped with Fumarate Tia equipment. At the same time, all the equipment which constitute the Income instrumentation have been improved with the aim of reliability and safety. The equipment used to perform maintenance activities has also been improved to both reduce doses and increase efficiency. The purpose of this paper is to describe the principal improvements and revamping of income instrumentation systems, and to summarize the principal lessons learned from our experience on all designs of PWR. Fumarate Tia, is permanently looking for improving the existing systems of instrumentation with the aim of reduction of the dosimetry during the maintenance services, improvement of the liability and lifetime of the equipment, and of course reduction of the duration of the outages in keeping always the same level of quality

  16. Safety concepts and their implications with respect to systems, instrumentation (automatic) control and hardware

    International Nuclear Information System (INIS)

    Paziaud, A.; Walther, M.

    1982-01-01

    This overview of instrumentation and control in the French Nuclear Power Plants sets out the importance of safety requirements. As a matter of fact, the amount of equipment increases proportionally to the increase in safety requirements, resulting in higher costs in spite of the decrease in the prices of each component owing to the advance in electronics. However the improved reliability should improve the plant capacity factor and, as a consequence, improve both the power output and the safety which is often endangered by minor failures starting severe accidents. (orig.)

  17. Availability analysis of the nuclear instrumentation of a research reactor; Analise da disponibilidade da instrumentacao nuclear de um reator de pesquisa

    Energy Technology Data Exchange (ETDEWEB)

    Vianna Filho, Alfredo Marques

    2016-07-01

    The maintenance of systems and equipment is a central question related to Production Engineering. Although systems are not fully reliable, it is often necessary to minimize the failure occurrence likelihood. The failures occurrences can have disastrous consequences during a plane flight or operation of a nuclear power plant. The elaboration of a maintenance plan has as objective the prevention and recovery from system failures, increasing reliability and reducing the cost of unplanned shutdowns. It is also important to consider the issues related to organizations safety, especially those dealing with dangerous technologies. The objective of this thesis is to propose a method for maintenance analysis of a nuclear research reactor, using a socio-technical approach, and focused on existing conditions in Brazil. The research reactor studied belongs to the federal government and it is located in the city of Rio de Janeiro. The specific objective of this thesis is to develop the availability analysis of one of the principal systems of the research reactor, the nuclear instrumentation system. In this analysis, were taken into account not only the technical aspects of the modules related to nuclear instrumentation system, but also the human and organizational factors that could affect the availability of the nuclear instrumentation system. The results showed the influence of these factors on the availability of the nuclear instrumentation system. (author)

  18. Field instrumentation for hydrofracturing stress measurements

    International Nuclear Information System (INIS)

    Bjarnason, Bjarni; Torikka, Arne.

    1989-08-01

    A recently developed system for rock stress measurements by the hydraulic fracturing method is documented in detail. The new equipment is intended for measurement in vertical or nearvertical boreholes, down to a maximum depth of 1000 m. The minimum borehole, diameter required is 56 mm. Downhole instrumentation comprises a straddle packer assembly for borehole fracturing, equipment for determination of fracture orientations and a pressure transducer. The downhole tools are operated by means of a multihose system, containing high pressure hydraulic tubings, signal cable and carrying wire into one hose unit. The surface components of the equipment include a system for generation and control of water pressures up to approximately 75 MPa, an hydraulically operated drum for the multihose and a data acquisition system. All surface instrumentation is permanently mounted on a truck, which also serves as power source for the instrumentation. In addition to the description of instrumentation, the theoretical fundament and the testing procedures associated with the hydraulic fracturing method are briefly outlined

  19. Review of failures in nuclear air cleaning systems (1975--1978)

    International Nuclear Information System (INIS)

    Moeller, D.W.

    1979-01-01

    During the period from January 1, 1975 through June 30, 1978, over 9,000 Licensee Event Reports (LERs) pertaining to the operation of commercial light water nuclear power plants in the US were reported to the Nuclear Regulatory Commission. Of these reports, over 1,200 (approximately 13%) pertained to failures in air monitoring, ventilating and cleaning systems. For BWR installations, over half of the reported events related to failures in equipment for monitoring the performance of air cleaning systems as contrasted to failures in the systems themselves. In PWR installations, failures in monitoring equipment amounted to about 32% of the total. Reported problem areas in BWR installations included the primary containment and standby gas treatment and off-gas systems, as well as the High Pressure Coolant Injection and Reactor Core Isolation Systems. For PWR installations, reported problem areas included primary containment and associated spray systems and waste processing equipment. Although data on reported failures in power reactor installations can be interpreted in a variety of ways, one message is clear. There is a need for research on the development of more reliable equipment for sampling and monitoring air systems. Equipment that provides inaccurate data on the performance of such systems can lead to as many problems as inadequacies in the systems themselves

  20. Handbook on care, handling and protection of nuclear medicine instruments

    International Nuclear Information System (INIS)

    2000-11-01

    Instruments are fundamental to successful nuclear medicine practice. They must be properly installed in an environment in which they can give accurate and uninterrupted service. They have to be properly and carefully operated and supported throughout their life by regular care and maintenance. If something is wrong with a key instrument all well trained staff members are idle and all purchased radiopharmaceuticals become useless. Overall responsibility for instrumentation rests with the directors of nuclear medicine centres. They should support their electronic engineers, medical physicists, technologists and physicians to plan and implement the care and protection of nuclear medicine instruments, see that they are properly maintained, and kept in optimum working condition by regular checks. Protection should be considered, and provided for, before installing any new instrument. The protective devices are part of the new installation and should be well maintained along with the instrument throughout its life. Thus protection needs careful planning, particularly at the beginning of a new instrumentation programme. It can affect selection, procurement, acceptance testing, and the design of quality control and maintenance routines. These activities should be considered as important in their own right. They should not be mixed in with other functions or left to take care of themselves in the daily rush to get through routine work. Experience suggests that more than half of all failures of electronic equipment are due to damage by external electrical disturbances. Section 2 of this handbook aims to help instrument users in nuclear medicine centres to understand the nature of the various types of disturbance, and to protect against them. Section 3 shows how air conditioning can help to protect instrumentation. Section 4 lists some practical tips to avoid accidental damage due to mishandling. A computer program for use with Personal Computers, ''EPC Expert'' is described

  1. An equipment complex for instrumental elementary analysis

    International Nuclear Information System (INIS)

    Borisov, G.I.; Komkov, M.M.; Kuz'michev, V.A.; Leonov, V.F.; Tarasov, Y.F.

    1986-01-01

    The competitiveness of elementary analysis on a research reactor depends, in many respects, on the provision of equipment which would permit the realization of the advantages of the analytical method. This paper describes the IR-8 reactor at the I.V. Kurchatov Institute of Atomic energy. In the design of the complex considerable attention was focused on automation and the radiation safety of the operations, which is of particular importance in the light of the large volumes of analysis

  2. Some emergency instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    Burgess, P H

    1986-10-01

    The widespread release of activity and the resultant spread of contamination after the Chernobyl accident resulted in requests to NRPB to provide instruments for, and expertise in, the measurement of radiation. The most common request was for advice on the usefulness of existing instruments, but Board staff were also involved in their adaptation or in the development of new instruments specially to meet the circumstances of the accident. The accident occurred on 26 April. On 1 May, NRPB was involved at Heathrow Airport in the monitoring of the British students who had returned from Kiev and Minsk. The main purpose was to reassure the students by checking that their persons and belongings did not have significant surface contamination. Additional measurements were also made of iodine activity in thyroid using hand-held detectors or a mobile body monitor. This operation was arranged with the Foreign and Commonwealth Office, which had also received numerous requests for instruments from embassies and consulates in countries close to the scene of the accident. There was concern for the well-being of staff and other United Kingdom nationals who resided in or intended to visit the most affected countries. The board supplied suitable instruments, and the FCO distributed them to embassies. The frequency of environmental monitoring was increased from 29 April in anticipation of contamination and appropriate Board instrumentation was deployed. After the Chernobyl cloud arrived in the UK on 2 May, there were numerous requests from local government, public authorities, private companies and members of the public for information and advice on monitoring equipment and procedures. Some of these requirements could be met with existing equipment but members of the public were usually advised not to proceed. At a later stage, the contamination of foodstuffs and livestock required the development of an instrument capable of detecting low levels of {sup 137}Cs and {sup 134}Cs in food

  3. The qualification of electrical components and instrumentations relevant to safety

    International Nuclear Information System (INIS)

    Zambardi, F.

    1989-03-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

  4. DWPF liquid sample station: Status of equipment development

    International Nuclear Information System (INIS)

    Caplan, J.R.

    1987-01-01

    This report summarizes operating experience and equipment status of the DWPF liquid sample cell. Operation hours to date, results of equipment inspections and problems encountered and their solutions are discussed. An equipment and instrumentation status updating DPST-85-592, DWPF LIQUID SAMPLE CELL MOCK-UP, is presented. Remaining development items are also outlined

  5. 14 CFR 121.337 - Protective breathing equipment.

    Science.gov (United States)

    2010-01-01

    ... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Instrument and Equipment Requirements § 121.337... systems other than chemical oxygen generators, there must be a means to allow the crew to readily... fully charged. (iv) For each chemical oxygen generator, the supply system equipment must meet the...

  6. Minimally invasive instrumentation without fusion during posterior thoracic corpectomies: a comparison of percutaneously instrumented nonfused segments with open instrumented fused segments.

    Science.gov (United States)

    Lau, Darryl; Chou, Dean

    2017-07-01

    OBJECTIVE During the mini-open posterior corpectomy, percutaneous instrumentation without fusion is performed above and below the corpectomy level. In this study, the authors' goal was to compare the perioperative and long-term implant failure rates of patients who underwent nonfused percutaneous instrumentation with those of patients who underwent traditional open instrumented fusion. METHODS Adult patients who underwent posterior thoracic corpectomies with cage reconstruction between 2009 and 2014 were identified. Patients who underwent mini-open corpectomy had percutaneous instrumentation without fusion, and patients who underwent open corpectomy had instrumented fusion above and below the corpectomy site. The authors compared perioperative outcomes and rates of implant failure requiring reoperation between the open (fused) and mini-open (unfused) groups. RESULTS A total of 75 patients were identified, and 53 patients (32 open and 21 mini-open) were available for followup. The mean patient age was 52.8 years, and 56.6% of patients were male. There were no significant differences in baseline variables between the 2 groups. The overall perioperative complication rate was 15.1%, and there was no significant difference between the open and mini-open groups (18.8% vs 9.5%; p = 0.359). The mean hospital stay was 10.5 days. The open group required a significantly longer stay than the mini-open group (12.8 vs 7.1 days; p open and mini-open groups at 6 months (3.1% vs 0.0%, p = 0.413), 1 year (10.7% vs 6.2%, p = 0.620), and 2 years (18.2% vs 8.3%, p = 0.438). The overall mean follow-up was 29.2 months. CONCLUSIONS These findings suggest that percutaneous instrumentation without fusion in mini-open transpedicular corpectomies offers similar implant failure and reoperation rates as open instrumented fusion as far out as 2 years of follow-up.

  7. Safeguarding on-power fuelled reactors - instrumentation and techniques

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  8. Providing reliable equipment to IAEA through a low risk transition plan

    International Nuclear Information System (INIS)

    Green, L.; Weinstock, E.V.; Karlin, E.W.

    1988-01-01

    The development and production of safeguards equipment is a complex process containing many potential pitfalls between the conceptual design and its implementation in the field. The conditions for equipment use are especially demanding. At the same time, the consequences of failure may be serious. Repeated failure may result in the loss of credibility of safeguards. Expensive back up measures such as re-verification of inventories may be required. Inspectors may come to distrust the equipment. Finally, the expense of maintaining the equipment may be excessive. It is therefore essential that the process for bringing equipment for the conceptual stage to actual routine use minimizes the risk of producing equipment that is unsuitable for the job. Fortunately, approaches for accomplishing this have already been developed in both the industrial and commercial sectors. One such approach, the Low Risk Transition Plan (LRTP) is described to show it can be applied to the production of reliable safeguards equipment

  9. Failure prediction using machine learning and time series in optical network.

    Science.gov (United States)

    Wang, Zhilong; Zhang, Min; Wang, Danshi; Song, Chuang; Liu, Min; Li, Jin; Lou, Liqi; Liu, Zhuo

    2017-08-07

    In this paper, we propose a performance monitoring and failure prediction method in optical networks based on machine learning. The primary algorithms of this method are the support vector machine (SVM) and double exponential smoothing (DES). With a focus on risk-aware models in optical networks, the proposed protection plan primarily investigates how to predict the risk of an equipment failure. To the best of our knowledge, this important problem has not yet been fully considered. Experimental results showed that the average prediction accuracy of our method was 95% when predicting the optical equipment failure state. This finding means that our method can forecast an equipment failure risk with high accuracy. Therefore, our proposed DES-SVM method can effectively improve traditional risk-aware models to protect services from possible failures and enhance the optical network stability.

  10. In-core failure of the instrumented BWR rod by locally induced high coolant temperature

    International Nuclear Information System (INIS)

    Yanagisawa, Kazuaki

    1985-12-01

    In the BWR type light water loop instrumented in HBWR, a current BWR type fuel rod pre-irradiated up to 5.6 MWd/kgU was power ramped to 50 kW/m. During the ramp, the diameter of the rod was expanded significantly at the bottom end. The behaviour was different from which caused by pellet-cladding interaction (PCI). In the post-irradiation examination, the rod was found to be failed. In this paper, the cause of the failure was studied and obtained the followings. (1) The significant expansion of the rod diameter was attributed to marked oxidation of cladding outer diameter, appeared in the direction of 0 0 -180 0 degree with a shape of nodular. (2) The cladding in the place was softened by high coolant temperature. Coolant pressure, 7MPa intruded the cladding into inside chamfer void at pellet interface. (3) At the place of the significant oxidation, an instrumented transformer was existed and the coolant flow area was very little. The reduction of the coolant flow was enhanced by the bending of the cladding which was caused in pre-irradiation stage. They are considered to be a principal cause of local closure of coolant flow and resultant high temperature in the place. (author)

  11. Instrumentation database specific to Trillo I NPP

    International Nuclear Information System (INIS)

    Pereira Pagan, M.B.; Saenz de Tejada, P.; Fernandez Alvarez, A.; Haya, J.

    1997-01-01

    The analysis of data on electronic instrumentation components in the Trillo I PSA has involved and extra effort, basically due to the particular characteristics of these equipment items. This analysis has different aspects depending on the type of information used: Components whose data have been obtained from generic information sources (with or without Bayesian processing). Components whose data have been obtained from specific German studies (TUV) Components whose data have been based directly on the historical experience of Trillo I NPP Components whose data have been based on miscellaneous generic and specific sources This information can also be classified into: Micro components formed by a single module ar card Micro components: formed by set of instrumentation elements It can be further subdivided according to the operating conditions of the components: Equipment whose operation depends on the functions they perform in a particular system (eg. reactor protection system instrumentation channels) Equipment whose operation is not associated with particular conditions (eg. modules for motor-operated equipment). (Author)

  12. Do NiTi instruments show defects before separation? Defects caused by torsional fatigue in hand and rotary nickel-titanium (NiTi) instruments which lead to failure during clinical use.

    Science.gov (United States)

    Chakka, N V Murali Krishna; Ratnakar, P; Das, Sanjib; Bagchi, Anandamy; Sudhir, Sudhir; Anumula, Lavanya

    2012-11-01

    Visual and microscopic evaluation of defects caused by torsional fatigue in hand and rotary nickel titanium (NiTi) instruments. Ninety-six NiTi greater taper instruments which were routinely used for root canal treatment only in anterior teeth were selected for the study. The files taken include ProTaper for hand use, ProTaper Rotary files and Endowave rotary files. After every use, the files were observed visually and microscopically (Stereomicroscope at 10×) to evaluate the defects caused by torsional fatigue. Scoring was given according to a new classification formulated which gives an indication of the severity of the defect or damage. Data was statistically analyzed using KruskallWallis and Mann-Whitney U test. Number of files showing defects were more under stereomicroscope than visual examination. But, the difference in the evaluation methods was not statistically significant. The different types of defects observed were bent instrument, straightening/stretching of twist contour and partial reverse twisting. Endowave files showed maximum number of defects followed by ProTaper for hand use and least in ProTaper Rotary. Visible defects due to torsional fatigue do occur in NiTi instruments after clinical use. Both visual and microscopic examinations were efficient in detecting defects caused due to torsional fatigue. This study emphasizes that all files should be observed for any visible defects before and after every instrumentation cycle to minimize the risk of instrument separation and failure of endodontic therapy.

  13. Life Cycle Management for Equipments in Nuclear Plants Based on Reliability

    International Nuclear Information System (INIS)

    Wang Dalin; Sun Jinlong

    2012-01-01

    Majority of equipments in nuclear power stations are not un-repairable, but repaired after failures or maintained periodically and then returned to running. Along with aging or fatigue causes, duration between failures may be variable such as larger or shorter. Equipments failure occurrences are consistent with non-homogeneous Poisson process (NHPP), in which their failure rates are variable. We chose Weibull process to simplify the actual circumstances to obtain the optimal life cycle management plans approximately. In application we need to estimate parameters of Weibull process with existing data. Before that, trend test is necessary. Total time test (TTT) is an alternative. Trend test can determine whether the failure rate changes along operating time and whether the devices operated under imperfect or minimal repair. Parameters of Weibull process λ, β can be estimated by maximum likelihood estimation method. LCM model is designed to found an optimizing model for those aging equipments under minimal repair or imperfect maintenance with maximum economic or availability as objective function. The purpose is to establish the optimal replacement strategies. Periodical replacement is the most regular choice and so LCM model aims to calculate the optimal replacement periodical duration.

  14. Compliance testing of medical diagnostic x-ray equipment: three years experience of a public hospital in western Australia

    International Nuclear Information System (INIS)

    Tuchyna, T.; Jacob, C.S.

    2000-01-01

    Full text: A formal compliance testing program which began on 1 January 1997 called for all medical and diagnostic x-ray equipment to be tested according to protocols established by the Western Australian Radiological Council. This work describes the impact of the legislation three years post implementation on a major teaching Hospital with 45 x-ray tubes located throughout 37 rooms. Testing is performed prior to scheduled service by licensed compliance testers according to test methods specified in the Western Australian Compliance Testing Workbook, 1997. A dedicated non-invasive x-ray beam analyser is instrumental in accurately determining radiation output parameters of the generator and x-ray tube. Assessment of compliance is determined by a Qualified Expert. Repair and re-testing of non-compliant items is coordinated with service personnel. Notices of non-compliance were received for approximately 60% of the equipment in the Hospital following the equipment' first annual test. Reasons and seriousness of failure varied according to equipment category, test category, equipment use and age. The majority of non-compliance issues were resolved within 90 days. At the end of the third year of testing, approximately 75% of the x-ray units tested met the compliance criteria. The main reasons for non-compliance were found to be design limitations associated with old technology and the current radiation legislation that makes it difficult for older equipment to meet the stringent criteria. The number and categories of failure did not significantly decrease in the second or third years of testing. Exemptions from compliance criteria have been sought for two units on the basis of age and design. Units unable to meet the criteria following several repair attempts or where the cost of repair was deemed not justified, were decommissioned. Formal testing of medical x-ray equipment has demonstrated various non-compliance issues that did not significantly improve during the

  15. IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

  16. Instrumentation in thermoluminescence dosimetry

    International Nuclear Information System (INIS)

    Julius, H.W.

    1986-01-01

    In the performance of a thermoluminescence dosimetry (TLD) system the equipment plays an important role. Crucial parameters of instrumentation in TLD are discussed in some detail. A review is given of equipment available on the market today - with some emphasis on automation - which is partly based on information from industry and others involved in research and development. (author)

  17. Conceptual design report, CEBAF basic experimental equipment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-04-13

    The Continuous Electron Beam Accelerator Facility (CEBAF) will be dedicated to basic research in Nuclear Physics using electrons and photons as projectiles. The accelerator configuration allows three nearly continuous beams to be delivered simultaneously in three experimental halls, which will be equipped with complementary sets of instruments: Hall A--two high resolution magnetic spectrometers; Hall B--a large acceptance magnetic spectrometer; Hall C--a high-momentum, moderate resolution, magnetic spectrometer and a variety of more dedicated instruments. This report contains a short description of the initial complement of experimental equipment to be installed in each of the three halls.

  18. Maintenance of nuclear medicine instruments

    Energy Technology Data Exchange (ETDEWEB)

    Ambro, P

    1993-12-31

    Maintenance of instruments is generally of two kinds: (a) corrective maintenance, on a non-scheduled basis, to restore equipment to a functional status by repairs; (b) preventive maintenance, to keep equipment in a specified functional condition by providing systematic inspection, quality control, detection and correction of early malfunctions. Most of the instruments used in nuclear medicine are rather complex systems built from mechanical, electrical and electronic parts. Any one of these components is liable to fail at some time or other. Repair could be done only by a specialist who is able to evaluate the condition of the various parts ranging from cables to connectors, from scintillators to photomultipliers, from microprocessors to microswitches. The knowledge of the intricacies of the various electronic components required for their repairs is quite wide and varied. The electronics industry turns out more and more multi-purpose chips which can carry out the functions of many parts used in the instruments of the earlier generation. This provides protection against unauthorized copying of the circuits but it serves another purpose as well of inhibiting repairs by non-factory personnel. These trends of the instrument design should be taken into consideration when a policy has to be developed for the repairs of the hospital based equipment 1 fig., 1 tab

  19. Maintenance of nuclear medicine instruments

    International Nuclear Information System (INIS)

    Ambro, P.

    1992-01-01

    Maintenance of instruments is generally of two kinds: (a) corrective maintenance, on a non-scheduled basis, to restore equipment to a functional status by repairs; (b) preventive maintenance, to keep equipment in a specified functional condition by providing systematic inspection, quality control, detection and correction of early malfunctions. Most of the instruments used in nuclear medicine are rather complex systems built from mechanical, electrical and electronic parts. Any one of these components is liable to fail at some time or other. Repair could be done only by a specialist who is able to evaluate the condition of the various parts ranging from cables to connectors, from scintillators to photomultipliers, from microprocessors to microswitches. The knowledge of the intricacies of the various electronic components required for their repairs is quite wide and varied. The electronics industry turns out more and more multi-purpose chips which can carry out the functions of many parts used in the instruments of the earlier generation. This provides protection against unauthorized copying of the circuits but it serves another purpose as well of inhibiting repairs by non-factory personnel. These trends of the instrument design should be taken into consideration when a policy has to be developed for the repairs of the hospital based equipment

  20. The development of techniques for determining the residual life time prediction on NPP equipment

    International Nuclear Information System (INIS)

    Antonov, Alexander V.; Dagaev, Alexander V.; Volnikov, Ivan S.

    1999-01-01

    The problem of determining the residual life prediction of NPP equipment is presently highly pressing. NPP residual life resources are 30 years, but for particular equipment it is much less. Thus, residual life resource for equipment of control and protection system of NPP unit is 5-10 years. The NPP equipment is expensive and its replacing requires much expense. Hence an urgent problem is to study residual life resources of equipment on the basis of statistic information obtained during operation. Deterministic approach of determining residual life resources for particular equipment is widely known in the literature. Physical and statistical models are also being developed for determining the residual life, e.g. the model (loading-bearing capability). The present work offers the techniques of the residual life determination reasoning from statistic information of functioning objects in the process of operation. To put the techniques into effect it is necessary to have information about the time of operation of a group of objects of the same type, the number of failures; it is desirable to know failure operating time, order of the object replacement and the reason which caused the replacement (failure or planned preventive maintenance). Metrics is based on studying the parameters for the series of failures resulted from real statistic data. Then we can proceed to distribution density of the failure working time. For this purpose the Voltarra's equation of the second order is solved f(t) = ω(t) + ∫ 0 t f(t - τ)ω(τ)dτ. Since statistics of data sampling related to failure is small due to difficulties in solution of Voltaire's equation, the authors offer moderate method of solution for the above equation. After distribution density of the failure working time is determined the calculation of equipment residual life is made by the following formula: T τ (t) 1/P(τ)∫ 0 ∞ P(t)dt. The proposed techniques are realised as the software. In the course of working

  1. 47 CFR 2.1505 - Test instrumentation and equipment.

    Science.gov (United States)

    2010-10-01

    ... instrument is to be DC coupled and capable of manually triggered single sweeps. (d) Frequency counter. A... frequency. (e) Signal generator. A calibrated signal generator with an output of at least 75 mW at 121.5 and...

  2. 40 CFR 63.648 - Equipment leak standards.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 10 2010-07-01 2010-07-01 false Equipment leak standards. 63.648...) National Emission Standards for Hazardous Air Pollutants From Petroleum Refineries § 63.648 Equipment leak...) through (c)(10) and (e) through (i) of this section. (1) The instrument readings that define a leak for...

  3. X-ray equipment

    International Nuclear Information System (INIS)

    Redmayne, I.G.B.

    1988-01-01

    The patent concerns a warning and protection system for mobile x-ray equipment used for 'on site' radiography, so that workers in the vicinity of such a working unit can be alerted to its presence. The invention is a local repeater warning system which gives a preliminary warning that energisation of the tubehead is imminent, as well as a switch near the tubehead to abort or inhibit energisation. The latter switch allows personnel caught in the vicinity of the tubehead to prevent energisation. The preliminary warning may be flashing lamps or by a klaxon. The control unit for the equipment may include a monitoring circuit to detect failure of the warning light or klaxon. (U.K.)

  4. X-ray equipment

    Energy Technology Data Exchange (ETDEWEB)

    Redmayne, I.G.B.

    1988-01-06

    The patent concerns a warning and protection system for mobile x-ray equipment used for 'on site' radiography, so that workers in the vicinity of such a working unit can be alerted to its presence. The invention is a local repeater warning system which gives a preliminary warning that energisation of the tubehead is imminent, as well as a switch near the tubehead to abort or inhibit energisation. The latter switch allows personnel caught in the vicinity of the tubehead to prevent energisation. The preliminary warning may be flashing lamps or by a klaxon. The control unit for the equipment may include a monitoring circuit to detect failure of the warning light or klaxon. (U.K.).

  5. Rooting out causes in failure analysis; Risk analysis

    Energy Technology Data Exchange (ETDEWEB)

    Keith, Graeme

    2010-07-01

    The Deepwater Horizon disaster was a terrible reminder of the consequences of equipment failure on facilities operating in challenging environments. Thankfully catastrophes on the scale of the Deepwater Horizon are rare, but equipment failure is a daily occurrence on installations around the globe. The consequences range from short unexpected downtime, to a total stop on production. from a brief burst of flaring to lasting environmental damage and from the momentary discomfiture of a worker to incapability or death. (Author)

  6. Virtual-Instrument-Based Online Monitoring System for Hands-on Laboratory Experiment of Partial Discharges

    Science.gov (United States)

    Karmakar, Subrata

    2017-01-01

    Online monitoring of high-voltage (HV) equipment is a vital tool for early detection of insulation failure. Most insulation failures are caused by partial discharges (PDs) inside the HV equipment. Because of the very high cost of establishing HV equipment facility and the limitations of electromagnetic interference-screened laboratories, only a…

  7. Operational and reliability experience with reactor instrumentation

    International Nuclear Information System (INIS)

    Dixon, F.; Gow, R.S.

    1978-01-01

    In the last 15 years the CEGB has experienced progressive plant development, integration and changes in operating regime through nine nuclear (gas-cooled reactor) power stations with corresponding instrumentation advances leading towards more refined centralized control. Operation and reliability experience with reactor instrumentation is reported in this paper with reference to the progressive changes related to the early magnox, late magnox and AGR periods. Data on instrumentation reliability in terms of reactor forced outages are presented and show that the instrumentation contributions to loss of generating plant availability are small. Reactor safety circuits, neutron flux and temperature measurements, gas analysis and vibration monitoring are discussed. In reviewing the reactor instrumentation the emphasis is on reporting recent experience, particularly on AGR equipment, but overall performance and changes to magnox equipment are included so that some appreciation can be obtained of instrumentation requirements with respect to plant lifetimes. (author)

  8. Failure Analysis of Nonvolatile Residue (NVR) Analyzer Model SP-1000

    Science.gov (United States)

    Potter, Joseph C.

    2011-01-01

    National Aeronautics and Space Administration (NASA) subcontractor Wiltech contacted the NASA Electrical Lab (NE-L) and requested a failure analysis of a Solvent Purity Meter; model SP-IOOO produced by the VerTis Instrument Company. The meter, used to measure the contaminate in a solvent to determine the relative contamination on spacecraft flight hardware and ground servicing equipment, had been inoperable and in storage for an unknown amount of time. NE-L was asked to troubleshoot the unit and make a determination on what may be required to make the unit operational. Through the use of general troubleshooting processes and the review of a unit in service at the time of analysis, the unit was found to be repairable but would need the replacement of multiple components.

  9. Experiences with 'on-line' diagnostic instrumentation in nuclear power plants

    International Nuclear Information System (INIS)

    Gopal, R.; Ciaramitaro, W.; Smith, J.R.

    1981-01-01

    Over the past several years, Westinghouse has developed a coordinated system of on-line diagnostic instrumentation for the acquisition and analysis of data for diagnostics and incipient failure detection of critical plant equipment and systems. Primary motivation for this work is to improve Nuclear Steam Supply System (NSSS) availability and maintainability through the detection of malfunctions at their inception. These systems include: 1) Acoustic leak monitoring for detection and location of leaks in the primary system pressure boundary and other piping systems in PWR's; 2) Metal impact monitoring for detection of loose debris in the reactor vessel and steam generators; 3) Nuclear noise monitoring for monitoring core barrel vibration. Summarized in this paper are some of the features of the systems and inplant experience. (author)

  10. Application range affected by software failures in safety relevant instrumentation and control systems of nuclear power plants

    International Nuclear Information System (INIS)

    Jopen, Manuela; Mbonjo, Herve; Sommer, Dagmar; Ulrich, Birte

    2017-03-01

    This report presents results that have been developed within a BMUB-funded research project (Promotion Code 3614R01304). The overall objective of this project was to broaden the knowledge base of GRS regarding software failures and their impact in software-based instrumentation and control (I and C) systems. To this end, relevant definitions and terms in standards and publications (DIN, IEEE standards, IAEA standards, NUREG publications) as well as in the German safety requirements for nuclear power plants were analyzed first. In particular, it was found that the term ''software fault'' is defined differently and partly contradictory in the considered literature sources. For this reason, a definition of software fault was developed on the basis of the software life cycle of software-based I and C systems within the framework of this project, which takes into account the various aspects relevant to software faults and their related effects. It turns out that software failures result from latent faults in a software-based control system, which can lead to a non-compliant behavior of a software-based I and C system. Hereby a distinction should be made between programming faults and specification faults. In a further step, operational experience with software failures in software-based I and C systems in nuclear facilities and in nonnuclear sector was investigated. The identified events were analyzed with regard to their cause and impacts and the analysis results were summarized. Based on the developed definition of software failure and on the COMPSIS-classification scheme for events related to software based I and C systems, the COCS-classification scheme was developed to classify events from operating experience with software failures, in which the events are classified according to the criteria ''cause'', ''affected system'', ''impact'' and ''CCF potential''. This classification scheme was applied to evaluate the events identified in the framework of this project

  11. LDRD report: Smoke effects on electrical equipment

    International Nuclear Information System (INIS)

    TANAKA, TINA J.; BAYNES, EDWARD E. JR.; NOWLEN, STEVEN P.; BROCKMANN, JOHN E.; GRITZO, LOUIS A.; SHADDIX, Christopher R.

    2000-01-01

    Smoke is known to cause electrical equipment failure, but the likelihood of immediate failure during a fire is unknown. Traditional failure assessment techniques measure the density of ionic contaminants deposited on surfaces to determine the need for cleaning or replacement of electronic equipment exposed to smoke. Such techniques focus on long-term effects, such as corrosion, but do not address the immediate effects of the fire. This document reports the results of tests on the immediate effects of smoke on electronic equipment. Various circuits and components were exposed to smoke from different fields in a static smoke exposure chamber and were monitored throughout the exposure. Electrically, the loss of insulation resistance was the most important change caused by smoke. For direct current circuits, soot collected on high-voltage surfaces sometimes formed semi-conductive soot bridges that shorted the circuit. For high voltage alternating current circuits, the smoke also tended to increase the likelihood of arcing, but did not accumulate on the surfaces. Static random access memory chips failed for high levels of smoke, but hard disk drives did not. High humidity increased the conductive properties of the smoke. The conductivity does not increase linearly with smoke density as first proposed; however, it does increase with quantity. The data can be used to give a rough estimate of the amount of smoke that will cause failures in CMOS memory chips, dc and ac circuits. Comparisons of this data to other fire tests can be made through the optical and mass density measurements of the smoke

  12. Development of an instrument for fast monitoring of radiotherapy equipment

    International Nuclear Information System (INIS)

    Khoury, H.J.; Almeida Melo, F. de; Patriota, J.H.; Oliveira Lira, C.B. de

    1990-01-01

    Radiation therapy machines need a constant monitoring to assure tumoral dose accuracy. Special attention must be given to linear accelerators which should be checked frequently. By this reason, an instrument was developed at the Nuclear Instrumentation Laboratory DEN/UFPE to measure the output energy and beam symmetry. This instrument use three silicon photodiodes as radiation detectors. Two of then were localized at 5cm and 10cm depht at the central axis and one at 5 cm from the center, at the lateral irradiated field. Changes in the photon spectrum are detected by the ratio of upper to lower photodiode response. The radiation field uniformity is checked by the lateral photodiode. (author) [pt

  13. [Development of Hospital Equipment Maintenance Information System].

    Science.gov (United States)

    Zhou, Zhixin

    2015-11-01

    Hospital equipment maintenance information system plays an important role in improving medical treatment quality and efficiency. By requirement analysis of hospital equipment maintenance, the system function diagram is drawed. According to analysis of input and output data, tables and reports in connection with equipment maintenance process, relationships between entity and attribute is found out, and E-R diagram is drawed and relational database table is established. Software development should meet actual process requirement of maintenance and have a friendly user interface and flexible operation. The software can analyze failure cause by statistical analysis.

  14. Equipment reliability improvement process; implementation in Almaraz NPP and Trillo NPP

    International Nuclear Information System (INIS)

    Risquez Bailon, Aranzazu; Gutierrez Fernandez, Eduardo

    2010-01-01

    The Equipment Reliability Improvement Process (INPO AP-913) is a non-regulatory process developed by the US Nuclear Industry for improving Plants Availability. This Process integrates and coordinates a broad range of equipment reliability activities into one process, performed by the Plant in a non-centralized way. The integration and coordination of these activities will allow plant personnel to evaluate the trends of important station equipment, develop and implement long-term equipment health plans, monitor equipment performance and condition, and make adjustments to preventive maintenance tasks and frequencies based on equipment operating experience, if necessary, arbitrating operational and design improvements, to reach a Failure-free Operation. This paper describes the methodology of Equipment Reliability Improvement Process, being focused on main aspects of the implementation process, relating to the scope and establishment of an Equipment Reliability Monitoring Plan, which should include and complement the existing mechanisms and organizations in the Plant to monitor the condition and performance of the equipments, with the common aim of achieving an operation free of failures. The paper will describe the tools that Iberdrola Ingenieria has developed to support the implementation and monitoring of the Equipment Reliability Improvement Process, as well as the results and lessons learned from its implementation in Almaraz NPP and Trillo NPP. (authors)

  15. Development of equipment qualification requirements for NPP instrumentation and control systems

    International Nuclear Information System (INIS)

    Siora, A. A.; Reshetitskij, S. V.; Harybin, A. V.

    2012-01-01

    The main stages of equipment qualification are presented. The aim of the work is to ensure compatibility between Ukrainian and international requirements. A comparison with US NRC requirements has been done. The approach in equipment qualification is presented for the resistance to: irradiation; dust; seismic motion, vibrations and mechanical impact; environmental impact (temperature, humidity, pressure); power supply parameters etc., as well as the technological testing

  16. 24 CFR 232.570 - Endorsement of credit instrument.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Endorsement of credit instrument... of Fire Safety Equipment Eligible Security Instruments § 232.570 Endorsement of credit instrument. The Commissioner shall indicate his insurance of the loan by endorsing the credit instrument and...

  17. Failure: A Source of Progress in Maintenance and Design

    Science.gov (United States)

    Chaïb, R.; Taleb, M.; Benidir, M.; Verzea, I.; Bellaouar, A.

    This approach, allows using the failure as a source of progress in maintenance and design to detect the most critical components in equipment, to determine the priority order maintenance actions to lead and direct the exploitation procedure towards the most penalizing links in this equipment, even define the necessary changes and recommendations for future improvement. Thus, appreciate the pathological behaviour of the material and increase its availability, even increase its lifespan and improve its future design. In this context and in the light of these points, the failures are important in managing the maintenance function. Indeed, it has become important to understand the phenomena of failure and degradation of equipments in order to establish an appropriate maintenance policy for the rational use of mechanical components and move to the practice of proactive maintenance [1], do maintenance at the design [2].

  18. Quantitative assessment of probability of failing safely for the safety instrumented system using reliability block diagram method

    International Nuclear Information System (INIS)

    Jin, Jianghong; Pang, Lei; Zhao, Shoutang; Hu, Bin

    2015-01-01

    Highlights: • Models of PFS for SIS were established by using the reliability block diagram. • The more accurate calculation of PFS for SIS can be acquired by using SL. • Degraded operation of complex SIS does not affect the availability of SIS. • The safe undetected failure is the largest contribution to the PFS of SIS. - Abstract: The spurious trip of safety instrumented system (SIS) brings great economic losses to production. How to ensure the safety instrumented system is reliable and available has been put on the schedule. But the existing models on spurious trip rate (STR) or probability of failing safely (PFS) are too simplified and not accurate, in-depth studies of availability to obtain more accurate PFS for SIS are required. Based on the analysis of factors that influence the PFS for the SIS, using reliability block diagram method (RBD), the quantitative study of PFS for the SIS is carried out, and gives some application examples. The results show that, the common cause failure will increase the PFS; degraded operation does not affect the availability of the SIS; if the equipment was tested and repaired one by one, the unavailability of the SIS can be ignored; the corresponding occurrence time of independent safe undetected failure should be the system lifecycle (SL) rather than the proof test interval and the independent safe undetected failure is the largest contribution to the PFS for the SIS

  19. Analysis of the Failures and Corrective Actions for the LHC Cryogenics Radiation Tolerant Electronics and its Field Instruments

    CERN Document Server

    Balle, Ch; Vauthier, N

    2014-01-01

    The LHC cryogenic system radiation tolerant electronics and their associated field instruments have been in nominal conditions since before the commissioning of the first LHC beams in September 2008. This system is made of about 15’000 field instruments (thermometers, pressure sensors, liquid helium level gauges, electrical heaters and position switches), 7’500 electronic cards and 853 electronic crates. Since mid-2008 a software tool has been deployed, this allows an operator to report a problem and then lists the corrective actions. The tool is a great help in detecting recurrent problems that may be tackled by a hardware or software consolidation. The corrective actions range from simple resets, exchange of defective equipment, repair of electrical connectors, etc. However a recurrent problem that heals by itself is present on some channels. This type of fault is extremely difficult to diagnose and it appears as a temporary opening of an electrical circuit; its duration can range from a few minutes to ...

  20. 46 CFR 78.47-75 - Ventilation alarm failure.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Ventilation alarm failure. 78.47-75 Section 78.47-75... Fire and Emergency Equipment, Etc. § 78.47-75 Ventilation alarm failure. (a) The alarm required by § 72... FAILURE IN VEHICULAR SPACE.” (b) [Reserved] [CGFR 66-33, 31 FR 15284, Dec. 6, 1966] ...

  1. Safeguarding on-power fuelled reactors - instrumentation and techniques

    International Nuclear Information System (INIS)

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

    1977-05-01

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

  2. Studies on failure kind analysis of the radiologic medical equipment in general hospital

    International Nuclear Information System (INIS)

    Lee, Woo Cheul; Kim, Jeong Lae

    1999-01-01

    This paper included a data analysis of the unit of medical devices using maintenance recording card that had medical devices of unit failure mode, hospital of failure mode and MTBF. The results of the analysis were as follows : 1. Medical devices of unit failure mode was the highest in QC/PM such A hospital as 33.9%, B hospital 30.9%, C hospital 30.3%, second degree was the Electrical and Electronic failure such A hospital as 23.5%, B hospital 25.3%, C hospital 28%, third degree was mechanical failure such A hospital as 19.6%, B hospital 22.5%, C hospital 25.4%. 2. Hospital of failure mode was the highest in Mobile X-ray device(A hospital 62.5%, B hospital 69.5%, C hospital 37.4%), and was the lowest in Sono devices(A hospital 16.76%, B hospital 8.4%, C hospital 7%). 3. Mean time between failures(MTBT) was the highest in SONO devices and was the lowest in Mobile X-ray devices which have 200 - 400 failure hours. 4. Average failure ratio was the highest in Mobile X-ray devices(A hospital 31.3%, B hospital 34.8%, C hospital 18.7%), and was the lowest in Sono(Ultrasound) devices (A hospital 8.4%, B hospital 4.2%, C hospital 3.5%). 5. Failure ratio results of medical devices according to QC/PM part of unit failure mode were as follows ; A hospital was the highest part of QC/PM (50%) in Mamo X-ray device and was the lowest part of QC/PM(26.4%) in Gastro X-ray. B hospital was the highest part of QC/PM(56%) in Mobile X-ray device, and the lowest part of QC/PM(12%) in Gastro X-ray. C hospital was the highest part of QC/PM(60%) in R/F X-ray device, and the lowest a part of QC/PM(21%) in Universal X-ray. It was found that the units responsible for most failure decreased by systematic management. We made the preventive maintenance schedule focusing on adjustment of operating and dust removal

  3. 46 CFR 97.37-50 - Ventilation alarm failure.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Ventilation alarm failure. 97.37-50 Section 97.37-50... OPERATIONS Markings for Fire and Emergency Equipment, Etc. § 97.37-50 Ventilation alarm failure. (a) The...-inch letters “VENTILATION FAILURE IN VEHICULAR SPACE.” (b) [Reserved] [CGFR 66-33, 31 FR 15286, Dec. 6...

  4. Instrumentation maintenance

    International Nuclear Information System (INIS)

    Mack, D.A.

    1976-09-01

    It is essential to any research activity that accurate and efficient measurements be made for the experimental parameters under consideration for each individual experiment or test. Satisfactory measurements in turn depend upon having the necessary instruments and the capability of ensuring that they are performing within their intended specifications. This latter requirement can only be achieved by providing an adequate maintenance facility, staffed with personnel competent to understand the problems associated with instrument adjustment and repair. The Instrument Repair Shop at the Lawrence Berkeley Laboratory is designed to achieve this end. The organization, staffing and operation of this system is discussed. Maintenance policy should be based on studies of (1) preventive vs. catastrophic maintenance, (2) records indicating when equipment should be replaced rather than repaired and (3) priorities established to indicate the order in which equipment should be repaired. Upon establishing a workable maintenance policy, the staff should be instructed so that they may provide appropriate scheduled preventive maintenance, calibration and corrective procedures, and emergency repairs. The education, training and experience of the maintenance staff is discussed along with the organization for an efficient operation. The layout of the various repair shops is described in the light of laboratory space and financial constraints

  5. Study on operation of a research reactor during one PCS pump failure accident

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Kyoung Woo; Yoon, Hyu Ngi; Kim, Seong Hoon; Chi, Dae Young; Yoon, Juh Yeon [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    The Primary cooling system (PCS) of a research reactor is designed to provide adequate cooling to the reactor core with a reasonable margin during all operation modes. The PCS consists of pumps, heat exchangers, and all necessary interconnecting pipes, valves, and instruments. The number of pumps is determined from a safety and economic point of view. As the number of pump trains increase, the cost increases according to the increase in safety class equipment. However, it is impossible to install one pump for a PCS because a zero flow can instantaneously occur during a pump failure such as a pump seizure. Thus, a PCS frequently consists of two parallel 50% capacity pumps and heat exchangers. In addition, check valves are generally installed to prevent a reversal flow when multiple pumps are designed to operate. However, if a swing type check valve is used, it should be estimated whether the slam due to instantaneous closing of the valve affects the system vibration. To reduce the vibration by a slam phenomenon, additional equipment such as a damper will be installed in the valve. The purpose of the check valve in PCS is to prevent the flow path when a reverse flow occurs. The installation of additional equipment will make it difficult to perform this function. In this study, it is estimated whether the PCS can operate without check valves. First, a flow analysis using Flowmaster was compared and verified by the calculation employing a empirical correlation. Second, the simulation for a one pump failure accident was performed and analyzed.

  6. Study on operation of a research reactor during one PCS pump failure accident

    International Nuclear Information System (INIS)

    Seo, Kyoung Woo; Yoon, Hyu Ngi; Kim, Seong Hoon; Chi, Dae Young; Yoon, Juh Yeon

    2012-01-01

    The Primary cooling system (PCS) of a research reactor is designed to provide adequate cooling to the reactor core with a reasonable margin during all operation modes. The PCS consists of pumps, heat exchangers, and all necessary interconnecting pipes, valves, and instruments. The number of pumps is determined from a safety and economic point of view. As the number of pump trains increase, the cost increases according to the increase in safety class equipment. However, it is impossible to install one pump for a PCS because a zero flow can instantaneously occur during a pump failure such as a pump seizure. Thus, a PCS frequently consists of two parallel 50% capacity pumps and heat exchangers. In addition, check valves are generally installed to prevent a reversal flow when multiple pumps are designed to operate. However, if a swing type check valve is used, it should be estimated whether the slam due to instantaneous closing of the valve affects the system vibration. To reduce the vibration by a slam phenomenon, additional equipment such as a damper will be installed in the valve. The purpose of the check valve in PCS is to prevent the flow path when a reverse flow occurs. The installation of additional equipment will make it difficult to perform this function. In this study, it is estimated whether the PCS can operate without check valves. First, a flow analysis using Flowmaster was compared and verified by the calculation employing a empirical correlation. Second, the simulation for a one pump failure accident was performed and analyzed

  7. IAEA experience with authentication of in-plant NDA instrumentation

    International Nuclear Information System (INIS)

    Augustson, R.H.; Dermendjiev, E.

    1983-01-01

    The paper discusses IAEA experience with permanently installed measuring equipment, i.e. in-plant NDA instrumentation, which often has advantages over portable equipment, such as improved accuracy, automated sample handling and data collection, and capacity for higher throughput. In some cases, in-plant equipment is the only means of making a field measurement. However, the use of in-plant equipment requires an additional set of inspector procedures to ensure that the instrument is working correctly and has not been tampered with. This process of verifying instrument performance is called authentication. General guidelines for approaches to authentication have been studied and formulated by an IAEA Advisory Group Meeting held in November 1981. Procedures for specific instruments have been developed in some cases with the help of national support programmes. The field application of authentication is accomplished by incorporating specific actions into inspection procedures. Results are written down as part of the working papers and included in the final inspection report. For quantitative checks such as measurement of a working standard the results are sent along with the inspection measurements to the Agency for inclusion in the safeguards data base. The in-plant equipment may be owned by the facility, a State, a safeguards organization or the Agency. In each case, the use of the in-plant equipment will necessitate additional interactions between facility operator and inspector, in order to judge the impact on plant operation, and understand what is being measured and what can go wrong. The paper discusses the IAEA's experience gained in the field application of authentication procedures for instrument systems such as weighing and volume measuring devices, rod scanners, neutron activation systems and K-edge densitometers

  8. University Reactor Instrumentation Program

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1992-11-01

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

  9. An assessment the severe accident equipment survivability for the Korean Next Generation Reactor

    International Nuclear Information System (INIS)

    Lee, B. C.; Moon, Y. T.; Park, J. W.; Kho, H. J.; Lee, S. W.

    1999-01-01

    One of the prominent design approaches to cope with the severe accident challenges in the Korean Next Generation Reactor is an assessment of equipment survivability in the severe accident environment at early design stage. In compliance with 10CFR50.34(f) and SECY-93-087, this work addresses that a reasonable level of assurance be provided to demonstrate that sufficient instrumentation and equipment will survive the consequences of a severe accident and will be available so that the operator may recover from and trend severe core damage sequences, including those scenarios which result in 100 percent oxidation of the active fuel cladding. An analytical and systematic approach was used to identify the equipment and instrumentation of safety-function and define severe accident environments including temperature, pressure, humidity, and radiation before and after the reactor vessel breach. As a result, it was concluded that with minor exceptions, existing design basis equipment qualification methods are sufficient to provide a reasonable level of assurance that this equipment will function during a severe accident. Furthermore, supplemental severe accident equipment and instrument procurement requirements were identified. (author)

  10. Failure mode and effect analysis experimental reliability determination for the CANDU reactor equipment

    International Nuclear Information System (INIS)

    Vieru, G.

    1996-01-01

    This paper describes the experimental tests performed in order to prove the reliability parameters for certain equipment manufactured in INR Pitesti, for NPP Cernavoda. The tests were provided by Technical Specifications and test procedures. A comparison, referring to the reliability parameters, between Canadian equipment and INR manufactured equipment ones is also given. The results of tests and conclusions are shown. (author)

  11. Experimenting with woodwind instruments

    Science.gov (United States)

    Lo Presto, Michael C.

    2007-05-01

    Simple experiments involving musical instruments of the woodwind family can be used to demonstrate the basic physics of vibrating air columns in resonance tubes using nothing more than straightforward measurements and data collection hardware and software. More involved experimentation with the same equipment can provide insight into the effects of holes in the tubing and other factors that make simple tubes useful as musical instruments.

  12. Management of radiological related equipments. Creating the equipment management database and analysis of the repair and maintenance records

    International Nuclear Information System (INIS)

    Eguchi, Megumu; Taguchi, Keiichi; Oota, Takashi; Kajiwara, Hiroki; Ono, Kiyotune; Hagio, Kiyofumi; Uesugi, Ekizo; Kajishima, Tetuo; Ueda, Kenji

    2002-01-01

    In 1997, we established the committee of equipments maintenance and management in our department. We designed the database in order to classify and register all the radiological related equipments using Microsoft Access. The management of conditions and cost of each equipment has become easier, by keeping and recording the database in the equipments management ledger and by filing the history of repairs or maintenances occurred to modalities. We then accounted numbers, cost of repairs and downtimes from the data of the repair and maintenance records for four years, and we reexamined the causal analysis of failures and the contents of the regular maintenance for CT and MRI equipments that had shown the higher numbers of repairs. Consequently, we have found the improvement of registration method of the data and the more economical way to use of the cost of repair. (author)

  13. Final disposal of spent nuclear fuel-equipment for site characterization

    International Nuclear Information System (INIS)

    Almen, K.; Hansson, K.; Johansson, B.E.; Nilsson, G.; Andersson, O.; Wikberg, P.; Aahagen, H.

    1983-05-01

    The suitability of a certain geological formation as a repository for the final disposal of spent nuclear fuel can be determined only after detailed investigation and analysis. The purpose of the investigations is to provide information on the geology and the hydrology and chemistry of the site concerned. The value of these data largely depends on the way in which they have been collected. The report of the findings should enable the investigating party to evaluate the function and the accuracy of the equipment with which field data have been collected for KBS 3. This report describes the geophysical equipment, the hydraulic testing equipment, the water chemistry sample extracting equipment and the core-logging equipment used. The objectives of the instrument development have been: - to obtain a high data quality. - to collect data automatically in logs and tape recorders for direct transfer to a central processing unit. - to provide back-up in order to counteract loss of data. - to make instrument more efficient. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

    failure. Firstly, the life time of emergency batteries after the station blackout (SBO) was insufficient to operate targeted instruments. Secondly, the absence of proper protection in the containment building for extremely harsh environment after severe accident caused malfunctions. Lastly, since the power or communication cable was cut off, the instruments in the containment building could not transmit information to the outside, or their power source could be lost because most of the equipment in NPPs is wired-system based.

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

    International Nuclear Information System (INIS)

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

    2013-01-01

    failure. Firstly, the life time of emergency batteries after the station blackout (SBO) was insufficient to operate targeted instruments. Secondly, the absence of proper protection in the containment building for extremely harsh environment after severe accident caused malfunctions. Lastly, since the power or communication cable was cut off, the instruments in the containment building could not transmit information to the outside, or their power source could be lost because most of the equipment in NPPs is wired-system based

  16. 76 FR 38608 - Sensors and Instrumentation Technical Advisory Committee;

    Science.gov (United States)

    2011-07-01

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  17. Experience with rotating equipment in FBTR

    International Nuclear Information System (INIS)

    Babu, A.; Subramanian, K.G.; Selvam, B.

    2006-01-01

    Fast breeder test reactor (FBTR) is a 40MWth sodium cooled PuC-UC fuelled fast breeder reactor located at Kalpakkam, Tamilnadu. FBTR has a variety of mechanical and electrical equipment comprising of single stage and multi stage water pumps, sodium pumps, compressors, Chiller units, Diesel Generator sets, vacuum pumps, ventilation fans, Turbo generator etc. The degree and extent of maintenance on these equipment are decided based on nuclear safety, station technical specification requirements, design criteria and operating philosophy. The variety and complexity of the equipment in FBTR demands various maintenance strategies (preventive, predictive, proactive etc.) for their upkeep. This paper discusses the performance of all mechanical and electrical equipment in FBTR, measures taken for their upkeep, major modifications done to prevent recurring failures, condition monitoring programme implemented, Maintenance Management and Information System developed for data acquisition and dissemination, etc. (author)

  18. Regulatory perspective on digital instrumentation and control systems for future advanced nuclear power plants

    International Nuclear Information System (INIS)

    Chiramal, M.

    1993-01-01

    This paper deals with the question of using digital technology in instrumentation and control systems for modern nuclear power reactors. The general opinion in the industry and among NRC staff is that such technology provides the opportunity for enhanced safety and reliable reactor operations. The major concern is the safe application of this technology so as to avoid common mode or common cause failures in systems. There are great differences between digital and analog system components. SECY-91-292 identifies some general regulatory concerns with regard to digital systems. There is clearly a lack of adequate regulatory direction on the application of digital equipment at this time, but the issue is being addressed by the industry, outside experts, and NRC staff. NRC staff presents a position on the issue of defense-in-depth and diversity with regard to insuring plant safety. Independent manual controls and readouts must be available to allow safe shutdown and monitoring of the plant in the event of safety system failures

  19. Governing of common cause failures

    International Nuclear Information System (INIS)

    Bock, H.W.

    1998-01-01

    Agreed strategy is to govern common cause failures by the application of diversity, to assure that the overall plant safety objectives are met even in the case that a common cause failure of a system with all redundant trains is assumed. The presented strategy aims on the application of functional diversity without the implementation of equipment diversity. In the focus are the design criteria which have to be met for the design of independent systems in such a way that the time-correlated failure of such independent systems according a common cause can be excluded deterministically. (author)

  20. Report of the Instrumentation Service - Annex C

    International Nuclear Information System (INIS)

    Majstorovic, D.

    1987-01-01

    This report describes the tasks and organizational structure of the Instrumentation service. The most important task of this Service is control and maintenance of the reactor control and protection instruments, operation control, and dosimetry system. Besides data about this basic instrumentation, the report includes data about control and maintenance of other electronic equipment related to experimental facilities [sr

  1. Preventive Rad/Nuc Detection Equipment Categorization for Consequence Management

    Energy Technology Data Exchange (ETDEWEB)

    Buddemeier, B. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Musolino, S. V. [Brookhaven National Lab. (BNL), Upton, NY (United States); Klemic, G. [US Dept. of Homeland Security National Security Technology Lab., New York, NY (United States)

    2017-06-01

    The overall objective of this project is to research, evaluate, and test first responder preventive radiological/nuclear detection equipment (PRND) to provide state and local agencies with guidance on how to best use this equipment for response after a radiological/nuclear release or detonation. While the equipment being tested in this effort has been specifically designed for detection and interdiction operations, the fleet of PRND equipment can help fill critical needs for radiological instrumentation should a consequence management response take place. This effort will provide scientific guidance on the best way to deploy and operate this class of equipment for consequence management missions. With the support of the US Department of Homeland Security’s (DHS) Domestic Nuclear Detection Office (DNDO), PRND equipment has been placed into service at federal, state, and local agencies throughout the nation. If the equipment capability and limitations are taken into account, this large inventory can be repurposed to support the emergency response in the aftermath of a radiological of nuclear event. This report evaluates PRND equipment to define key categories of equipment and the types of missions they can be used for. This is important because there are over 100 different types of PRND equipment, often with significantly different capabilities with respect to the consequence management mission. The current DNDO draft NIMS PRND equipment types were used as a foundation and expanded, when necessary, to address key characteristics important for the consequence mission. Table 1 provides a summary of the PRND instrument categories developed for this effort. Also included on the table are some common response mission detection equipment categories that will be used for capability comparisons.

  2. Environmental Testing for Precision Parts and Instruments

    International Nuclear Information System (INIS)

    Choi, Man Yong; Park, Jeong Hak; Yun, Kyu Tek

    2001-01-01

    Precision parts and instruments are tested to evaluate performance in development-process and product-step to prement a potential defect due to a failure design. In this paper, Environmental test technology, which is the basis of reliability analysis, is introduced with examples of test criterion, test method for products, encoder and traffic signal controller, and measuring instruments. Recently, as the importance of the environmental test technology is recognised. It is proposed that training of test technician and technology of jig design and failure analysis are very essential

  3. Activity of the Service for maintenance of the electronic equipment of the RA reactor in 1976, report - Annex IV

    International Nuclear Information System (INIS)

    Milosevic, M.

    1976-01-01

    Within the organizational structure of the RA reactor staff, the Service for instrumentation maintenance has the following tasks: maintenance of the existing electronic equipment; participating in experiments planning and preparation of electronic equipment; purchasing new equipment, spare parts and components; construction of new equipment for internal needs; implementation of new equipment. Basic instrumentation of the reactor facility includes: control and protection system, and dosimetry system [sr

  4. An on-line monitoring system for navigation equipment

    Science.gov (United States)

    Wang, Bo; Yang, Ping; Liu, Jing; Yang, Zhengbo; Liang, Fei

    2017-10-01

    Civil air navigation equipment is the most important infrastructure of Civil Aviation, which is closely related to flight safety. In addition to regular flight inspection, navigation equipment's patrol measuring, maintenance measuring, running measuring under special weather conditions are the important means of ensuring aviation flight safety. According to the safety maintenance requirements of Civil Aviation Air Traffic Control navigation equipment, this paper developed one on-line monitoring system with independent intellectual property rights for navigation equipment, the system breakthroughs the key technologies of measuring navigation equipment on-line including Instrument Landing System (ILS) and VHF Omni-directional Range (VOR), which also meets the requirements of navigation equipment ground measurement set by the ICAO DOC 8071, it provides technical means of the ground on-line measurement for navigation equipment, improves the safety of navigation equipment operation, and reduces the impact of measuring navigation equipment on airport operation.

  5. Maintenance of scientific instruments

    International Nuclear Information System (INIS)

    Lucero, E.

    1986-01-01

    During the last years Colombia has increased the use of nuclear techniques, instruments and equipment in ambitious health programs, as well as in research centers, industry and education; this has resulted in numerous maintenance problems. As an alternative solution IAN has established a Central Maintenance Laboratory for nuclear instruments within an International Atomic Energy Agency program for eight Latin American and nine Asian Countries. Established strategies and some results are detailed in this writing

  6. Failure analysis for WWER-fuel elements

    International Nuclear Information System (INIS)

    Boehmert, J.; Huettig, W.

    1986-10-01

    If the fuel defect rate proves significantly high, failure analysis has to be performed in order to trace down the defect causes, to implement corrective actions, and to take measures of failure prevention. Such analyses are work-consuming and very skill-demanding technical tasks, which require examination methods and devices excellently developed and a rich stock of experience in evaluation of features of damage. For that this work specifies the procedure of failure analyses in detail. Moreover prerequisites and experimental equipment for the investigation of WWER-type fuel elements are described. (author)

  7. The latest radiation instrument

    International Nuclear Information System (INIS)

    Kang, Se Sik; Gwon, Dal Gwan; Kim, Gyeong Geum

    2008-08-01

    This book deals with the latest radiation instrument, which is comprised of eight chapters. It explains X rays instrument for medial treatment, X-ray tube instrument and permissible burden with its history, structure and characteristic high voltage apparatus with high voltage rectifier circuit, X-ray control apparatus for medical treatment, X-ray image equipment X-ray television apparatus and CCD 205, X-ray apparatus of install and types, Digital X-ray apparatus with CR 261 and DR 269, performance management on X-ray for medical treatment with its history, necessity and management in the radiation field.

  8. Fault diagnosis of nuclear-powered equipment based on HMM and SVM

    International Nuclear Information System (INIS)

    Yue Xia; Zhang Chunliang; Zhu Houyao; Quan Yanming

    2012-01-01

    For the complexity and the small fault samples of nuclear-powered equipment, a hybrid HMM/SVM method was introduced in fault diagnosis. The hybrid method has two steps: first, HMM is utilized for primary diagnosis, in which the range of possible failure is reduced and the state trends can be observed; then faults can be recognized taking the advantage of the generalization ability of SVM. Experiments on the main pump failure simulator show that the HMM/SVM system has a high recognition rate and can be used in the fault diagnosis of nuclear-powered equipment. (authors)

  9. Report of the electric Equipment Service - Annex E

    International Nuclear Information System (INIS)

    Sanovic, V.

    1990-01-01

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period [sr

  10. Report of the electric Equipment Service - Annex E

    International Nuclear Information System (INIS)

    Sanovic, V.

    1987-01-01

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period [sr

  11. Report of the electric Equipment Service - Annex E

    International Nuclear Information System (INIS)

    Sanovic, V.

    1988-01-01

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period [sr

  12. Report of the electric Equipment Service - Annex E

    International Nuclear Information System (INIS)

    Tanaskovic, M.

    1995-01-01

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period [sr

  13. Equipment Obsolescence Analysis and Management Software

    Energy Technology Data Exchange (ETDEWEB)

    Redmond, J.; Carret, L.; Shaon, S.; Schultz, C.

    2015-07-01

    The procurement engineering resources at Nuclear Power Plants (NPPs) are experiencing increasing backlog for procurement items primarily due to the inability to order the original replacement parts. The level of effort and time required to prepare procurement packages is increasing since the number of obsolete parts are increasing exponentially. Procurement packages for obsolete components and parts are much more complex and take more time to prepare because of the need to perform equivalency evaluations, testing requirements and test acceptance criteria development, commercial grade dedication or equipment qualification, and increasing efforts to verify that no fraudulent or counterfeit parts are procured. This problem will be further compounded when NPPs pursue license renewal and approval for plant-life extension. Advanced planning and advanced knowledge of equipment obsolescence is required to allow for sufficient time to properly procure replacement parts for obsolete items. The uncertain supply chain capability due to obsolescence is a real problem and can cause a risk to reliable plant operations due to the potential for a lack of available spare parts and replacement components to support outages and unplanned component failures. Advanced notification of obsolescence is increasingly more important to ensure that adequate time and planning is scheduled to procure the proper replacement parts. A thorough analysis of Original Equipment Manufacturer (OEM) availability and inventory as well as an analysis of failure rates and usage rates is required to predict critical part needs to allow for early identification of obsolescence issues so that a planned and controlled strategy to qualify replacement equipment can be implemented. (Author)

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  15. Microfluidic Apps for off-the-shelf instruments.

    Science.gov (United States)

    Mark, Daniel; von Stetten, Felix; Zengerle, Roland

    2012-07-21

    Within the last decade a huge increase in research activity in microfluidics could be observed. However, despite several commercial success stories, microfluidic chips are still not sold in high numbers in mass markets so far. Here we promote a new concept that could be an alternative approach to commercialization: designing microfluidic chips for existing off-the-shelf instruments. Such "Microfluidic Apps" could significantly lower market entry barriers and provide many advantages: developers of microfluidic chips make use of existing equipment or platforms and do not have to develop instruments from scratch; end-users can profit from microfluidics without the need to invest in new equipment; instrument manufacturers benefit from an expanded customer base due to the new applications that can be implemented in their instruments. Microfluidic Apps could be considered as low-cost disposables which can easily be distributed globally via web-shops. Therefore they could be a door-opener for high-volume mass markets.

  16. Root cause of failure analysis and the system engineer

    International Nuclear Information System (INIS)

    Coppock, M.S.; Hartwig, A.W.

    1990-01-01

    In an industry where ever-increasing emphasis is being placed on root cause of failure determination, it is imperative that a successful nuclear utility have an effective means of identifying failures and performing the necessary analyses. The current Institute of Nuclear Power Operations (INPO) good practice, OE-907, root-cause analysis, gives references to methodology that will help determine breakdowns in procedures, programs, or design but gives very little guidance on how or when to perform component root cause of failure analyses. The system engineers of nuclear utilities are considered the focal point for their respective systems and are required by most programs to investigate component failures. The problem that the system engineer faces in determining a component root cause of failures lies in acquisition of the necessary data to identify the need to perform the analysis and in having the techniques and equipment available to perform it. The system engineers at the Palo Verde nuclear generating station routinely perform detailed component root cause of failure analyses. The Palo Verde program provides the system engineers with the information necessary to identify when a component root cause of failure is required. Palo Verde also has the necessary equipment on-site to perform the analyses

  17. A Study on Performance and Safety Tests of Electrosurgical Equipment.

    Science.gov (United States)

    Tavakoli Golpaygani, A; Movahedi, M M; Reza, M

    2016-09-01

    Modern medicine employs a wide variety of instruments with different physiological effects and measurements. Periodic verifications are routinely used in legal metrology for industrial measuring instruments. The correct operation of electrosurgical generators is essential to ensure patient's safety and management of the risks associated with the use of high and low frequency electrical currents on human body. The metrological reliability of 20 electrosurgical equipment in six hospitals (3 private and 3 public) was evaluated in one of the provinces of Iran according to international and national standards. The achieved results show that HF leakage current of ground-referenced generators are more than isolated generators and the power analysis of only eight units delivered acceptable output values and the precision in the output power measurements was low. Results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially in high risk instruments. It is also necessary to provide training courses for operating staff in the field of meterology in medicine to be acquianted with critical parameters to get accuracy results with operation room equipment.

  18. Void Fraction Instrument operation and maintenance manual

    International Nuclear Information System (INIS)

    Borgonovi, G.; Stokes, T.I.; Pearce, K.L.; Martin, J.D.; Gimera, M.; Graves, D.B.

    1994-09-01

    This Operations and Maintenance Manual (O ampersand MM) addresses riser installation, equipment and personnel hazards, operating instructions, calibration, maintenance, removal, and other pertinent information necessary to safely operate and store the Void Fraction Instrument. Final decontamination and decommissioning of the Void Fraction Instrument are not covered in this document

  19. Current state of commercial radiation detection equipment for homeland security applications

    International Nuclear Information System (INIS)

    Klann, R.T.; Shergur, J.; Mattesich, G.

    2009-01-01

    With the creation of the U.S. Department of Homeland Security (DHS) came the increased concern that terrorist groups would attempt to manufacture and use an improvised nuclear device or radiological dispersal device. As such, a primary mission of DHS is to protect the public against the use of these devices and to assist state and local responders in finding, locating, and identifying these types of devices and materials used to manufacture these devices. This assistance from DHS to state and local responders comes in the form of grant money to procure radiation detection equipment. In addition to this grant program, DHS has supported the development of American National Standards Institute standards for radiation detection equipment and has conducted testing of commercially available instruments. This paper identifies the types and kinds of commercially available equipment that can be used to detect and identify radiological material - for use in traditional search applications as well as primary and secondary screening of personnel, vehicles, and cargo containers. In doing so, key considerations for the conduct of operations are described as well as critical features of the instruments for specific applications. The current state of commercial instruments is described for different categories of detection equipment including personal radiation detectors, radioisotope identifiers, man-portable detection equipment, and radiation portal monitors. In addition, emerging technologies are also discussed, such as spectroscopic detectors and advanced spectroscopic portal monitors

  20. Nuclear electronic equipment for control and monitoring boards. Susceptibility of nuclear electronic pulse equipment to interference

    International Nuclear Information System (INIS)

    Buisson, Jacques; Cochinal, R.; Duquesnoy, J.; Roquefort, H.

    1972-07-01

    The correct functioning of pulse measurement units in industrial environmental conditions where interference is high, frequently gives rise to many installation problems which are difficult to solve. This paper offers some recommendations with a view to minimising the effect to electric interference on electronic equipment and gives a test method which enables this effect to be assessed qualitatively. It has been devised for nuclear electronic instrumentation but it may also be applied to other equipment and in particular the test method may be used for other cases. After a few preliminaries on how interference acts and on the terminology, the design of the equipment and the recommended connections are mentioned. Test methods are then indicated, followed by various technical comments. (author) [fr

  1. The IKARUS instrument

    International Nuclear Information System (INIS)

    Gerster, H.J.; Stein, G.

    1994-01-01

    When the Federal Government decided on a 25% reduction of CO 2 emissions till 2005 in 1990 the necessity resulted that an instrument has to be developed for the analysis and assessment of the ecological, economic and energetic impact of different reduction strategies. The development task was awarded by the BMFT to the Research Centre Juelich in cooperation with well-known institutions of energy system research. The total instrument is scheduled to be finished by the end of 1994. For the decentral use of the instrument by a wide specialist public the developed models and data banks which are equipped with a user-friendly surface are suited for larger PCs (486, 16 MB RAM/500-1000 MB ROM). (orig.) [de

  2. The evolution of IRRR nuclear standards from the single failure criterion and their impact on system design

    International Nuclear Information System (INIS)

    Clark, D.H.

    1978-01-01

    One of the first industry standards developed in the United States to meet regulatory agency criteria for the design and installation of nuclear power plant control and instrumentation systems was prepared by the Institute of Electrical and Electronics Engineers, Inc., abbreviated IEEE. This was IEEE Std. 279, first issued in 1968. It was subsequently revised and reissued as IEEE Std. 279-1971 ''IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations''. Not only has the implementation of this standard had a tremendous impact on nuclear power plant design in the United States, it has been the base document from which subsequent IEEE nuclear standards have been developed. Three major concepts which are addressed by IEEE 279, and which have had a major impact upon control and instrumentation systems in nuclear power plants are the following : 1) Single failure criterion. 2) Equipment qualification. 3) Channel independence. Each of these concepts has resulted in the development of subsequent IEEE Nuclear Standards. The impact of some of these on control and instrumentation systems are discussed. (author)

  3. A probabilistic analysis of the implications of instrument failures on ESA's Swarm mission for its individual satellite orbit deployments

    Science.gov (United States)

    Jackson, Andrew

    2015-07-01

    On launch, one of Swarm's absolute scalar magnetometers (ASMs) failed to function, leaving an asymmetrical arrangement of redundant spares on different spacecrafts. A decision was required concerning the deployment of individual satellites into the low-orbit pair or the higher "lonely" orbit. I analyse the probabilities for successful operation of two of the science components of the Swarm mission in terms of a classical probabilistic failure analysis, with a view to concluding a favourable assignment for the satellite with the single working ASM. I concentrate on the following two science aspects: the east-west gradiometer aspect of the lower pair of satellites and the constellation aspect, which requires a working ASM in each of the two orbital planes. I use the so-called "expert solicitation" probabilities for instrument failure solicited from Mission Advisory Group (MAG) members. My conclusion from the analysis is that it is better to have redundancy of ASMs in the lonely satellite orbit. Although the opposite scenario, having redundancy (and thus four ASMs) in the lower orbit, increases the chance of a working gradiometer late in the mission; it does so at the expense of a likely constellation. Although the results are presented based on actual MAG members' probabilities, the results are rather generic, excepting the case when the probability of individual ASM failure is very small; in this case, any arrangement will ensure a successful mission since there is essentially no failure expected at all. Since the very design of the lower pair is to enable common mode rejection of external signals, it is likely that its work can be successfully achieved during the first 5 years of the mission.

  4. Control of training instrument

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  5. Regulation EM-GT-7. Quality control of the radiography equipment

    International Nuclear Information System (INIS)

    2015-01-01

    The purpose of this document is to provide practical guidance of technical procedures for carrying out quality control in X-ray equipment. This guide is applicable to general purpose radiography equipment, although some of the procedures may be applied to other types of diagnostic imaging equipment. The tests described require the appointed instrumentation and some of these can be implemented in the radiodiagnostic given the simplicity of them and others require special equipment and can be performed by external specialized groups to these units.

  6. Con Edison power failure of July 13 and 14, 1977. Final staff report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-06-01

    On July 13, 1977 the entire electric load of the Con Edison system was lost, plunging New York City and Westchester County into darkness. The collapse resulted from a combination of natural events, equipment malfunctions, questionable system-design features, and operating errors. An attempt is made in this report to answer the following: what were the specific causes of the failure; if equipment malfunctions and operator errors contributed, could they have been prevented; to what extent was Con Edison prepared to handle such an emergency; and did Con Edison plan prudently reserve generation, for reserve transmission capability, for automatic equipment to protect its system, and for proper operator response to a critical situation. Following the introductory and summary section, additional sections include: the Consolidated Edison system; prevention of bulk power-supply interruptions; the sequence of failure and restoration; analysis of the July 1977 power failure; restoration sequence and equipment damage assessment; and other investigations of the blackout. (MCW)

  7. Standard guide for corrosion-related failure analysis

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2000-01-01

    1.1 This guide covers key issues to be considered when examining metallic failures when corrosion is suspected as either a major or minor causative factor. 1.2 Corrosion-related failures could include one or more of the following: change in surface appearance (for example, tarnish, rust, color change), pin hole leak, catastrophic structural failure (for example, collapse, explosive rupture, implosive rupture, cracking), weld failure, loss of electrical continuity, and loss of functionality (for example, seizure, galling, spalling, swelling). 1.3 Issues covered include overall failure site conditions, operating conditions at the time of failure, history of equipment and its operation, corrosion product sampling, environmental sampling, metallurgical and electrochemical factors, morphology (mode) or failure, and by considering the preceding, deducing the cause(s) of corrosion failure. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibili...

  8. Rotary mode system initial instrument calibration

    International Nuclear Information System (INIS)

    Johns, B.R.

    1994-01-01

    The attached report contains the vendor calibration procedures used for the initial instrument calibration of the rotary core sampling equipment. The procedures are from approved vendor information files

  9. Equipment for oral surgery in small animals.

    Science.gov (United States)

    Reiter, Alexander M

    2013-05-01

    This article provides an overview of equipment used for oral surgery. Specific instruments and materials used when performing relevant operative procedures are also mentioned in other articles in this issue. Copyright © 2013 Elsevier Inc. All rights reserved.

  10. High energy arcing fault fires in switchgear equipment : a literature review.

    Energy Technology Data Exchange (ETDEWEB)

    Nowlen, Steven Patrick; Brown, Jason W.; Wyant, Francis John

    2008-10-01

    In power generating plants, switchgear provide a means to isolate and de-energize specific electrical components and buses in order to clear downstream faults, perform routine maintenance, and replace necessary electrical equipment. These protective devices may be categorized by the insulating medium, such as air or oil, and are typically specified by voltage classes, i.e. low, medium, and high voltage. Given their high energy content, catastrophic failure of switchgear by means of a high energy arcing fault (HEAF) may occur. An incident such as this may lead to an explosion and fire within the switchgear, directly impact adjacent components, and possibly render dependent electrical equipment inoperable. Historically, HEAF events have been poorly documented and discussed in little detail. Recent incidents involving switchgear components at nuclear power plants, however, were scrupulously investigated. The phenomena itself is only understood on a very elementary level from preliminary experiments and theories; though many have argued that these early experiments were inaccurate due to primitive instrumentation or poorly justified methodologies and thus require re-evaluation. Within the past two decades, however, there has been a resurgence of research that analyzes previous work and modern technology. Developing a greater understanding of the HEAF phenomena, in particular the affects on switchgear equipment and other associated switching components, would allow power generating industries to minimize and possibly prevent future occurrences, thereby reducing costs associated with repair and downtime. This report presents the findings of a literature review focused on arc fault studies for electrical switching equipment. The specific objective of this review was to assess the availability of the types of information needed to support development of improved treatment methods in fire Probabilistic Risk Assessment (PRA) for nuclear power plant applications.

  11. Frailty Assessment in Heart Failure: an Overview of the Multi-domain Approach.

    Science.gov (United States)

    McDonagh, Julee; Ferguson, Caleb; Newton, Phillip J

    2018-02-01

    The study aims (1) to provide a contemporary description of frailty assessment in heart failure and (2) to provide an overview of multi-domain frailty assessment in heart failure. Frailty assessment is an important predictive measure for mortality and hospitalisation in individuals with heart failure. To date, there are no frailty assessment instruments validated for use in heart failure. This has resulted in significant heterogeneity between studies regarding the assessment of frailty. The most common frailty assessment instrument used in heart failure is the Frailty Phenotype which focuses on five physical domains of frailty; the appropriateness a purely physical measure of frailty in individuals with heart failure who frequently experience decreased exercise tolerance and shortness of breath is yet to be determined. A limited number of studies have approached frailty assessment using a multi-domain view which may be more clinically relevant in heart failure. There remains a lack of consensus regarding frailty assessment and an absence of a validated instrument in heart failure. Despite this, frailty continues to be assessed frequently, primarily for research purposes, using predominantly physical frailty measures. A more multidimensional view of frailty assessment using a multi-domain approach will likely be more sensitive to identifying at risk patients.

  12. Executive dysfunction is independently associated with reduced functional independence in heart failure.

    Science.gov (United States)

    Alosco, Michael L; Spitznagel, Mary Beth; Raz, Naftali; Cohen, Ronald; Sweet, Lawrence H; Colbert, Lisa H; Josephson, Richard; van Dulmen, Manfred; Hughes, Joel; Rosneck, Jim; Gunstad, John

    2014-03-01

    To examine the independent association between executive function with instrumental activities of daily living and health behaviours in older adults with heart failure. Executive function is an important contributor to functional independence as it consists of cognitive processes needed for decision-making, planning, organising and behavioural monitoring. Impairment in this domain is common in heart failure patients and associated with reduced performance of instrumental activities of daily living in many medical and neurological populations. However, the contribution of executive functions to functional independence and healthy lifestyle choices in heart failure patients has not been fully examined. Cross-sectional analyses. One hundred and seventy-five heart failure patients completed a neuropsychological battery and echocardiogram. Participants also completed the Lawton-Brody Instrumental Activities of Daily Living Scale and reported current cigarette use. Hierarchical regressions revealed that reduced executive function was independently associated with worse instrumental activity of daily living performance with a specific association for decreased ability to manage medications. Partial correlations showed that executive dysfunction was associated with current cigarette use. Our findings suggest that executive dysfunction is associated with poorer functional independence and contributes to unhealthy behaviours in heart failure. Future studies should examine whether heart failure patients benefit from formal organisation schema (i.e. pill organisers) to maintain independence. Screening of executive function in heart failure patients may provide key insight into their ability to perform daily tasks, including the management of treatment recommendations. © 2013 John Wiley & Sons Ltd.

  13. Analysis on detection accuracy of binocular photoelectric instrument optical axis parallelism digital calibration instrument

    Science.gov (United States)

    Ying, Jia-ju; Yin, Jian-ling; Wu, Dong-sheng; Liu, Jie; Chen, Yu-dan

    2017-11-01

    Low-light level night vision device and thermal infrared imaging binocular photoelectric instrument are used widely. The maladjustment of binocular instrument ocular axises parallelism will cause the observer the symptom such as dizziness, nausea, when use for a long time. Binocular photoelectric equipment digital calibration instrument is developed for detecting ocular axises parallelism. And the quantitative value of optical axis deviation can be quantitatively measured. As a testing instrument, the precision must be much higher than the standard of test instrument. Analyzes the factors that influence the accuracy of detection. Factors exist in each testing process link which affect the precision of the detecting instrument. They can be divided into two categories, one category is factors which directly affect the position of reticle image, the other category is factors which affect the calculation the center of reticle image. And the Synthesize error is calculated out. And further distribute the errors reasonably to ensure the accuracy of calibration instruments.

  14. Maintenance and fabrication of electronic equipment

    International Nuclear Information System (INIS)

    Chung, Chong Eun; Moon, Byung Soo; Hong, Suk Boong; Kim, Yong Keun; Kim, Jung Bok

    2003-12-01

    Development of radiation monitoring equipment could be the base of domestic development of RMS. And the technique could be adapted to development of other radiation equipment of KAERI as well as hospitals and nuclear power plants. The RMS technology could be adapted to the development of precision instruments related to nuclear radiation and be the base of fundamental technology such as protein structure analysis of bio technology, development of nano advanced material and aircraft material. The technology of multi-channel readout ASIC for nuclear radiation detector, which has been imported from abroad, could be adapted to development of radiation equipment for image processing, position of detection, NDT etc., and also the technique will be expected to contribute to increase the use of radiation technology to industrial applications

  15. Lessons Learned From the Analysis of the SAFOD Downhole Instrument Package.

    Science.gov (United States)

    Johnson, Wade; Mencin, David; Mattioli, Glen

    2013-04-01

    In September of 2008 a downhole instrument package (DIP) consisting of a string of seismometers and tilt meters in isolated pressure vessels (PODs) was installed in the SAFOD main borehole. This package was designed to protect the sensors from the corrosive borehole environment and to operate for two years. The SAFOD borehole is not sealed at the bottom allowing borehole gasses and fluids infiltratration. Previous short-term installations of instruments in the SAFOD main borehole had also failed as a result of corrosion of the wireline cable head. The average failure time for these installations was two weeks. The use of stainless steel tubing connected to the pressure vessels through gas tight fittings was designed to block borehole fluid and gas infiltration of the individual instruments within the PODs. Unfortunately, the DIP completely failed within a month of its installation. In October of 2010, the DIP was removed from the borehole and a failure analysis was performed. This analysis involved to following steps: 1. Analysis of data to understand timeline of failure 2. Remove instrument safely, maintaining integrity of spliced section and documenting any external clues. Test instrument at surface 3. Open PODs in a way that allows for sampling and avoids damaging instruments. 4. Chemical analysis of fluids recovered from splices and PODs. 5. Instrument failure analysis by the instrument manufacturers. The analysis found that there were several design flaws in the DIP. This included the use of motor oil to take up air space in the individual PODs, use of a large number of gas tight seals, lack of internal seals, poorly done solder joints, use of non-temperature rated sensors, and lack of management oversight. The lessons learned from the attempts to instrument the SAFOD borehole are critical to the success of future deep borehole projects.

  16. Chief objectives of the development of X-ray equipment engineering in Russia

    International Nuclear Information System (INIS)

    Blinov, N.N.; Varshavskij, Yu.V.; Zelikman, M.I.

    1997-01-01

    Based on the world tendencies in the development of X-ray diagnostic instruments the main problems int he development of domestic X-ray diagnostic equipment engineering are analyzed. Variant of basic equipment for modern X-ray room for digital biomedical radiography is proposed. Tendencies int he instrumentation of X-ray diagnosis are the following ones: X-ray computerized tomograph creation, development of telecontrolled X-ray computerized. complexes for biomedical X-ray complexes for digital biomedical radiography, automation of the film development

  17. Development of digital power measuring and protecting equipment for SPRR-300 reactor

    International Nuclear Information System (INIS)

    Wang Xuejie; Li Xi'an; Zhu Shilei

    2005-01-01

    A measuring and protecting equipment of reactor power based on Single-Chip Microcomputer is introduced in this paper. The composition of hardware and the major control idea about the software for the equipment are presented. Digitizing the measuring data from nuclear instruments is precondition of reactor control and protection system which would be computerizing, and it is also an application of redundancy and variety of reactor protection system in nuclear measuring instruments. At last the working state is described. (authors)

  18. Environment for the instruments

    International Nuclear Information System (INIS)

    Ambro, P.

    1992-01-01

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

  19. Environment for the instruments

    Energy Technology Data Exchange (ETDEWEB)

    Ambro, P

    1993-12-31

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

  20. Integrated reliability condition monitoring and maintenance of equipment

    CERN Document Server

    Osarenren, John

    2015-01-01

    Consider a Viable and Cost-Effective Platform for the Industries of the Future (IOF) Benefit from improved safety, performance, and product deliveries to your customers. Achieve a higher rate of equipment availability, performance, product quality, and reliability. Integrated Reliability: Condition Monitoring and Maintenance of Equipment incorporates reliable engineering and mathematical modeling to help you move toward sustainable development in reliability condition monitoring and maintenance. This text introduces a cost-effective integrated reliability growth monitor, integrated reliability degradation monitor, technological inheritance coefficient sensors, and a maintenance tool that supplies real-time information for predicting and preventing potential failures of manufacturing processes and equipment. The author highlights five key elements that are essential to any improvement program: improving overall equipment and part effectiveness, quality, and reliability; improving process performance with maint...

  1. Analysis of NPP pipes and equipment damage in life time prolongation

    International Nuclear Information System (INIS)

    Tkachev, V.V.; Zheltukhin, K.K.

    2008-01-01

    Paper describes a procedure to calculate the probability of pipes and equipment failure taking account of both the service records of the structures under various conditions and their aging. The parameters characterizing applied loads, failures, as well as metal strength, mechanical and thermal properties serve as the arbitrary values used in the described procedure. Paper presents an example of the probability calculation of failure of the RBMK emergency feed pump recirculation pipes when their service life is prolonged [ru

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

    International Nuclear Information System (INIS)

    Abad Bassols, L.; Nino Perote, R.

    1996-01-01

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

  3. Report of the Instrumentation Service - Annex C

    International Nuclear Information System (INIS)

    Mikic, N.

    1999-01-01

    This report describes the tasks and organizational structure of the Instrumentation service. The most important task of this Service is control and maintenance of the reactor control and protection instruments, operation control, and dosimetry system. Besides data about this basic instrumentation, the report includes data about control and maintenance of other electronic equipment, inspection of the reactor vessel and spent fuel storage pool and describes activities related control and maintenace of the experimental devices [sr

  4. Report of the Instrumentation Service - Annex C

    International Nuclear Information System (INIS)

    Mikic, N.

    2000-01-01

    This report describes the tasks and organizational structure of the Instrumentation service. The most important task of this Service is control and maintenance of the reactor control and protection instruments, operation control, and dosimetry system. Besides data about this basic instrumentation, the report includes data about control and maintenance of other electronic equipment, inspection of the reactor vessel and spent fuel storage pool and describes activities related control and maintenace of the experimental devices [sr

  5. Report of the electric Equipment Service - Annex E

    International Nuclear Information System (INIS)

    Karic, Z.

    2002-01-01

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period. Activity plan for year 2002 is included [sr

  6. Improving FMEA risk assessment through reprioritization of failures

    Science.gov (United States)

    Ungureanu, A. L.; Stan, G.

    2016-08-01

    Most of the current methods used to assess the failure and to identify the industrial equipment defects are based on the determination of Risk Priority Number (RPN). Although conventional RPN calculation is easy to understand and use, the methodology presents some limitations, such as the large number of duplicates and the difficulty of assessing the RPN indices. In order to eliminate the afore-mentioned shortcomings, this paper puts forward an easy and efficient computing method, called Failure Developing Mode and Criticality Analysis (FDMCA), which takes into account the failures and the defect evolution in time, from failure appearance to a breakdown.

  7. Performance specifications for health physics instrumentation: portable instrumentation for use in normal work environments. Part 2. Test results

    International Nuclear Information System (INIS)

    Kenoyer, J.L.; Swinth, K.L.; Stoetzel, G.A.; Selby, J.M.

    1986-09-01

    The Pacific Northwest Laboratory evaluated a draft American National Standards Institute Standard N42.17 (ANSI N42.17) on performance specifications for health physics instrumentation through a project jointly funded by the US Department of Energy and the US Nuclear Regulatory Commission. The evaluation involved testing a representative cross section of instruments against criteria in the standard. This report presents results of the testing program. A brief history of the project is included in the introduction. The instrumentation tested is described in general terms (i.e., types, ranges); however, no direct relationship between the results and a specific instrument model is made in this report. Testing requirements in ANSI N42.17D4, Revision 1 (May 1985) are summarized and the methods by which the tests are performed are discussed. Brief descriptions of the testing equipment are included in the methods section of the report. More detailed information about the draft standard, testing requirements and procedures, and the test equipment is included in ''Performance Specifications for Health Physics Instrumentation - Portable Instrumentation for Use in Normal Work Environments, Part 1: Manual of Testing Procedures.'' Results of testing are given in two formats: test-by-test and instrument-by-instrument. Discussion is included on significant and interesting findings, on comparisons of results from the same type of instruments from same and different manufacturers, and on data grouped by manufacturer. Conclusions are made on the applicability and practicality of the proposed standard and on instrument performance. Changes that have been made to the proposed standard based on findings of the testing program are listed and discussed. 22 refs., 11 figs., 77 tabs

  8. A Study on Performance and Safety Tests of Electrosurgical Equipment

    Directory of Open Access Journals (Sweden)

    Tavakoli Golpaygani A.

    2016-09-01

    Full Text Available Introduction: Modern medicine employs a wide variety of instruments with different physiological effects and measurements. Periodic verifications are routinely used in legal metrology for industrial measuring instruments. The correct operation of electrosurgical generators is essential to ensure patient’s safety and management of the risks associated with the use of high and low frequency electrical currents on human body. Material and Methods: The metrological reliability of 20 electrosurgical equipment in six hospitals (3 private and 3 public was evaluated in one of the provinces of Iran according to international and national standards. Results: The achieved results show that HF leakage current of ground-referenced generators are more than isolated generators and the power analysis of only eight units delivered acceptable output values and the precision in the output power measurements was low. Conclusion: Results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially in high risk instruments. It is also necessary to provide training courses for operating staff in the field of meterology in medicine to be acquianted with critical parameters to get accuracy results with operation room equipment.

  9. Safety systems I/C equipment reliability analyses of the Kozloduy NPP units 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Halev, G; Christov, N [Risk Engineering Ltd., Sofia (Bulgaria)

    1996-12-31

    The purpose of the analysis is to assess the safety systems I/C equipment reliability. The assessment includes: quantification of the safety systems unavailability due to component failures; definition of the minimal cut sets leading to the analysed safety systems failure; quantification of the I/C equipment importance measures of the dominant contribution components. The safety systems I/C equipment reliability has been analysed using PSAPACK (a code for probabilistic safety assessment). Fault trees for the following safety systems of the Kozloduy-3 and Kozloduy-4 reactors have been constructed: neutron flow control equipment, reactor protection system, main coolant pumps, pressurizer safety valves `Sempell`, steam dump systems, spray system, low pressure injection system, emergency feeding water system, essential service water system. THree separate reports have been issued containing the performed analyses and results. 1 ref.

  10. Assessment of electrical equipment aging for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The electrical and instrumentation equipments, especially whose parts are made of polymer material, are gradually degraded by thermal and radiation environment in the normal operation, and the degradation is thought to progress rapidly when they are exposed to the environment of the design basis event (DBE). The integrity of the equipments is evaluated by the environmental qualification (EQ) test simulating the environment of the normal operation and the DBE. The project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) indicated the importance of applying simultaneous thermal and radiation aging for simulating the aging in normal operation. The project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008 to apply the outcome of ACA to the other electrical and instrumentation equipment and to establish an advanced EQ test method that can appropriately simulate the environment in actual plants. In FY2012, aging characteristics of thermal aging and simultaneous aging were obtained for the epoxy resin of electrical penetrations and the O-ring of connectors. Physical property measurement was carried out for epoxy resin of electrical penetration subject to the type testing in FY2010. (author)

  11. Assessment of electrical equipment aging for nuclear power plant

    International Nuclear Information System (INIS)

    2013-01-01

    The electrical and instrumentation equipments, especially whose parts are made of polymer material, are gradually degraded by thermal and radiation environment in the normal operation, and the degradation is thought to progress rapidly when they are exposed to the environment of the design basis event (DBE). The integrity of the equipments is evaluated by the environmental qualification (EQ) test simulating the environment of the normal operation and the DBE. The project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) indicated the importance of applying simultaneous thermal and radiation aging for simulating the aging in normal operation. The project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008 to apply the outcome of ACA to the other electrical and instrumentation equipment and to establish an advanced EQ test method that can appropriately simulate the environment in actual plants. In FY2012, aging characteristics of thermal aging and simultaneous aging were obtained for the epoxy resin of electrical penetrations and the O-ring of connectors. Physical property measurement was carried out for epoxy resin of electrical penetration subject to the type testing in FY2010. (author)

  12. Common cause failures of reactor pressure components

    International Nuclear Information System (INIS)

    Mankamo, T.

    1978-01-01

    The common cause failure is defined as a multiple failure event due to a common cause. The existence of common failure causes may ruin the potential advantages of applying redundancy for reliability improvement. Examples relevant to large mechanical components are presented. Preventive measures against common cause failures, such as physical separation, equipment diversity, quality assurance, and feedback from experience are discussed. Despite the large number of potential interdependencies, the analysis of common cause failures can be done within the framework of conventional reliability analysis, utilizing, for example, the method of deriving minimal cut sets from a system fault tree. Tools for the description and evaluation of dependencies between components are discussed: these include the model of conditional failure causes that are common to many components, and evaluation of the reliability of redundant components subjected to a common load. (author)

  13. Unified electronic unit for miniature radioactivity logging equipment

    International Nuclear Information System (INIS)

    Bragin, A.A.; Goldshtejn, L.M.; Fedorov, R.F.; Shikhman, A.S.

    1981-01-01

    Appropriateness and urgency of the unification of components of radioactivity logging equipment used for the investigation of wells at solid mineral deposits is substantiated. A two-channel electronic unit for miniature equipment for radioactivity logging is described and its basic specifications and performance are given. All functional assemblies of the unit are structurally made in the form of printed circuit boards placed in a pan-shaped chassis 28 mm in diameter. The unit's general design provides for the possibility to attach two probes with detection devices to the unit. The unit is used in the two-channel radioactivity logging instrument ''Kura-2'' and in the two-channel radiometer ''RUR-2''. The outer diameter of these instruments is 48 mm and they ensure the investigation of ore and coal wells with a combination radioactivity methods [ru

  14. Single-purpose nuclear medicine instruments

    International Nuclear Information System (INIS)

    Boucek, J.

    Nuclear medicine requires the most up-to-date specialized technical facilities. The paper underlines the factor of reliability in purpose-designed equipment used for basic examinations. The possibility is also discussed of the automation of standard nuclear medicine instruments

  15. Design and construction rules for electrical equipments of nuclear islands. 3. ed.

    International Nuclear Information System (INIS)

    1993-01-01

    The French design and construction for electrical equipments of nuclear islands (RCC-E) deals with equipments of which the failure may have consequences on the safety of persons or appreciable effects on the availability of the power plant. This book presents the rules concerning (1) qualification procedure, (2) the design of functional units, (3) the installation (environmental conditions, protection rules), (4) the constituent elements of equipments, (5) the control and testing methods

  16. Cold Vacuum Drying Instrument Air System Design Description. System 12

    International Nuclear Information System (INIS)

    SHAPLEY, B.J.; TRAN, Y.S.

    2000-01-01

    This system design description (SDD) addresses the instrument air (IA) system of the spent nuclear fuel (SNF). This IA system provides instrument quality air to the Cold Vacuum Drying (CVD) Facility. The IA system is a general service system that supports the operation of the heating, ventilation, and air conditioning (HVAC) system, the process equipment skids, and process instruments in the CVD Facility. The following discussion is limited to the compressor, dryer, piping, and valving that provide the IA as shown in Drawings H-1-82222, Cold Vacuum Drying Facility Mechanical Utilities Compressed and Instrument Air PandID, and H-1.82161, Cold Vacuum Drying Facility Process Equipment Skid PandID MCO/Cusk Interface. Figure 1-1 shows the physical location of the 1A system in the CVD Facility

  17. Cold Vacuum Drying Instrument Air System Design Description (SYS 12)

    Energy Technology Data Exchange (ETDEWEB)

    SHAPLEY, B.J.; TRAN, Y.S.

    2000-06-05

    This system design description (SDD) addresses the instrument air (IA) system of the spent nuclear fuel (SNF). This IA system provides instrument quality air to the Cold Vacuum Drying (CVD) Facility. The IA system is a general service system that supports the operation of the heating, ventilation, and air conditioning (HVAC) system, the process equipment skids, and process instruments in the CVD Facility. The following discussion is limited to the compressor, dryer, piping, and valving that provide the IA as shown in Drawings H-1-82222, Cold Vacuum Drying Facility Mechanical Utilities Compressed & Instrument Air P&ID, and H-1.82161, Cold Vacuum Drying Facility Process Equipment Skid P&ID MCO/Cusk Interface. Figure 1-1 shows the physical location of the 1A system in the CVD Facility.

  18. Ageing of instrumentation and control cables in NPPs

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  19. On reliability and maintenance modelling of ageing equipment in electric power systems

    International Nuclear Information System (INIS)

    Lindquist, Tommie

    2008-04-01

    Maintenance optimisation is essential to achieve cost-efficiency, availability and reliability of supply in electric power systems. The process of maintenance optimisation requires information about the costs of preventive and corrective maintenance, as well as the costs of failures borne by both electricity suppliers and customers. To calculate expected costs, information is needed about equipment reliability characteristics and the way in which maintenance affects equipment reliability. The aim of this Ph.D. work has been to develop equipment reliability models taking the effect of maintenance into account. The research has focussed on the interrelated areas of condition estimation, reliability modelling and maintenance modelling, which have been investigated in a number of case studies. In the area of condition estimation two methods to quantitatively estimate the condition of disconnector contacts have been developed, which utilise results from infrared thermography inspections and contact resistance measurements. The accuracy of these methods were investigated in two case studies. Reliability models have been developed and implemented for SF6 circuit-breakers, disconnector contacts and XLPE cables in three separate case studies. These models were formulated using both empirical and physical modelling approaches. To improve confidence in such models a Bayesian statistical method incorporating information from the equipment design process was also developed. This method was illustrated in a case study of SF6 circuit-breaker operating rods. Methods for quantifying the effect of maintenance on equipment condition and reliability have been investigated in case studies on disconnector contacts and SF6 circuit-breakers. The input required by these methods are condition measurements and historical failure and maintenance data, respectively. This research has demonstrated that the effect of maintenance on power system equipment may be quantified using available data

  20. Analysis of the failures and corrective actions for the LHC cryogenics radiation tolerant electronics and its field instruments

    Energy Technology Data Exchange (ETDEWEB)

    Balle, Christoph; Casas, Juan; Vauthier, Nicolas [CERN, TE Department, 1211 Geneva (Switzerland)

    2014-01-29

    The LHC cryogenic system radiation tolerant electronics and their associated field instruments have been in nominal conditions since before the commissioning of the first LHC beams in September 2008. This system is made of about 15’000 field instruments (thermometers, pressure sensors, liquid helium level gauges, electrical heaters and position switches), 7’500 electronic cards and 853 electronic crates. Since mid-2008 a software tool has been deployed, this allows an operator to report a problem and then lists the corrective actions. The tool is a great help in detecting recurrent problems that may be tackled by a hardware or software consolidation. The corrective actions range from simple resets, exchange of defective equipment, repair of electrical connectors, etc. However a recurrent problem that heals by itself is present on some channels. This type of fault is extremely difficult to diagnose and it appears as a temporary opening of an electrical circuit; its duration can range from a few minutes to several months. This paper presents the main type of problems encountered during the last four years, their evolution over time, the various hardware or software consolidations that have resulted and whether they have had an impact in the availability of the LHC beam.

  1. Maintenance and fabrication of nuclear electronic equipment

    International Nuclear Information System (INIS)

    Hong, Seok Boong; Chung, Chong Eun; Hwang, In Koo; Koo, In Soo; Park, Bum; Kim, Soo Hee; Lee, Seong Joo; Kim, Min Seok; Choi, Wha Lim

    2011-12-01

    - process equipment at PIEF, Chemical Analysis Team and RWFTF have been calibrated. - The electronic equipment and radiation equipment at RWTF and PIEF have been prepared. - Development and installation of integrated RMS software for Hanaro Cold Neutron Laboratory Building(CNLB) RMS, and development and performance upgrade of a portal monitor for CNLB. - Performance test of the Hardware/Software of digital unit controller has been performed, and functional upgrade of the Hardware/Software of stimulator for SMART MMIS performance test facility has also been performed. - A controller of high voltage power supply for a small electron beam generator and a controller for razer pinning and a remote monitoring apparatus of cathode power supply for a 0.2 Mev. small electron beam generator have been designed and fabricated. - Database construction for effective maintenance for the process equipment and radiation instruments are designed and constructed

  2. Service for maintenance of electronic equipment of the RA reactor, Report for 1977 - Annex IV

    International Nuclear Information System (INIS)

    Milosevic, M.

    1977-01-01

    This report describes the tasks and organizational structure of the Service for maintenance of electronic equipment of the RA reactor. The most important task of this Service is control and maintenance of the reactor control and protection instruments, operation control, and dosimetry system. Besides data about this basic instrumentation, the report includes data about control and maintenance of other electronic equipment related to the experimental devices [sr

  3. An optimal inspection strategy for randomly failing equipment

    International Nuclear Information System (INIS)

    Chelbi, Anis; Ait-Kadi, Daoud

    1999-01-01

    This paper addresses the problem of generating optimal inspection strategies for randomly failing equipment where imminent failure is not obvious and can only be detected through inspection. Inspections are carried out following a condition-based procedure. The equipment is replaced if it has failed or if it shows imminent signs of failure. The latter state is indicated by measuring certain predetermined control parameters during inspection. Costs are associated with inspection, idle time and preventive or corrective actions. An optimal inspection strategy is defined as the inspection sequence minimizing the expected total cost per time unit over an infinite span. A mathematical model and a numerical algorithm are developed to generate an optimal inspection sequence. As a practical example, the model is applied to provide a machine tool operator with a time sequence for inspecting the cutting tool. The tool life time distribution and the trend of one control parameter defining its actual condition are supposed to be known

  4. Some suggestions based on the instrumentation installation experience at RAPP

    International Nuclear Information System (INIS)

    Raghunath, M.R.; Singh, S.; Jain, V.K.

    1977-01-01

    Suggestions regarding installation of reactor instrumentation have been made based on the instrumentation installation experience at the Rajasthan Atomic Power Plant. It has been mentioned that the instrumentation installation work has to proceed simultaneously with that of the heavy equipment and piping errection work, to meet the commissioning target dates. (S.K.K.)

  5. Statistical analysis of operating efficiency and failures of a medical linear accelerator for ten years

    International Nuclear Information System (INIS)

    Ju, Sang Gyu; Huh, Seung Jae; Han, Young Yih

    2005-01-01

    To improve the management of a medical linear accelerator, the records of operational failures of a Varian CL2100C over a ten year period were retrospectively analyzed. The failures were classified according to the involved functional subunits, with each class rated into one of three levels depending on the operational conditions. The relationships between the failure rate and working ratio and between the failure rate and outside temperature were investigated. In addition, the average life time of the main part and the operating efficiency over the last 4 years were analyzed. Among the recorded failures (total 587 failures), the most frequent failure was observed in the parts related with the collimation system, including the monitor chamber, which accounted for 20% of all failures. With regard to the operational conditions, 2nd level of failures, which temporally interrupted treatments, were the most frequent. Third level of failures, which interrupted treatment for more than several hours, were mostly caused by the accelerating subunit. The number of failures was increased with number of treatments and operating time. The average life-times of the Klystron and Thyratron became shorter as the working ratio increased, and were 42 and 83% of the expected values, respectively. The operating efficiency was maintained at 95% or higher, but this value slightly decreased. There was no significant correlation between the number of failures and the outside temperature. The maintenance of detailed equipment problems and failures records over a long period of time can provide good knowledge of equipment function as well as the capability of predicting future failure. More rigorous equipment maintenance is required for old medical linear accelerators for the advanced avoidance of serious failure and to improve the quality of patient treatment

  6. Assessment of the impact of fueling machine failure on the safety of the CANDU-PHWR

    International Nuclear Information System (INIS)

    Al-Kusayer, T.A.

    1982-01-01

    A survey of possible LOCA (Loss-of-Coolant Accident) initiating events that might take place for CANDU-PHWRs (Canadian Deuterium Uranium-Pressurized Heavy Water Reactors) has been conducted covering both direct and indirect initiators. Among the 22 initiating events that were surveyed in this study, four direct initiators have been selected and analyzed briefly. Those selected were a pump suction piping break, an isolation valve piping break, a bleed valve failure, and a fueling machine interface failure. These were selected as examples of failures that could take place in the inlet side, outlet side, or PHTS (Primary Heat Transport System) interfaces. The Pickering NGS (Unit-A) was used for this case study. Double failure (failure of the protective devices to operate when the process equipment fault occurs) and a triple failure (failure of the protective devices and the ECCS as well as the process equipment) were found to be highly improbable

  7. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  8. Performing instrumentation and controls upgrades

    International Nuclear Information System (INIS)

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

    1992-01-01

    I and C upgrades are comprised of a varying range of content, complexity, expansiveness, and criticality. There are common threads in all upgrades which can be simplified by the development of a long term I and C upgrade plan. The development of a such a plan can establish effective ground rules for upgrades, large and small. It can be the basis from which to begin an upgrade evaluation and the standard which is used to compare the degree of compliance of any upgrade regarding the plan or to define the differences from the plan and an individual upgrade. Primary motivation for I and C upgrades are obsolescence and unavailability of spare parts. Numerous other areas of consideration are also involved in an upgrade. Today's technology results in most upgrades largely or totally utilizing digital equipment. The use of digital equipment is fairly new in many I and C applications and requires an elaborate evaluation from functional, qualification, operational, and licensing perspectives as well as others. A well defined upgrade plan developed as a basis for I and C upgrades is a significant start to ensuring an effective upgrade process. Properly developed and implemented, the plan will support I and C upgrade efforts to ensure that the intricacies associated with such tasks eliminate the existing problems which require the upgrade to be performed. The upgrade plan also results in ensuring the maximum benefit from all perspectives of the plant enhancements being carried out and considered for future implementation. Instrumentation and controls aging and replacement are issues of growing importance due to the potential for significant impact on plant operation and efficiency. Obsolescence and unavailability of spare parts are major drivers towards evaluating the cost benefits of upgrading current equipment. In addition to these two primary factors, the advantages of utilizing digital equipment have also become of prime importance when evaluating instrumentation and

  9. Mission Analysis for Using Preventive Radiological/Nuclear Detection Equipment for Consequence Management

    Energy Technology Data Exchange (ETDEWEB)

    Buddemeier, Brooke R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wood-Zika, Annmarie R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Haynes, Daniel [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Klemic, Gladys A. [US Dept. of Homeland Security National Urban Security Technology Lab., Manhattan, NY (United States); Musolino, Stephen V. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2017-09-01

    The overall objective of this project is to research, evaluate, and test first responder preventive radiological/nuclear detection (PRND) equipment to provide state and local agencies with scientific guidance on how to effectively use this equipment for response after a radiological/nuclear release or detonation. While the equipment being tested in this effort has been specifically designed by technology manufacturers and purchased by responders for preventive detection and source interdiction operations, the fleet of PRND equipment can help fill critical needs for radiological instrumentation should a consequence management (CM) response take place, as it is currently the most widely available and fielded radiological instrumentation by state and local agencies. This effort will provide scientific guidance on the most effective way to utilize this class of equipment for consequence management missions. Gaining a better understanding of how PRND equipment can operate and perform for these missions will allow for recommendations on the tactical approach responders can use for consequence management operations. PRND equipment has been placed into service by federal, state, and local agencies throughout the nation. If the equipment capability and limitations are taken into account, this large inventory can be leveraged to support the emergency response in the aftermath of a radiological or nuclear event. With several hundred makes and models of PRND equipment, often with significantly different detection capabilities that do not align with their nominal PRND equipment type, development of a streamlined categorization scheme with respect to consequence management missions was the first step to identifying safe and effective uses of PRND equipment for radiological/nuclear incident response.

  10. Machinery failure analysis and troubleshooting practical machinery management for process plants

    CERN Document Server

    Bloch, Heinz P

    2012-01-01

    Solve the machinery failure problems costing you time and money with this classic, comprehensive guide to analysis and troubleshooting  Provides detailed, complete and accurate information on anticipating risk of component failure and avoiding equipment downtime Includes numerous photographs of failed parts to ensure you are familiar with the visual evidence you need to recognize Covers proven approaches to failure definition and offers failure identification and analysis methods that can be applied to virtually all problem situations Demonstr

  11. ANALISIS TOTAL PRODUCTIVE MAINTENANCE DENGAN METODE OVERALL EQUIPMENT EFFECTIVENESS DAN FUZZY FAILURE MODE AND EFFECTS ANALYSIS

    Directory of Open Access Journals (Sweden)

    Supriyadi Supriyadi

    2017-11-01

    Full Text Available Ash Handling System merupakan suatu bagian dari pembangkit listrik tenaga uap dengan bahan bakar batu bara yang berfungsi untuk menyalurkan limbah pembuangan sisa hasil proses pembakaran batu bara pada boiler. Sisa pembakaran terbagi menjadi fly ash dan bottom ash. Untuk sisa pembakaran fly ash akan disalurkan menuju ke Electrostatic Precipitator untuk ditangkap  dengan metode corona dan ditransfer menuju penampungan fly ash dengan cara dimampatkan bersama udara dari kompresor yang melalui pipa-pipa dan tabung transporter. Sedangkan untuk sisa pembakaran bottom ash akan disalurkan dengan alat yang disebut SSC (Submerged Scraper Conveyor. Gangguan pada SSC dapat terjadi mulai dari belt putus, masalah pada penggerak, hingga masalah pada kelistrikan dan instrumennya. Penelitian ini bertujuan untuk mengetahui nilai OEE, mengetahui dampak gangguan belt sobek, mengetahui penyebab terjadinya belt conveyor sobek dan melakukan estimasi hasil perbaikan dari sisi biaya. Penelitian ini menggunakan metode Overall Equipment Effectiveness (OEE dan Fuzzy Failure Mode and Effects Analysis. Hasil penelitian menunjukkan bahwa rata-rata nilai OEE pada tahun 2015 sekitar 52,05%, masih di bawah standar nilai OEE sebesar 85%. Penyebab utamanya adalah adanya gangguan belt sobek karena gesekan belt dengan support return ketika belt conveyor mengalami jogging yang berdampak pada terganggunya penyaluran abu. Modifikasi dapat menghindari kerugian perusahaan sebesar Rp. 582.548.800,00.

  12. Gearbox Instrumentation for the Investigation of Bearing Axial Cracking

    Energy Technology Data Exchange (ETDEWEB)

    Keller, Jonathan A [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Lambert, Scott R [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-03-27

    Failures in gearbox bearings have been the primary source of reliability issues for wind turbine drivetrains, leading to costly downtime and unplanned maintenance. The most common failure mode is attributed to so-called axial cracks or white-etching cracks, which primarily affect the intermediate and high-speed-stage bearings. The high-speed-shaft and bearing loads and sliding will be measured with a specially instrumented gearbox installed in a 1.5-megawatt turbine at the National Wind Technology Center in an upcoming test campaign. Additional instrumentation will also measure the tribological environment of these bearings, including bearing temperatures, lubricant temperature and water content, air temperature and humidity, and stray electrical current across the bearings. This paper fully describes the instrumentation package and summarizes initial results.

  13. 21 CFR 864.3010 - Tissue processing equipment.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Tissue processing equipment. 864.3010 Section 864.3010 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL DEVICES HEMATOLOGY AND PATHOLOGY DEVICES Pathology Instrumentation and Accessories § 864.3010...

  14. Use of fuel reprocessing plant instrumentation for international safeguards

    International Nuclear Information System (INIS)

    Ayers, A.L.

    1977-01-01

    The International Atomic Energy Agency has a program for developing instrumentation to be used by safeguards inspectors at reprocessing facilities. These instruments have generally been individual pieces of equipment for improving the accuracy of existing measurement instrumentation or equipment to perform nondestructive assay on a selected basis. It is proposed that greater use be made of redundant plant instrumentation and data recovery systems that could augment plant instrumentation to verify the validity of plant measurements. Use of these methods for verfication must be proven as part of an operating plant before they can be relied upon for safeguards surveillance. Inspectors must be qualified in plant operations, or have ready access to those so qualified, if the integrity of the operation is to be properly assessed. There is an immediate need for the development and in-plant proof testing of an integrated gamma, passive neutron, and active neutron measurement system for drum quantities of radioactive trash. The primary safeguards effort should be limited to plutonium and highly enriched uranium

  15. Electrical and control equipment in nuclear power plants. Problems when replacing aging equipment; El och kontrollutrustning i kaernkraftverk - Problematik vid utbyte av aaldrad utrustning

    Energy Technology Data Exchange (ETDEWEB)

    Nordling, Anna; Haakansson, Goeran

    2012-11-01

    Interoperability between different technical systems is more complicated when old and new technology meet, such as between analog and digital technology. New electrical and I and C equipment is selected with consideration to simplify and improve the compatibility and interoperability. The original construction of nuclear power plants with electricity and I and C equipment had more natural interfaces. Generally experienced guidance, to the management of interoperability and interfaces, feels insufficient. Skills transfer programs are identified as a major need, as more and more important personnel are retiring and important information is lost with them. Lack of appropriate skills directly affects the ability to produce accurate and complete requirements specification. Failure modes of newer electrical and I and C equipment are perceived as more complex than the older equipment. When choosing equipment, attempts are made to minimize unnecessary features, to reduce the number of potential failure modes. There is a lack of consistent understanding of the meaning of robustness in electrical technology and I and C technology, in the nuclear plant engineering departments. The overall picture is that the robustness has worsened since the facilities were built. The Swedish nuclear power plants have an internal organizational structure with separated client and support organization. This splits the nuclear organization into two distinct parts which threaten to separate the two entities focus. Engineering departments at the Swedish nuclear power plants express a need for increased expertise in the client organization (blocks). Competence requested is for example, system knowledge to facilitate and enhance the quality of the initial analysis performed in the blocks. Suppliers receive more recently larger turnkey projects, both to minimize costs but also to minimize the interfaces and co-function problems. This, however, heightens demands for knowledge transfer between

  16. Providing nuclear reactor control information in the presence of instrument failures

    International Nuclear Information System (INIS)

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

    1986-01-01

    A technique for using unfailed instrument outputs to generate optimal estimates of failed sensor outputs is presented and evaluated. The technique uses a bank of discrete, linear Kalman filters, each dedicated to one instrument, and a combinatory logic to perform the output estimation. The technique is tested using measurement data from a university research reactor

  17. Frequency Analysis of Failure Scenarios from Shale Gas Development.

    Science.gov (United States)

    Abualfaraj, Noura; Gurian, Patrick L; Olson, Mira S

    2018-04-29

    This study identified and prioritized potential failure scenarios for natural gas drilling operations through an elicitation of people who work in the industry. A list of twelve failure scenarios of concern was developed focusing on specific events that may occur during the shale gas extraction process involving an operational failure or a violation of regulations. Participants prioritized the twelve scenarios based on their potential impact on the health and welfare of the general public, potential impact on worker safety, how well safety guidelines protect against their occurrence, and how frequently they occur. Illegal dumping of flowback water, while rated as the least frequently occurring scenario, was considered the scenario least protected by safety controls and the one of most concern to the general public. In terms of worker safety, the highest concern came from improper or inadequate use of personal protective equipment (PPE). While safety guidelines appear to be highly protective regarding PPE usage, inadequate PPE is the most directly witnessed failure scenario. Spills of flowback water due to equipment failure are of concern both with regards to the welfare of the general public and worker safety as they occur more frequently than any other scenario examined in this study.

  18. The research on the failure regularity of GM counter tubes

    International Nuclear Information System (INIS)

    Li Jiyuan; Huai Guangli; Xie Bo; Zhang Hao

    2002-01-01

    The reliability of GM counter tubes should be described by useful time before failure-life and failure rate during life. A new method to study the failure regularity of GM counter tubes is advanced and adopted. The essential point of the method is that after the GM counter tubes of the instruments in use is tested, both the performance parameters and other information of the GM counter tubes and the instruments collected are recorded. Then database is created. Failure criterion is ascertained. The GM counter tubes are inspected to determine whether they are failure. Failure mode should be decided if the GM counter tubes failure. The GM counter tubes with the same useful year come together to make up a subsample. According to the relevant information, the number of the subsample is restored to the number of the sample that initially put into use. Then the number of failure sample is counted and at the same time the distribution of failure mode is got. The parameter m, γ, t 0 of Weibull distribution function are calculated with method of linear fit. Thus mean life, failure rate and other character values are obtained. Using this method, useful life and failure rate are determined. The conclusion is that the useful life is 18-20 years and the failure rate is 5 x 10 -6 and 4 x 10 -6 /h respectively during the course

  19. International economic association on production of nuclear instrumentation - ''INTERINSTRUMENT''

    International Nuclear Information System (INIS)

    Twardon, Z.

    1979-01-01

    History of establishment and development of the International economic association ''Interinstrument'' is stated. Structure of the Association is given and directions of its activity, as well as structure of its budget. List is given of organizations, performing works according to the agreements with the Association. Main directions are stated of activity of the Association in the field of specialization of production of items of nuclear equipment; co-ordination of activity in the sphere of foreign trade; information about new instruments. Activity is stated of the branch offices of the Association, engaged in maintenance of instruments and nuclear equipment [ru

  20. Low Cost Science Teaching Equipment for Visually Impaired Children

    Science.gov (United States)

    Gupta, H. O.; Singh, Rakshpal

    1998-05-01

    A low cost null detector an electronic thermometer and a colorimeter have been designed and developed for enabling visually impaired children (VIC) to do experiments in science that normally are accessible only to sighted children. The instruments are based on audio null detection in a balanced bridge and use a themistor for sensing the temperature and an LDR for color change. The analog output can be tactually read by VIC. The equipment has been tested for suitability with VIC. The approach followed in developing these equipment would be generally appropriate to a wide variety of science equipment for VIC by incorporating suitable sensors.

  1. 14 CFR 91.205 - Powered civil aircraft with standard category U.S. airworthiness certificates: Instrument and...

    Science.gov (United States)

    2010-01-01

    ... type of operation, and those instruments and items of equipment are in operable condition. (b) Visual... required instruments and equipment; and (7) Radar altimeter. (i) Exclusions. Paragraphs (f) and (g) of this... Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC...

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

    International Nuclear Information System (INIS)

    Fryer, M.O.

    1984-01-01

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

  3. Engineering electrodynamics electric machine, transformer, and power equipment design

    CERN Document Server

    Turowski, Janusz

    2013-01-01

    Due to a huge concentration of electromagnetic fields and eddy currents, large power equipment and systems are prone to crushing forces, overheating, and overloading. Luckily, power failures due to disturbances like these can be predicted and/or prevented.Based on the success of internationally acclaimed computer programs, such as the authors' own RNM-3D, Engineering Electrodynamics: Electric Machine, Transformer, and Power Equipment Design explains how to implement industry-proven modeling and design techniques to solve complex electromagnetic phenomena. Considering recent progress in magneti

  4. Usefulness of ACR MRI phantom for quality assurance of MRI instruments

    International Nuclear Information System (INIS)

    Lee, Jung Whee; Ahn, Kook Jin; Lee, Seung Koo; Na, Dong Gyu; Oh, Chang Hyun; Chang, Yong Min; Lim, Tae Hwan

    2006-01-01

    To examine whether the ACR phantom could be used in quality standards for magnetic resonance imaging (MRI) instruments in Korea. We conducted the phantom test using the ACR MRI phantom in 20 MRI instruments currently used in Korea. According to ACR criteria, we acquired the phantom images which were then assessed by the following seven tests: geometric accuracy, high spatial resolution, slice thickness accuracy, slice position accuracy, image intensity uniformity, percent signal ghosting, and low contrast object detectability. The phantom images were interpreted by three experienced radiologists according to ACR criteria. Then, we examined the failure rate of each test and evaluated the inter-observer variation in the measurements and test failure. The failure rate of each test could be broken into the following components: geometric accuracy (11-21%), high contrast spatial resolution (10-15%), slice thickness accuracy(6-22%), slice position accuracy (5-17%), image intensity uniformity (6%), percent signal ghosting (16%), and low contrast object detectability (8-10%). In this series, all the failure rates were less than 30%. In addition, no inter-observer variation was seen in the measurements and test failure. ACR MRI phantom promises to be established as the standard phantom for MRI instruments in Korea because of its objectivity in assessing the phantom images

  5. Design of the power sources for portable nuclear instruments

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  6. Preserving EQ as per CSA N290.13: EQ of equipment for CANDU NPP

    International Nuclear Information System (INIS)

    Bordeleau, H.

    2006-01-01

    EQ is basically a Quality Assurance process that ensures that required safety related equipment will performed their safety functions during accident generating harsh environmental condition. As any good Quality Assurance Program, EQ activities have to be imbedded in the normal tasks of the people at the plant in such a way that it is not an extra concern but part of the things to be assessed and done on a regular basis so that the EQ Status of the equipment will not be compromised. The experience shows us that even with brand new plants there are discrepancies between equipment designed to be installed and that installed (wrong model or wrong instrument). Improper installation was also found. To eliminate these mistakes it is recommended to have a thorough initial inspection during construction or commissioning and later at regular intervals during operation. To avoid new mistakes during maintenance, crews have to be properly qualified and trained on completed procedure with appropriate work report that will required to be scrutinized for possible common cause failure and OPEX report. Procurement and handling of equipment and spare parts require a thorough revision of procurement and storage practices to guarantee proper storage, availability and identification of equipment for EQ replacement. A shelf life program for degradable material shall be implemented. Condition monitoring program could be use to extend life of equipment or as a qualification methods, caution should be use to look very precisely to the critical parameters that need to be monitored and to carefully tailor the monitoring program. EQ program should also consider barriers, they are not EQ equipment; it is usually made out of non-ageing material like metal or concrete. But there could be sealing material used in conjunction with the barriers and these may need special care. The impact of EQ parameters changes related to services conditions, new technical data or condition monitoring has to be

  7. Small Portable Analyzer Diagnostic Equipment (SPADE) Program -- Diagnostic Software Validation

    Science.gov (United States)

    1984-07-01

    Electronic Equipment Electromagnetic Emission and Susceptibility Requirements for the Control of Electromagnetic Interference Electromagnetic...ONLY. ORIENTATION OF DEFECT LOOKING HHO QIlILL: t -ed’-o· Significant efforts were expended to simulate spalling failures associated with naturally

  8. Non-invasive measuring instrument of kVp, R/M and exposure time

    International Nuclear Information System (INIS)

    Laan, Flavio T. van der; Elbern, Alwin W.

    1996-01-01

    The development of an instrument for fast measurement of essential parameters related to quality control of X-ray equipment is described. The unit is designed with a 80 C31 micro controller, a function keyboard, an αnumeric display and a probe with PV diodes. Testing and calibration in this non-invasive instrument has been done at the X-rays equipment for the Santa Rita Hospital in Porto Alegre, Rio Grande do Sul State, Brazil

  9. Technical Basis for Evaluating Software-Related Common-Cause Failures

    Energy Technology Data Exchange (ETDEWEB)

    Muhlheim, Michael David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard [Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    The instrumentation and control (I&C) system architecture at a nuclear power plant (NPP) incorporates protections against common-cause failures (CCFs) through the use of diversity and defense-in-depth. Even for well-established analog-based I&C system designs, the potential for CCFs of multiple systems (or redundancies within a system) constitutes a credible threat to defeating the defense-in-depth provisions within the I&C system architectures. The integration of digital technologies into the I&C systems provides many advantages compared to the aging analog systems with respect to reliability, maintenance, operability, and cost effectiveness. However, maintaining the diversity and defense-in-depth for both the hardware and software within the digital system is challenging. In fact, the introduction of digital technologies may actually increase the potential for CCF vulnerabilities because of the introduction of undetected systematic faults. These systematic faults are defined as a “design fault located in a software component” and at a high level, are predominately the result of (1) errors in the requirement specification, (2) inadequate provisions to account for design limits (e.g., environmental stress), or (3) technical faults incorporated in the internal system (or architectural) design or implementation. Other technology-neutral CCF concerns include hardware design errors, equipment qualification deficiencies, installation or maintenance errors, instrument loop scaling and setpoint mistakes.

  10. JACoW Online analysis for anticipated failure diagnostics of the CERN cryogenic systems

    CERN Document Server

    Gayet, Philippe; Bradu, Benjamin; Cirillo, Roberta

    2018-01-01

    The cryogenic system is one of the most critical component of the CERN Large Hadron Collider (LHC) and its associated experiments ATLAS and CMS. In the past years, the cryogenic team has improved the maintenance plan and the operation procedures and achieved a very high reliability. However, as the recovery time after failure remains the major issue for the cryogenic availability new developments must take place. A new online diagnostic tool is developed to identify and anticipate failures of cryogenics field equipment, based on the acquired knowledge on dynamic simulation for the cryogenic equipment and on previous data analytic studies. After having identified the most critical components, we will develop their associated models together with the signature of their failure modes. The proposed tools will detect deviation between the actual systems and their model or identify preliminary failure signatures. This information will allow the operation team to take early mitigating actions before the failure occu...

  11. Comparison of defects in ProTaper hand-operated and engine-driven instruments after clinical use.

    Science.gov (United States)

    Cheung, G S P; Bian, Z; Shen, Y; Peng, B; Darvell, B W

    2007-03-01

    To compare the type of defects and mode of material failure of engine-driven and hand-operated ProTaper instruments after clinical use. A total of 401 hand-operated and 325 engine-driven ProTaper instruments were discarded from an endodontic clinic over 17 months. Those that had fractured were examined for plastic deformation in lateral view and remounted for fractographical examination in scanning electron microscope. The mode of fracture was classified as 'fatigue' or 'shear' failure. The lengths of fractured segments in both instruments were recorded. Any distortion in hand instrument was noted. Data were analysed using chi-square, Fisher's exact or Student's t-test, where appropriate. Approximately 14% of all discarded hand-operated instruments and 14% of engine-driven instruments were fractured. About 62% of hand instruments failed because of shear fracture, compared with approximately 66% of engine-driven instruments as a result of fatigue (P hand instruments were affected by shear, and either remained intact or was fractured, compared with 5% of engine-driven instruments (P hand versus engine-driven group (P hand instruments were discarded intact but distorted (rarely for engine-driven instruments); all were in the form of unscrewing of the flutes. The location of defects in hand Finishing instruments was significantly closer to the tip than that for Shaping instruments (P ProTaper engine-driven and hand-operated instruments appeared to be different, with shear failure being more prevalent in the latter.

  12. Adjustable extender for instrument module

    International Nuclear Information System (INIS)

    Sevec, J.B.; Stein, A.D.

    1975-01-01

    A blank extender module used to mount an instrument module in front of its console for repair or test purposes has been equipped with a rotatable mount and means for locking the mount at various angles of rotation for easy accessibility. The rotatable mount includes a horizontal conduit supported by bearings within the blank module. The conduit is spring-biased in a retracted position within the blank module and in this position a small gear mounted on the conduit periphery is locked by a fixed pawl. The conduit and instrument mount can be pulled into an extended position with the gear clearing the pawl to permit rotation and adjustment of the instrument

  13. Assessment of the performance of containment and surveillance equipment part 1: methodology

    International Nuclear Information System (INIS)

    Rezniczek, A.; Richter, B.

    2009-01-01

    Equipment performance aims at the creation of relevant data. As Containment and Surveillance (C/S) is playing an ever increasing role in safeguards systems, the issue of how to assess the performance of C/S equipment is being addressed by the ESARDA Working Group on C/S. The issue is important not only for the development of appropriate safeguards approaches but also for the review of existing approaches with regard to the implementation of the Additional Protocol (A P) and Integrated Safeguards. It is expected that the selection process of appropriate equipment, especially for unattended operation, is facilitated by the availability of methods to determine the performance of such equipment. Apart from EURATOM, the users of assessment methodologies would be the International Atomic Energy Agency (IAEA), plant operators, and instrument developers. The paper describes a non-quantitative performance assessment methodology. A structured procedure is outlined that allows assessing the suitability of different C/S instrumentation to comply with the objectives of its application. The principle to determine the performance of C/S equipment is to define, based on safeguards requirements, a task profile and to check the performance profile against the task profile. The performance profile of C/S equipment can be derived from the functional specifications and design basis tolerances provided by the equipment manufacturers.

  14. A guide on instrument of biochemistry and molecular biology

    International Nuclear Information System (INIS)

    1995-10-01

    This book is about instrument on biochemistry and molecular biology, which consists of six chapters. It deals with introduction of advanced bio-instrument, common utilization and maintain, explanation of each instrument like capillary electrophoresis, interactive laser cytometer, personal computer and software, an electron microscope and DNA/RNS synthesis instrument, large equipment and special system like information system and network, analysis system for genome and large spectro graph, outside donation, examples for common utilization and appendix on data like application form for use.

  15. Engineering Analysis of the Recovered SAFOD Borehole Instrumentation

    International Nuclear Information System (INIS)

    Johnson, Wade

    2014-01-01

    The basic data set was acquired during 18 instrumentation setting tests conducted from 2004 through 2007 as part of SAFOD. Active hydrocarbon-rich water invaded the borehole because the borehole had not sealed at the bottom. For this reason, the water in the casing reached the cable head and caused a malfunction. Attempts were made to use better O rings, Krytox oil, and epoxy seal, but all failed. In most of these deployments, standard wire-line was used and the average failure time was two weeks. Based on design review, many improvements such as stainless tube encapsulate electric cables, all-metal seals, and Swageloks were applied. Setting of improved downhole instrument packages was carried out in the autumn of 2008. Still, these instruments could not endure the high temperature environment of 120 degrees Celsius for a long period of time, and all were offline in less than a month. A SAFOD engineering subcommittee was established in 2010 to investigate the problems caused through an examination of the removed instruments. It became clear that fluid including active hydrocarbons had invaded the stainless tubing from the seal part and caused all instruments to fail. Based on the above-mentioned experience, recommendations for the future are as follows. - Perform strict oversight of subcontractors. - Perform robust risk analysis and prepare a risk mitigation plan. - Multiple checks should be performed on points of failure by different people. - If possible, avoid the use of active electronics in environments like those in SAFOD. - Components must be rated for use in the temperature range of the environment in which they are to be used. - If a failure occurs, remove the instrumentation in a timely manner. - The SAFOD POD design was not inherently flawed but poorly implemented. (author)

  16. 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

  17. Information needs and instrument availability for accident management : Application to YGN 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Whan; Park, Rae Jun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Suh, Kune Yull [Seoul Nationsl University, Seoul (Korea, Republic of)

    1996-12-01

    This paper introduces the five-step methodology for identifying information needs and assessing instrument availability during the course of severe in nuclear power plants. The methodology is applied to the Yonggwang (YGN) 3 and 4 to shed light on accident management. It constructs three safety objective trees to prevent the reactor vessel failure, to prevent the containment failure, and to mitigate the fission product release from the containment. The study assesses information needs and instrument availability under severe conditions for preventing the reactor vessel failure of YGN 3 and 4, and recommends additional instruments that may prove to be vital importance in managing the accident. 6 refs., 6 figs., 3 tabs. (author).

  18. Standard audit procedure for continuous emission monitors and ambient air monitoring instruments

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-06-15

    The instruments were published in an operational policy manual in 2009. This policy aims to introduce standard audit criteria that can be used to determine if continuous emission monitors and ambient air monitoring devices are operating within acceptable parameters. Before delivering upscale points of the instrument to be audited, each one of the audit equipment used in the field is required to be at normal operating conditions. Before the beginning of the audit, each one of the meteorological and flow measurement equipment is required to be conditioned to current conditions. If the audit fails, the instrument will have to be audited quarterly. The establishment of specific procedures based on instrument manufacturer or certifying body operational standards is required in the case of non-continuous monitoring instruments presenting operational principles outside of the audit procedures listed in the document.

  19. UF{sub 6} cylinder lifting equipment enhancements

    Energy Technology Data Exchange (ETDEWEB)

    Hortel, J.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States)

    1991-12-31

    This paper presents numerous enhancements that have been made to the Portsmouth lifting equipment to ensure the safe handling of cylinders containing liquid uranium hexafluoride (UF{sub 6}). The basic approach has been to provide redundancy to all components of the lift path so that any one component failure would not cause the load to drop or cause any undesirable movement.

  20. Management of ageing of I and C equipment in nuclear power plants. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2000-06-01

    Experience has shown that ageing and obsolescence have the potential to cause the maintainability and operability of many instrumentation and control (I and C) systems to deteriorate well before the end of plant life. An I and C ageing management strategy is therefore required to control and minimize this threat. This report gives guidance on how to develop such a strategy and provides examples and supporting information on how established and recently developed maintenance, surveillance, and testing techniques may be employed to support the strategy. In some cases, equipment refurbishment may be necessary and guidance on this subject is given in a companion publication (IAEA-TECDOC-1016, Modernization of Instrumentation and Control in Nuclear Power Plants, IAEA, Vienna, 1998). The International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) of the IAEA proposed in 1995 that a technical report be prepared to provide general guidelines on the management of ageing of important I and C equipment in nuclear power plants. The purpose of the report would be to guide the worldwide nuclear industry on potential effects of I and C ageing on plant safety and economy, and the means that are available to help minimize or eliminate any detrimental consequences of ageing. In response, a consultants meeting of five experts from Finland, France, Germany, the United Kingdom and the USA was held by the IAEA in Vienna in September 1997 to exchange national experience on the subject and to discuss the possible content of the report. The group of experts was tasked with bringing together all the information that is available on I and C ageing and ageing management methods. After a thorough discussion and analysis of the available information, an extended outline of the report on the subject was produced. The purpose of the extended outline was to identify a structure of the report, bring together information available at the moment and to provide guidance

  1. Experience gained with certification of instruments for the system for nuclear material physical protection, accounting, and control

    International Nuclear Information System (INIS)

    Gus'kov, O.M.; Egorov, V.V.; Morozov, O.S.; Novikov, V.M.

    1999-01-01

    Results of the tests have confirmed the expedience of certification of the equipment, especially imported items. For the use of imported equipment at Russian facilities, it is justified to accommodate the accompanying documents thereto for the Russian standards. Equipment items shipped to Russia should be prepared for the certification tests and/or operation. When taking decision on the certification of imported equipment, it is expedient to preliminarily estimate the instrument's parameters and its operation in Russia. To solve the question whether the imported equipment is usable for Russia and what engineering support and maintenance is needed for its operation, it would be justified to create the Center for engineering support of instruments to be used for nuclear material protection, control and accounting on the basis of one of institutes dealing with the development of instruments for these application [ru

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  4. Neutron beam instruments at Harwell

    International Nuclear Information System (INIS)

    Baston, A.H.; Harris, D.H.C.

    1978-11-01

    A list and brief descriptions are given of the neutron beam facilities for U.K. scientists at Harwell and in academic institutions, available under an agreement between the Science Research Council and AERE (Harwell). The list falls under the following headings: reactor instruments (single crystal diffractometers, powder diffractometers, triple axis spectrometers, time-of-flight cold neutron twin rotor spectrometer, beryllium filter spectrometer, MARX spectrometer, Harwell small-angle scattering spectrometer); LINAC instruments (total scattering spectrometer, back scattering spectrometer, active sample spectrometer, inelastic rotor spectrometer, constant Q spectrometer); ancillary equipment (cryostats, superconducting magnets, electromagnets, furnaces). (U.K.)

  5. 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

  6. Testing Aircraft Instruments.

    Science.gov (United States)

    1981-02-11

    1. Have test data been collected, recorded, and presented in accordance with this TOP? Yes No Comment : 2. Were the facilities, test equipment...instrumentation, and support accommodations adequate to accomplish the test objectives? Yes No Comment : 3. Have all data collected been reviewed for...correctness and completeness? Yes No Comment : 4. Were the test results compromised in any way due to insufficient test planning? Yes No Comment : 5. Were the

  7. Unsolved problems in applying U.S. regulatory guides to control system equipment

    International Nuclear Information System (INIS)

    Stade, R.E.

    1978-01-01

    Two current problems encountered when designing control systems to the United States Regulatory Guide requirements are discussed. They are: 1) Level of surge voltages that should be specified when procuring solid state control and instrumentation systems and equipment. 2) The approach to be used qualifying equipment that must meet the aging requirements. (author)

  8. Application of risk-based inspection methods for cryogenic equipment

    CERN Multimedia

    CERN. Geneva

    2016-01-01

    Risk-based Inspection (RBI) is widely applied across the world as part of Pressure Equipment Integrity Management, especially in the oil and gas industry, to generally reduce costs compared with time-based approaches and assist in assigning resources to the most critical equipment. One of the challenges in RBI is to apply it for low temperature and cryogenic applications, as there are usually no degradation mechanisms by which to determine a suitable probability of failure in the overall risk assessment. However, the assumptions used for other degradation mechanisms can be adopted to determine, qualitatively and semi-quantitatively, a consequence of failure within the risk assessment. This can assist in providing a consistent basis for the assumptions used in ensuring adequate process safety barriers and determining suitable sizing of relief devices. This presentation will discuss risk-based inspection in the context of cryogenic safety, as well as present some of the considerations for the risk assessme...

  9. 2H Evaporator CP class instrumentation uncertainties evaluations

    International Nuclear Information System (INIS)

    Hwang, E.

    1994-01-01

    The Evaporator Pot Temperature Instrumentations and the Steam Condensate Gamma Monitors are two instrumentation systems in the 2H Evaporator facilities that are classified as the critical protection. The temperature high alarm and interlock circuit and the temperature recorder circuit of the pot temperature instrumentation loop are described. From the gamma monitor loop, the high gamma alarm and interlock circuit, failure alarm and interlock circuit, cesium activity recorder circuit, and americium activity recorder circuit are described

  10. 2H Evaporator CP class instrumentation uncertainties evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, E.

    1994-02-10

    The Evaporator Pot Temperature Instrumentations and the Steam Condensate Gamma Monitors are two instrumentation systems in the 2H Evaporator facilities that are classified as the critical protection. The temperature high alarm and interlock circuit and the temperature recorder circuit of the pot temperature instrumentation loop are described. From the gamma monitor loop, the high gamma alarm and interlock circuit, failure alarm and interlock circuit, cesium activity recorder circuit, and americium activity recorder circuit are described. (GHH)

  11. Digital instrumentation for retrofit applications

    International Nuclear Information System (INIS)

    Dennis, U.E.

    1986-01-01

    There can be many reasons for applying retrofit designs to existing power plants. Whatever the reasons, care in planning and instrument design will be required in order to derive the full benefits afforded by today's technology. Specifically, the availability of microprocessors and their related integrated circuits make possible capabilities, accuracies, reliabilities, maintainability and user interfaces not achievable when original equipment was designed. Some of the motives for the replacement of current instrumentation are examined and the various benefits and pitfalls of applying present day microprocessor technology to new designs are discussed. From this, a set of design objectives can be formulated that can best take advantage of modern technology. General Electric's design solution, a family of instruments called NUMAC (Nuclear Measurement, Analysis and Control) is described, followed by descriptions of instruments currently in production and those contemplated for design in the near future

  12. 21 CFR 862.2050 - General purpose laboratory equipment labeled or promoted for a specific medical use.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false General purpose laboratory equipment labeled or... TOXICOLOGY DEVICES Clinical Laboratory Instruments § 862.2050 General purpose laboratory equipment labeled or promoted for a specific medical use. (a) Identification. General purpose laboratory equipment labeled or...

  13. Beam reliability and equipment downtime tracking how Lansce closes the loop

    International Nuclear Information System (INIS)

    Callaway, N.T.; Ryder, R.D.

    2003-01-01

    LANSCE uses a semi-automated accounting system to track how well we meet our stated beam delivery goals. When an equipment failure prevents delivery of the desired beam to our customers, the first order cause is identified and an accurate measurement of the downtime is recorded. For equipment downtimes of significant duration, we investigate the causes and make recommendations that will hopefully eliminate or mitigate the impact of similar downtimes in the future. (authors)

  14. Multiaxial brittle failure of a 3D carbon-carbon composite

    International Nuclear Information System (INIS)

    Davy, Catherine

    2001-01-01

    Several industrial equipments, for example in aeronautics, civil or military nuclear applications, imply multi-axially loaded brittle materials for which reliable failure models are needed. In that context, our study focuses on a 3D carbon-carbon composite submitted in service to a triaxial strain state along its orthotropy axes. A failure criterion based on a bibliographical analysis is identified thanks to uniaxial tensile tests, and validated through an original multiaxial experiment. The scatter on its failure characteristics is also identified. (author) [fr

  15. Design of a application of failure registration in equipment of radiotherapy treatments

    International Nuclear Information System (INIS)

    Martinez Ortega, J.; Rodriguez Cobo, C.; Pinto Monedero, M.; Rodriguez Romero, R.; Castro Tejero, P.; Sanchez Rubio, P.; Quintana Paz, A.

    2013-01-01

    It has developed an application that aims to provide a centralized database of service interventions, and can detect deficiencies at the time of response, percentages of operability or persistent failures in units. (Author)

  16. Life Cycle Management for Equipments in Nuclear Plants Based on Reliability

    International Nuclear Information System (INIS)

    Wang Dalin; Sun Jinlong

    2012-01-01

    Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (author)

  17. Wireless sensors for predictive maintenance of rotating equipment in research reactors

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2011-01-01

    In 2008-2009, the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) tested the potential of predictive or condition-based maintenance techniques to reduce maintenance costs, minimize the risk of catastrophic failures, and maximize system availability by attaching wireless-based sensors to selected rotating equipment at HFIR. Rotating equipment is an ideal 'test case' for the viability of integrated, online predictive maintenance strategies because motors, bearings, and shafts are ubiquitous in nuclear power plants and because the maintenance methods typically performed on rotating equipment today (such as portable or handheld vibration data collection equipment) are highly labor-intensive. The HFIR project achieved all five of its objectives: (1) to identify rotating machinery of the types used in research reactors and determine their operational characteristics, degradation mechanisms, and failure modes, (2) to establish a predictive maintenance program for rotating equipment in research reactors, (3) to identify wireless sensors that are suitable for predictive maintenance of rotating machinery and test them in a laboratory setting, (4) to establish the requirements and procedures to be followed when implementing wireless sensors for predictive maintenance in research reactors, and (5) to develop a conceptual design for a predictive maintenance system for research reactors based on wireless sensors. The project demonstrated that wireless sensors offer an effective method for monitoring key process conditions continuously and remotely, thereby enhancing the safety, reliability, and efficiency of the aging research reactor fleet.

  18. Nuclear electronic instrument systems using the Harwell 6000 series

    International Nuclear Information System (INIS)

    Seymour, F.D.; Snelling, G.F.; Hawthorn, I.

    1980-01-01

    This report describes some of the more recent equipment designed by the Systems Instrumentation Unit (AERE, Harwell), in the Harwell 6000 modular format. The units include: Laboratory Instruments (alpha monitors, beta-gamma detectors, spectrometers, automatic sample changer systems, automated counting laboratory systems, low power systems). Environmental Monitors (nuclear plant monitor, air monitor, sea bed monitor). Process Instruments (plutonium waste control, x-ray fluorescence monitor, process monitor, beam current monitor, effluent monitors). (U.K.)

  19. Guide to optimized replacement of equipment seals

    International Nuclear Information System (INIS)

    Gleason, J.F.

    1990-03-01

    A reevaluation of current scheduled replacement intervals of polymeric seals in plant equipment can achieve significant benefits. Information is provided which has the potential for increasing replacement intervals based on better information on how seals have performed through unique nuclear industry tests to qualify equipment, improved elastomers and increased knowledge of the failure mechanisms and related performance. The research was performed by reviewing applications of elastomeric seals in nuclear plants and practice associated with defining seal replacement intervals in the nuclear power and other industries. Performance indicators and how they predict degradation of seals were evaluated. Guidelines and a flow chart for reevaluating seal replacement intervals are provided. 29 refs., 38 figs., 8 tabs

  20. REVIEW OF EQUIPMENT USED IN RUSSIAN PRACTICE FOR ACCOUNTING MEASUREMENTS OF NUCLEAR MATERIALS

    International Nuclear Information System (INIS)

    NEYMOTIN, L.

    1999-01-01

    The objective of this work was to analyze instrumentation and methodologies used at Russian nuclear facilities for measurement of item nuclear materials, materials in bulk form, and waste streams; specify possibilities for the application of accounting measurements; and develop recommendations for improvement. The major steps and results: Representative conversion, enrichment (gas centrifuge), fuel fabrication, spent fuel reprocessing, and chemical-metallurgical production facilities in Russia were selected; Full lists of nuclear materials were prepared; Information about measurement methods and instrumentation for each type of nuclear material were gathered; and Recommendations on methodological and instrumentation support of accounting measurements for all types of materials were formulated. The analysis showed that the existing measurement methods and instrumentation serve mostly to support the technological process control and nuclear and radiation safety control. Requirements for these applications are lower than requirements for MC and A applications. To improve the state of MC and A at Russian nuclear facilities, significant changes in instrumentation support will be required, specifically in weighing equipment, volume measurements, and destructive and non-destructive analysis equipment, along with certified reference materials

  1. 10 CFR 20.1703 - Use of individual respiratory protection equipment.

    Science.gov (United States)

    2010-01-01

    ... continuous communication with the workers (visual, voice, signal line, telephone, radio, or other suitable... characteristics of the equipment are capable of providing the proposed degree of protection under anticipated... communication failure, significant deterioration of operating conditions, or any other conditions that might...

  2. Remote Access to Instrumental Analysis for Distance Education in Science

    Directory of Open Access Journals (Sweden)

    Dietmar Kennepohl

    2005-11-01

    Full Text Available Remote access to experiments offers distance educators another tool to integrate a strong laboratory component within a science course. Since virtually all modern chemical instrumental analysis in industry now use devices operated by a computer interface, remote control of instrumentation is not only relatively facile, it enhances students’ opportunity to learn the subject matter and be exposed to “real world” contents. Northern Alberta Institute of Technology (NAIT and Athabasca University are developing teaching laboratories based on the control of analytical instruments in real-time via an Internet connection. Students perform real-time analysis using equipment, methods, and skills that are common to modern analytical laboratories (or sophisticated teaching laboratories. Students obtain real results using real substances to arrive at real conclusions, just as they would if they were in a physical laboratory with the equipment; this approach allows students to access to conduct instrumental science experiments, thus providing them with an advantageous route to upgrade their laboratory skills while learning at a distance.

  3. Failure Modes Taxonomy for Reliability Assessment of Digital Instrumentation and Control Systems for Probabilistic Risk Analysis - Failure modes taxonomy for reliability assessment of digital I and C systems for PRA

    International Nuclear Information System (INIS)

    Amri, A.; Blundell, N.; ); Authen, S.; Betancourt, L.; Coyne, K.; Halverson, D.; Li, M.; Taylor, G.; Bjoerkman, K.; Brinkman, H.; Postma, W.; Bruneliere, H.; Chirila, M.; Gheorge, R.; Chu, L.; Yue, M.; Delache, J.; Georgescu, G.; Deleuze, G.; Quatrain, R.; Thuy, N.; Holmberg, J.-E.; Kim, M.C.; Kondo, K.; Mancini, F.; Piljugin, E.; Stiller, J.; Sedlak, J.; Smidts, C.; Sopira, V.

    2015-01-01

    Digital protection and control systems appear as upgrades in older nuclear power plants (NPP), and are commonplace in new NPPs. To assess the risk of NPP operation and to determine the risk impact of digital systems, there is a need to quantitatively assess the reliability of the digital systems in a justifiable manner. Due to the many unique attributes of digital systems (e.g., functions are implemented by software, units of the system interact in a communication network, faults can be identified and handled online), a number of modelling and data collection challenges exist, and international consensus on the reliability modelling has not yet been reached. The objective of the task group called DIGREL has been to develop a taxonomy of failure modes of digital components for the purposes of probabilistic risk analysis (PRA). An activity focused on the development of a common taxonomy of failure modes is seen as an important step towards standardised digital instrumentation and control (I and C) reliability assessment techniques for PRA. Needs from PRA has guided the work, meaning, e.g., that the I and C system and its failures are studied from the point of view of their functional significance point of view. The taxonomy will be the basis of future modelling and quantification efforts. It will also help to define a structure for data collection and to review PRA studies. The proposed failure modes taxonomy has been developed by first collecting examples of taxonomies provided by the task group organisations. This material showed some variety in the handling of I and C hardware failure modes, depending on the context where the failure modes have been defined. Regarding the software part of I and C, failure modes defined in NPP PRAs have been simple - typically a software CCF failing identical processing units. The DIGREL task group has defined a new failure modes taxonomy based on a hierarchical definition of five levels of abstraction: 1. system level (complete

  4. Independent Orbiter Assessment (IOA): Assessment of instrumental subsystem FMEA/CIL

    Science.gov (United States)

    Gardner, J. R.; Addis, A. W.

    1988-01-01

    The McDonnell Douglas Astronautics Company (MDAC) was selected in June 1986 to perform an Independent Orbiter Assessment (IOA) of the Failure Modes and Effects Analysis (FMEA) and Critical Items List (CIL). The IOA effort first completed an analysis of the Instrumentation hardware, generating draft failure modes and potential critical items. To preserve independence, this analysis was accomplished without reliance upon the results contained within the NASA FMEA/CIL documentation. The IOA results were then compared to the NASA FMEA/CIL baseline. A resolution of each discrepancy from the comparison is provided through additional analysis as required. The results of that comparison for the Orbiter Instrumentation hardware are documented. The IOA product for Instrumentation analysis consisted of 107 failure mode worksheets that resulted in 22 critical items being identified. Comparison was made to the Pre 51-L NASA baseline with 14 Post 51-L FMEAs added, which consists of 96 FMEAs and 18 CIL items. This comparison produced agreement on all but 25 FMEAs which caused differences in 5 CIL items.

  5. Challenges in Resolution for IC Failure Analysis

    Science.gov (United States)

    Martinez, Nick

    1999-10-01

    Resolution is becoming more and more of a challenge in the world of Failure Analysis in integrated circuits. This is a result of the ongoing size reduction in microelectronics. Determining the cause of a failure depends upon being able to find the responsible defect. The time it takes to locate a given defect is extremely important so that proper corrective actions can be taken. The limits of current microscopy tools are being pushed. With sub-micron feature sizes and even smaller killing defects, optical microscopes are becoming obsolete. With scanning electron microscopy (SEM), the resolution is high but the voltage involved can make these small defects transparent due to the large mean-free path of incident electrons. In this presentation, I will give an overview of the use of inspection methods in Failure Analysis and show example studies of my work as an Intern student at Texas Instruments. 1. Work at Texas Instruments, Stafford, TX, was supported by TI. 2. Work at Texas Tech University, was supported by NSF Grant DMR9705498.

  6. 77 FR 61737 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-10-11

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  7. 77 FR 37652 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-06-22

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  8. 75 FR 1339 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-01-11

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  9. 77 FR 2270 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-01-17

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... the level of export controls applicable to sensors and instrumentation equipment and technology...

  10. 78 FR 1198 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-01-08

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  11. 76 FR 323 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-01-04

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  12. 78 FR 63161 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting...

    Science.gov (United States)

    2013-10-23

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting ``Rescheduled'' The Sensors and Instrumentation... that affect the level of export controls applicable to sensors and instrumentation equipment and...

  13. 75 FR 39920 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-07-13

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  14. 78 FR 19638 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-04-02

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  15. 76 FR 63607 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-10-13

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  16. 78 FR 60251 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-10-01

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. [[Page...

  17. 78 FR 40098 - Sensors And Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-07-03

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors And Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  18. 77 FR 23222 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-04-18

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  19. 75 FR 14426 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-03-25

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... of export controls applicable to sensors and instrumentation equipment and technology. Agenda Public...

  20. 75 FR 62508 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-10-12

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting The Sensors and Instrumentation Technical Advisory... level of export controls applicable to sensors and instrumentation equipment and technology. Agenda...

  1. Design aspects of safety critical instrumentation of nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Swaminathan, P. [Electronics Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, Tamil Nadu (India)]. E-mail: swamy@igcar.ernet.in

    2005-07-01

    Safety critical instrumentation systems ensure safe shutdown/configuration of the nuclear installation when process status exceeds the safety threshold limits. Design requirements for safety critical instrumentation such as functional and electrical independence, fail-safe design, and architecture to ensure the specified unsafe failure rate and safe failure rate, human machine interface (HMI), etc., are explained with examples. Different fault tolerant architectures like 1/2, 2/2, 2/3 hot stand-by are compared for safety critical instrumentation. For embedded systems, software quality assurance is detailed both during design phase and O and M phase. Different software development models such as waterfall model and spiral model are explained with examples. The error distribution in embedded system is detailed. The usage of formal method is outlined to reduce the specification error. The guidelines for coding of application software are outlined. The interface problems of safety critical instrumentation with sensors, actuators, other computer systems, etc., are detailed with examples. Testability and maintainability shall be taken into account during design phase. Online diagnostics for safety critical instrumentation is detailed with examples. Salient details of design guides from Atomic Energy Regulatory Board, International Atomic Energy Agency and standards from IEEE, BIS are given towards the design of safety critical instrumentation systems. (author)

  2. Design aspects of safety critical instrumentation of nuclear installations

    International Nuclear Information System (INIS)

    Swaminathan, P.

    2005-01-01

    Safety critical instrumentation systems ensure safe shutdown/configuration of the nuclear installation when process status exceeds the safety threshold limits. Design requirements for safety critical instrumentation such as functional and electrical independence, fail-safe design, and architecture to ensure the specified unsafe failure rate and safe failure rate, human machine interface (HMI), etc., are explained with examples. Different fault tolerant architectures like 1/2, 2/2, 2/3 hot stand-by are compared for safety critical instrumentation. For embedded systems, software quality assurance is detailed both during design phase and O and M phase. Different software development models such as waterfall model and spiral model are explained with examples. The error distribution in embedded system is detailed. The usage of formal method is outlined to reduce the specification error. The guidelines for coding of application software are outlined. The interface problems of safety critical instrumentation with sensors, actuators, other computer systems, etc., are detailed with examples. Testability and maintainability shall be taken into account during design phase. Online diagnostics for safety critical instrumentation is detailed with examples. Salient details of design guides from Atomic Energy Regulatory Board, International Atomic Energy Agency and standards from IEEE, BIS are given towards the design of safety critical instrumentation systems. (author)

  3. 浅谈提高大型仪器设备使用效率的措施%Discussion on improving utilization efficiency of large instruments and equipment

    Institute of Scientific and Technical Information of China (English)

    吴冰; 张勇

    2011-01-01

    大型仪器设备在高校学科建设中起着重要的支撑作用,高校对仪器设备的投人逐年增加,本文从提高机时利用率、管理人员素质和健全管理制度等方面探讨了提高大型仪器设备使用效率的措施.%Large instruments and equipment play an important supporting role in the building of academic disciplines in colleges and universities, and funds apropriated for their purchase and operation are increasing each year. This paper discusses the methods to improve the utilization efficiency of these instruments through improving the quality of management staff and administration system and increasing the usage factor.

  4. Systematic analysis and prevention of human originated common cause failures in relation to maintenance activities at Finnish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Laakso, K. [VTT Industrial Systems, Espoo (Finland)

    2006-12-15

    The focus in human reliability analysis of nuclear power plants has traditionally been on human performance in disturbance conditions. On the other hand, human maintenance failures and design deficiencies, remained latent in the system, have an impact on the severity of a disturbance, e.g. by disabling safety-related equipment on demand. Especially common cause failures (CCFs) of safety related systems can affect the core damage risk to a significant extent. The topic has been addressed in Finnish studies, where experiences of latent human errors have been searched and analysed systematically from the maintenance history stored in the the power plant information systems of the Loviisa and Olkiluoto NPPs. Both the single and multiple errors (CCFs) were classified in detail and documented as error and event reports. The human CCFs involved human, organisational and technical factors. The review of the analysed single and multiple errors showed that instrumentation and control and electrical equipment are more prone to human error caused failure events than the other maintenance objects. The review of the analysed experience showed that most errors stem from the refuelling and maintenance outage periods. More than half of the multiple errors from the outages remained latent to the power operating periods. The review of the analysed multiple errors showed that difficulties with small plant modifications and planning of maintenance and operability were significant sources of common cause failures. The most dependent human errors originating from small modifications could be reduced by a more tailored planning and coverage of their start-up testing programs. Improvements could also be achieved by identifying better in work planning from the operating experiences those complex or intrusive repair and preventive maintenance work tasks and actions which are prone to errors. Such uncertain cases in important equipment require a more tailored work planning of the installation

  5. Systematic analysis and prevention of human originated common cause failures in relation to maintenance activities at Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Laakso, K.

    2006-12-01

    The focus in human reliability analysis of nuclear power plants has traditionally been on human performance in disturbance conditions. On the other hand, human maintenance failures and design deficiencies, remained latent in the system, have an impact on the severity of a disturbance, e.g. by disabling safety-related equipment on demand. Especially common cause failures (CCFs) of safety related systems can affect the core damage risk to a significant extent. The topic has been addressed in Finnish studies, where experiences of latent human errors have been searched and analysed systematically from the maintenance history stored in the the power plant information systems of the Loviisa and Olkiluoto NPPs. Both the single and multiple errors (CCFs) were classified in detail and documented as error and event reports. The human CCFs involved human, organisational and technical factors. The review of the analysed single and multiple errors showed that instrumentation and control and electrical equipment are more prone to human error caused failure events than the other maintenance objects. The review of the analysed experience showed that most errors stem from the refuelling and maintenance outage periods. More than half of the multiple errors from the outages remained latent to the power operating periods. The review of the analysed multiple errors showed that difficulties with small plant modifications and planning of maintenance and operability were significant sources of common cause failures. The most dependent human errors originating from small modifications could be reduced by a more tailored planning and coverage of their start-up testing programs. Improvements could also be achieved by identifying better in work planning from the operating experiences those complex or intrusive repair and preventive maintenance work tasks and actions which are prone to errors. Such uncertain cases in important equipment require a more tailored work planning of the installation

  6. Safety Review related to Commercial Grade Digital Equipment in Safety System

    International Nuclear Information System (INIS)

    Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

    2013-01-01

    The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

  7. Laser alignment of rotating equipment at PNL

    International Nuclear Information System (INIS)

    Berndt, R.H.

    1994-05-01

    Lateral vibration in direct-drive equipment is usually caused by misalignment. Over the years, because of the need to improve on techniques and ways of working more efficiently, various types of alignment methods have evolved. In the beginning, craftsmen used a straight-edge scale across the coupling with a feeler gauge measuring the misalignment error. This is still preferred today for aligning small couplings. The industry has since decided that alignment of large direct-drive equipment needed a more accurate type of instrumentation. Rim and face is another of the first alignment methods and is used on all sizes of equipment. A disadvantage of the rim and face method is that in most cases the coupling has to be disassembled. This can cause alignment problems when the coupling is reassembled. Also, the rim and face method is not fast enough to work satisfactorily on alignment of thermally hot equipment. Another concern is that the coupling has to be manufactured accurately for correct rim and face readings. Reverse dial alignment is an improvement over the rim and face method, and depending on the operator's experience, this method can be very accurate. A good training program along with field experience will bring the operator to a proper level of proficiency for a successful program. A hand-held computer with reverse dial calculations in memory is a must for job efficiency. An advantage over the rim and face method is that the coupling is not disassembled and remains locked together. Reverse dial instrumentation measures from both shaft center lines, rather than the coupling surface so the machining of the coupling during manufacture is not a major concern

  8. Using PHM to measure equipment usable life on the Air Force's next generation reusable space booster

    Science.gov (United States)

    Blasdel, A.

    The U.S. Air Force procures many launch vehicles and launch vehicle services to place their satellites at their desired location in space. The equipment on-board these satellite and launch vehicle often suffer from premature failures that result in the total loss of the satellite or a shortened mission life sometimes requiring the purchase of a replacement satellite and launch vehicle. The Air Force uses its EELV to launch its high priority satellites. Due to a rise in the cost of purchasing a launch using the Air Force's EELV from 72M in 1997 to as high as 475M per launch today, the Air Force is working to replace the EELV with a reusable space booster (RSB). The RSB will be similar in design and operations to the recently cancelled NASA reusable space booster known as the Space Shuttle. If the Air Force uses the same process that procures the EELV and other launch vehicles and satellites, the RSB will also suffer from premature equipment failures thus putting the payloads at a similar high risk of mission failure. The RSB is expected to lower each launch cost by 50% compared to the EELV. The development of the RSB offers the Air Force an opportunity to use a new reliability paradigm that includes a prognostic and health management program and a condition-based maintenance program. These both require using intelligent, decision making self-prognostic equipment The prognostic and health management program and its condition-based maintenance program allows increases in RSB equipment usable life, lower logistics and maintenance costs, while increasing safety and mission assurance. The PHM removes many decisions from personnel that, in the past resulted in catastrophic failures and loss of life. Adding intelligent, decision-making self-prognostic equipment to the RSB will further decrease launch costs while decreasing risk and increasing safety and mission assurance.

  9. Prediction of Maintenance Period of Equipment Through Risk Assessment of Thermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Song, Gee Wook; Kim, Bum Shin; Choi, Woo Song; Park, Myung Soo [KEPCO Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    Risk-based inspection (RBI) is a well-known method that is used to optimize inspection activities based on risk analysis in order to identify the high-risk components of major facilities such as power plants. RBI, when implemented and maintained properly, improves plant reliability and safety while reducing unplanned outages and repair costs. Risk is given by the product of the probability of failure (Pof) and the consequence of failure (COF). A semi-quantitative method is generally used for risk assessment. Semi-quantitative risk assessment complements the low accuracy of qualitative risk assessment and the high expense and long calculation time of quantitative risk assessment. The first step of RB I is to identify important failure modes and causes in the equipment. Once these are defined, the Pof and COF can be assessed for each failure. During Pof and COF assessment, an effective inspection method and range can be easily found. In this paper, the calculation of the Pof is improved for accurate risk assessment. A modified semi-quantitative risk assessment was carried out for boiler facilities of thermal power plants, and the next maintenance schedules for the equipment were decided.

  10. Prediction of Maintenance Period of Equipment Through Risk Assessment of Thermal Power Plants

    International Nuclear Information System (INIS)

    Song, Gee Wook; Kim, Bum Shin; Choi, Woo Song; Park, Myung Soo

    2013-01-01

    Risk-based inspection (RBI) is a well-known method that is used to optimize inspection activities based on risk analysis in order to identify the high-risk components of major facilities such as power plants. RBI, when implemented and maintained properly, improves plant reliability and safety while reducing unplanned outages and repair costs. Risk is given by the product of the probability of failure (Pof) and the consequence of failure (COF). A semi-quantitative method is generally used for risk assessment. Semi-quantitative risk assessment complements the low accuracy of qualitative risk assessment and the high expense and long calculation time of quantitative risk assessment. The first step of RB I is to identify important failure modes and causes in the equipment. Once these are defined, the Pof and COF can be assessed for each failure. During Pof and COF assessment, an effective inspection method and range can be easily found. In this paper, the calculation of the Pof is improved for accurate risk assessment. A modified semi-quantitative risk assessment was carried out for boiler facilities of thermal power plants, and the next maintenance schedules for the equipment were decided

  11. THE CHARACTERISTICS OF EEC PET INSTRUMENTATION

    NARCIS (Netherlands)

    PAANS, AMJ

    1991-01-01

    As a result of a Guide-Questionnaire distributed among all European PET centers an inventory of the European PET instrumentation has become available in a data base. An overview and analysis of the European PET equipment, cyclotrons, scanners and software, together with some global information on

  12. Development of an approach for the analysis of network technologies in safety related instrumentation and control systems with respect to the propagation and effect of postulated failures; Entwicklung eines Ansatzes zur Analyse der Netzwerktechnologien in sicherheitsrelevanten Leittechniksystemen hinsichtlich Verbreitung und Auswirkung postulierter Fehler

    Energy Technology Data Exchange (ETDEWEB)

    Herb, Joachim; Jopen, Manuela; Lindner, Falk; Piljugin, Ewgenij; Vogt, Pascal

    2015-06-15

    So far, safety related instrumentation and control (I and C) functions in nuclear power plants, such as controlling of safety systems, were mostly performed by conventional (analog) I and C equipment. For some years now, I and C systems and equipment in nuclear power plants worldwide, but also in Germany, are modernized by computer-based I and C systems. In signal processing of the computer-based I and C systems, modern network technologies are used both for internal and external communication, whereas the reliability and safety for information transfer and processing plays an important role. National and interna-tional operational experience shows a significant influence of communication in a net-worked I and C system on its reliability. The aim of the GRS within the project 361R01351 ''Development of an approach for an analysis of network technologies in safety related I and C systems in view of distribution and effect of postulated failures'' was to improve the expertise in the field of network communication, to investigate phenomenologically potential sources of failures and fault propagation paths (Network failures) in a generic I and C system as well as to develop methodic approaches for analyses of propagation and effect of postulated failures in typical networks. The GRS conducted extensive research in the field of ''Data communication in digital I and C systems''. In this report, the basic principles of data communication of computer-based I and C systems are presented. This includes, among other things, network topolo-gies, communication protocols and standards as well as generic failures. Additionally, the properties of different analysis methods and its applicability for reliability analyses of network communication in computer-based I and C systems are discussed. Based on state of the art evaluation, an analysis approach was developed, which takes into account the specific properties of network communication and

  13. Usage of Failure Mode & EffectAnalysis Method (FMEA forsafety assessment in a drug manufacture

    Directory of Open Access Journals (Sweden)

    Y Nazari

    2006-04-01

    Full Text Available Background and Aims: This study was hold in purpose of recognizing and controlling workplacehazards in production units of a drag ManufactureMethod:So for recognition and assessment of hazards, FMEA Method was used. FMEASystematically investigates the effects of equipment and system failures leading often toequipment design improvements. At first the level of the study defined as system. Then accordingto observations, accident statistic, and interview with managers, supervisory, and workers highrisk system were determiner. So the boundaries of the system established and informationregarding the relevant Components, their function and interactions gathered. To preventConfusion between Similar pieces of equipment, a unique system identifier developed. After thatall failure modes and their causes for each equipment or system listed, the immediate effects ofeach failure mode and interactive effect on other equipment or system was described too. Riskpriority number was determined according to global and local criteriaResults: After all some actions and solution proposed to reduce the likelihood and severity offailures and raise their delectability.Conclusion :This study illustrated that although of the first step drug manufacture may seem safe,but there are still many hazardous condition that could cause serious accidents, The result proposedit is necessary: (1 to develop comprehensive manual for periodical and regular inspection ofinstruments of workplaces in purpose of recognize unknown failures and their causes, (2 developa comprehensive program for systems maintenance and repair, and (3 conduct worker training.

  14. Review of equipment aging theory and technology. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Carfagno, S.P.; Gibson, R.J.

    1980-09-01

    The theory and technology of equipment aging is reviewed, particularly as they relate to the qualification of safety-system equipment for nuclear power generating stations. A fundamental degradation model is developed, and its relation to more restricted models (e.g., Arrhenius and inverse-stress models) is shown. The most common theoretical and empirical models of aging are introduced, and limitations on their practical application are analyzed. Reliability theory and its application to the acceleration of aging are also discussed. A compendium of aging data for materials and components, including degradation mechanisms, failure modes and activation energies, is included.

  15. Review of equipment aging theory and technology. Final report

    International Nuclear Information System (INIS)

    Carfagno, S.P.; Gibson, R.J.

    1980-09-01

    The theory and technology of equipment aging is reviewed, particularly as they relate to the qualification of safety-system equipment for nuclear power generating stations. A fundamental degradation model is developed, and its relation to more restricted models (e.g., Arrhenius and inverse-stress models) is shown. The most common theoretical and empirical models of aging are introduced, and limitations on their practical application are analyzed. Reliability theory and its application to the acceleration of aging are also discussed. A compendium of aging data for materials and components, including degradation mechanisms, failure modes and activation energies, is included

  16. Recommendations for managing equipment aging in nuclear power plants

    International Nuclear Information System (INIS)

    Gunther, W.E.; Subudhi, M.; Aggarwal, S.K.

    1992-01-01

    Research conducted under the auspices of the US NRC's Nuclear Plant Aging Research (NPAR) Program has resulted in a large database of component and system operating, maintenance, and testing information. This database has been used to determine the susceptibility to aging of selected components, and the potential for equipment aging to impact plant safety and availability. it has also identified methods for detecting and mitigating component and system aging. This paper describes the research recommendations on electrical components which could be applied to maintenance, testing, and inspection activities to detect and mitigate the effects of aging prior to equipment failures

  17. Bayesian analysis of repairable systems showing a bounded failure intensity

    International Nuclear Information System (INIS)

    Guida, Maurizio; Pulcini, Gianpaolo

    2006-01-01

    The failure pattern of repairable mechanical equipment subject to deterioration phenomena sometimes shows a finite bound for the increasing failure intensity. A non-homogeneous Poisson process with bounded increasing failure intensity is then illustrated and its characteristics are discussed. A Bayesian procedure, based on prior information on model-free quantities, is developed in order to allow technical information on the failure process to be incorporated into the inferential procedure and to improve the inference accuracy. Posterior estimation of the model-free quantities and of other quantities of interest (such as the optimal replacement interval) is provided, as well as prediction on the waiting time to the next failure and on the number of failures in a future time interval is given. Finally, numerical examples are given to illustrate the proposed inferential procedure

  18. Performance and quality control of nuclear medicine instrumentation

    International Nuclear Information System (INIS)

    Paras, P.

    1981-01-01

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

  19. Analysis Method of Common Cause Failure on Non-safety Digital Control System

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yun Goo; Oh, Eun Gse [KHNP, Daejeon (Korea, Republic of)

    2014-08-15

    The effects of common cause failure on safety digital instrumentation and control system had been considered in defense in depth analysis with safety analysis method. However, the effects of common cause failure on non-safety digital instrumentation and control system also should be evaluated. The common cause failure can be included in credible failure on the non-safety system. In the I and C architecture of nuclear power plant, many design feature has been applied for the functional integrity of control system. One of that is segmentation. Segmentation defenses the propagation of faults in the I and C architecture. Some of effects from common cause failure also can be limited by segmentation. Therefore, in this paper there are two type of failure mode, one is failures in one control group which is segmented, and the other is failures in multiple control group because that the segmentation cannot defense all effects from common cause failure. For each type, the worst failure scenario is needed to be determined, so the analysis method has been proposed in this paper. The evaluation can be qualitative when there is sufficient justification that the effects are bounded in previous safety analysis. When it is not bounded in previous safety analysis, additional analysis should be done with conservative assumptions method of previous safety analysis or best estimation method with realistic assumptions.

  20. Automatic creation of Markov models for reliability assessment of safety instrumented systems

    International Nuclear Information System (INIS)

    Guo Haitao; Yang Xianhui

    2008-01-01

    After the release of new international functional safety standards like IEC 61508, people care more for the safety and availability of safety instrumented systems. Markov analysis is a powerful and flexible technique to assess the reliability measurements of safety instrumented systems, but it is fallible and time-consuming to create Markov models manually. This paper presents a new technique to automatically create Markov models for reliability assessment of safety instrumented systems. Many safety related factors, such as failure modes, self-diagnostic, restorations, common cause and voting, are included in Markov models. A framework is generated first based on voting, failure modes and self-diagnostic. Then, repairs and common-cause failures are incorporated into the framework to build a complete Markov model. Eventual simplification of Markov models can be done by state merging. Examples given in this paper show how explosively the size of Markov model increases as the system becomes a little more complicated as well as the advancement of automatic creation of Markov models

  1. Development of a dosimetric system for dental X-ray equipment quality control

    International Nuclear Information System (INIS)

    Melo, Francisco Almeida de

    2002-08-01

    An electronic instrument with digital readout was designed and constructed to provide fast, simple and non-invasive measurements of X-ray dental equipment parameters. This instrument is capable of evaluating the entrance dose, exposure time, tube voltage (kVp) and beam filtration. It consists of a set of five photodiodes connected each one in the photocurrent mode to the input of a designed integrating electrometer. Three of the detectors are fixed under aluminium filters with different thicknesses, one is fixed under a 0.3 mm copper filter and the other has no filtration. The readings of the three detectors under aluminium filters and of the bare detector permit the determination of the half-value layer, which is used to calculate the beam filtration. The ratio between the readings of the detector below the copper filter and the one without filtration is used to determine the tube voltage. The signal produced by the detector without filter is used to evaluate the patient entrance dose, and to active an electronic timer for measuring the real exposure time. The tests and calibration of the instrument in different voltages in the 59 - 70kVp range, showed that its response is both stable and reproducible to within 1%. The instrument response was compared to the one from a commercial non-invasive X-ray test equipment (Gammex RMI Multifunction kVp meter). The results showed that the response of the developed instrument is in good agreement with the RMI meter which is the standard equipment for such measurements. These results indicate that the dosimetric system is suitable for use in Dental Quality Assurance Programs. (author)

  2. Safeguards instrumentation: past, present, future

    International Nuclear Information System (INIS)

    Higinbotham, W.A.

    1982-01-01

    Instruments are essential for accounting, for surveillance and for protection of nuclear materials. The development and application of such instrumentation is reviewed, with special attention to international safeguards applications. Active and passive nondestructive assay techniques are some 25 years of age. The important advances have been in learning how to use them effectively for specific applications, accompanied by major advances in radiation detectors, electronics, and, more recently, in mini-computers. The progress in seals has been disappointingly slow. Surveillance cameras have been widely used for many applications other than safeguards. The revolution in TV technology will have important implications. More sophisticated containment/surveillance equipment is being developed but has yet to be exploited. On the basis of this history, some expectations for instrumentation in the near future are presented

  3. Solar Constant (SOLCON) Experiment: Ground Support Equipment (GSE) software development

    Science.gov (United States)

    Gibson, M. Alan; Thomas, Susan; Wilson, Robert

    1991-01-01

    The Solar Constant (SOLCON) Experiment, the objective of which is to determine the solar constant value and its variability, is scheduled for launch as part of the Space Shuttle/Atmospheric Laboratory for Application and Science (ATLAS) spacelab mission. The Ground Support Equipment (GSE) software was developed to monitor and analyze the SOLCON telemetry data during flight and to test the instrument on the ground. The design and development of the GSE software are discussed. The SOLCON instrument was tested during Davos International Solar Intercomparison, 1989 and the SOLCON data collected during the tests are analyzed to study the behavior of the instrument.

  4. Fatigue resistance of engine-driven rotary nickel-titanium instruments produced by new manufacturing methods.

    Science.gov (United States)

    Gambarini, Gianluca; Grande, Nicola Maria; Plotino, Gianluca; Somma, Francesco; Garala, Manish; De Luca, Massimo; Testarelli, Luca

    2008-08-01

    The aim of the present study was to investigate whether cyclic fatigue resistance is increased for nickel-titanium instruments manufactured by using new processes. This was evaluated by comparing instruments produced by using the twisted method (TF; SybronEndo, Orange, CA) and those using the M-wire alloy (GTX; Dentsply Tulsa-Dental Specialties, Tulsa, OK) with instruments produced by a traditional NiTi grinding process (K3, SybronEndo). Tests were performed with a specific cyclic fatigue device that evaluated cycles to failure of rotary instruments inside curved artificial canals. Results indicated that size 06-25 TF instruments showed a significant increase (p 0.05) in the mean number of cycles to failure when compared with size 06-20 GT series X instruments. The new manufacturing process produced nickel-titanium rotary files (TF) significantly more resistant to fatigue than instruments produced with the traditional NiTi grinding process. Instruments produced with M-wire (GTX) were not found to be more resistant to fatigue than instruments produced with the traditional NiTi grinding process.

  5. Equipment used in nuclear medicine

    International Nuclear Information System (INIS)

    Das, B.K.; Noreen Norfaraheen Lee Abdullah

    2012-01-01

    Detection of radiation is the common purpose of all equipment's and instruments used in radioisotope laboratories. The first and most important instrument that was used in nuclear medicine was Geiger tube developed by H.W. Geiger as early in 1908. He in association with Mueller developed the so called Geiger-Muller tube (GM tube) which could be used to detect beta and gamma radiations. In spite of its severe limitations, GM tube remained the only external counting device until 1949. In 1948, Kallman reported that the scintillations can be detected and amplified with the help of photomultiplier tubes (PMTs). In comparison with gas filled detectors, scintillation detectors have two principal advantages that augment their use in nuclear medicine. Firstly, they are capable of much higher counting rates because of fast resolving times and secondly, because they are much more efficient for gamma ray detection. The scintillation detector is the most basic block of any modern radioisotope detection instrument like rate meter, counter, scanner, gamma camera or single photon emission computed tomography. (author)

  6. Instrumentation & Data Acquisition System (D AS) Engineer

    Science.gov (United States)

    Jackson, Markus Deon

    2015-01-01

    The primary job of an Instrumentation and Data Acquisition System (DAS) Engineer is to properly measure physical phenomenon of hardware using appropriate instrumentation and DAS equipment designed to record data during a specified test of the hardware. A DAS system includes a CPU or processor, a data storage device such as a hard drive, a data communication bus such as Universal Serial Bus, software to control the DAS system processes like calibrations, recording of data and processing of data. It also includes signal conditioning amplifiers, and certain sensors for specified measurements. My internship responsibilities have included testing and adjusting Pacific Instruments Model 9355 signal conditioning amplifiers, writing and performing checkout procedures, writing and performing calibration procedures while learning the basics of instrumentation.

  7. Analysis of defects in ProTaper hand-operated instruments after clinical use.

    Science.gov (United States)

    Shen, Ya; Bian, Zhuan; Cheung, Gary Shun-pan; Peng, Bin

    2007-03-01

    The purpose of this study was to analyze the type and location of defects observed in ProTaper for Hand Use (PHU) instruments after routine clinical use. We analyzed a total of 401 PHUs discarded from an endodontic clinic over a 17-month period. Those failed instruments were examined on the lateral and fractographic surface by scanning electron microscope. Of the 86 PHUs that showed discernible defects, 28 were intact but partially unwound, and 58 were fractured (36 because of shear and 22 from fatigue failure). The primary characteristic of shear failure was the presence of a skewed dimple and/or tear ridge, a typical pattern developed because of a combination of various loads. Nearly 74% of the instruments with defects exhibited shear damage. About three-quarters of the instrument fractures occurred in the apical one-third of the canal, mostly in molars. The results of this study indicated that most PHU instruments fail because of either shear or fatigue.

  8. New technology in nuclear power plant instrumentation and control

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

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

  9. PV System Component Fault and Failure Compilation and Analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Klise, Geoffrey Taylor; Lavrova, Olga; Gooding, Renee Lynne

    2018-02-01

    This report describes data collection and analysis of solar photovoltaic (PV) equipment events, which consist of faults and fa ilures that occur during the normal operation of a distributed PV system or PV power plant. We present summary statistics from locations w here maintenance data is being collected at various intervals, as well as reliability statistics gathered from that da ta, consisting of fault/failure distributions and repair distributions for a wide range of PV equipment types.

  10. Experience with diagnostic instrumentation in nuclear power plants

    International Nuclear Information System (INIS)

    Gopal, R.; Ciaramitaro, W.

    1977-01-01

    Over the past several years, Westinghouse has developed a coordinated system of on-line diagnostic instrumentation for the acquisition and analysis of data for diagnostics and incipient failure detection of critical plant equipment and systems. Primary motivation for this work is to improve NSSS availability and Maintainability through the detection of malfunctions at their inception. These systems encompass the following areas: (1) Vibration Monitoring System for detection of changes in vibrational characteristics of the major components of Nuclear Steam Supply System (NSSS) and Balance of Plant (BOP); (2) Acoustic Monitoring System for detection and location of leaks in the primary system pressure boundary and other piping systems in PWRs; (3) Metal Impact Monitoring for detection of loose debris in the reactor vessel and steam generators; (4) Nuclear Noise Monitoring System for monitoring core barrel vibration; (5) Sensor Response Time Measurement System for detecting any degradation of process sensors; and (6) Transit Time Flow Meter for determining primary coolant flow rate. Summarized in this paper are some of the features of the systems and in-plant experience. These experiences demonstrate that diagnostic systems in combination with analytical and laboratory work for data interpretation do improve plant availability. (author)

  11. Meteorological Satellites (METSAT) and Earth Observing System (EOS) Advanced Microwave Sounding Unit-A (AMSU-A) Failure Modes and Effects Analysis (FMEA) and Critical Items List (CIL)

    Science.gov (United States)

    1996-01-01

    This Failure Modes and Effects Analysis (FMEA) is for the Advanced Microwave Sounding Unit-A (AMSU-A) instruments that are being designed and manufactured for the Meteorological Satellites Project (METSAT) and the Earth Observing System (EOS) integrated programs. The FMEA analyzes the design of the METSAT and EOS instruments as they currently exist. This FMEA is intended to identify METSAT and EOS failure modes and their effect on spacecraft-instrument and instrument-component interfaces. The prime objective of this FMEA is to identify potential catastrophic and critical failures so that susceptibility to the failures and their effects can be eliminated from the METSAT/EOS instruments.

  12. Quality of mammography equipment in Health Public Network; Calidad de proceso generador de imagenes mamograficas de equipos instalados en la Red Publica de Salud

    Energy Technology Data Exchange (ETDEWEB)

    Ruberti Filha, E. M.; Pires, S. R.; Medeiros, R. B.

    2006-07-01

    In spite of the requirements of the Brazilian Regulatory Organization to ensure that quality control verifications are made in the radiological equipment, further actions should also be carried out in order to guarantee the quality of the images and of the diagnosis. This study has as its objective to analyze the failures of the image generation system using instruments to control the quality of the radiological equipment, verify the processing image conditions and, finally, classify the mammographic findings as unacceptable, suitable and acceptable. A statistical phantom was used in which the fibers and the microcalcifications were randomly positioned. The images were then read by specialists and the level of agreement was measured by the Kappa value. It was possible to check that most of the tested equipment parameters presented a good performance, although the film processing did not generate satisfactory results and caused reading difficulties. Many of the results of these reading were classified as unacceptable. Among these images, only a small percentage of them presented the fibers and microcalcifications of the sizes required by the Brazilian legislation. We concluded that it is only possible to generate good quality images if all the steps of the process are properly controlled. Therefore, it is relevant to invest in training, calibration and maintenance of the mammographic equipment. (Author)

  13. Bacteriological research for the contamination of equipment in chest radiography

    International Nuclear Information System (INIS)

    Choi, Seung Gu; Song, Woon Heung; Kweon, Dae Cheol

    2015-01-01

    The purpose is to determine the degree of contamination of the equipment for infection control in chest radiography of the radiology department. We confirmed by chemical and bacterial identification of bacteria of the equipment and established a preventive maintenance plan. Chest X-ray radiography contact area on the instrument patients shoulder, hand, chin, chest lateral radiography patient contact areas with a 70% isopropyl alcohol cotton swab were compared to identify the bacteria before and after sterilization on the patient contact area in the chest radiography equipment of the department. The gram positive Staphylococcus was isolated from side shoots handle before disinfection in the chest radiography equipment. For the final identification of antibiotic tested that it was determined by performing the nobobiocin to the sensitive Staphylococcus epidermidis. Chest radiography equipment before disinfecting the handle side of Staphylococcus epidermidis bacteria were detected using a disinfectant should be to prevent hospital infections

  14. Bacteriological research for the contamination of equipment in chest radiography

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Seung Gu; Song, Woon Heung; Kweon, Dae Cheol [Shinhan University, Uijeongbu (Korea, Republic of)

    2015-12-15

    The purpose is to determine the degree of contamination of the equipment for infection control in chest radiography of the radiology department. We confirmed by chemical and bacterial identification of bacteria of the equipment and established a preventive maintenance plan. Chest X-ray radiography contact area on the instrument patients shoulder, hand, chin, chest lateral radiography patient contact areas with a 70% isopropyl alcohol cotton swab were compared to identify the bacteria before and after sterilization on the patient contact area in the chest radiography equipment of the department. The gram positive Staphylococcus was isolated from side shoots handle before disinfection in the chest radiography equipment. For the final identification of antibiotic tested that it was determined by performing the nobobiocin to the sensitive Staphylococcus epidermidis. Chest radiography equipment before disinfecting the handle side of Staphylococcus epidermidis bacteria were detected using a disinfectant should be to prevent hospital infections.

  15. The qualification of electrical components and instrumentations relevant to safety; La qualificazione dei componenti elettrici e di strumentazione rilevanti per la sicurezza

    Energy Technology Data Exchange (ETDEWEB)

    Zambardi, F [ENEA - Direzione Sicurezza Nucleare e Protezione Sanitaria, Divisione Sistemi Elettrici e Strumentazione, Rome (Italy)

    1989-03-15

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

  16. Insights About Emergency Diesel Generator Failures from the USNRC's Common Cause Failure Database

    International Nuclear Information System (INIS)

    Mosleh, A.; Rasmuson, D.; Marshall, F.; Wierman, T.

    1999-01-01

    The US Nuclear Regulatory Commission has sponsored development of a database of common cause failure events for use in commercial nuclear power plant risk and reliability analyses. This paper presents a summary of the results from analysis of the emergency diesel generator data from the database. The presentation is limited to the overall insights, the design and manufacturing cause and the instrumentation and control sub-system

  17. Study of simple CFRP-metal joint failure

    Science.gov (United States)

    Cheng, Jingquan; Rodriguez, Antonio; Emerson, Nicolas; Symmes, Arthur

    2008-07-01

    In millimeter wavelength telescope design and construction, there have been a number of mysterious failures of simple CFRF-metal joints. Telescope designers have not had satisfactory interpretations of these failures. In this paper, factors which may influence the failure of joints are discussed. These include stress concentration, material creep, joint fatigue, reasons related to chemical process and manufacture process. Extrapolation formulas for material creep, joint fatigue, and differential thermal stresses are derived in this paper. Detailed chemical and manufacturing factors are also discussed. All these issues are the causes of a number of early failures under a loading which is significantly lower than the strength of adhesives used. For ensuring reliability of a precision instrument structure joint, the designer should have a thorough understanding of all these factors.

  18. An energy-efficient failure detector for vehicular cloud computing.

    Science.gov (United States)

    Liu, Jiaxi; Wu, Zhibo; Dong, Jian; Wu, Jin; Wen, Dongxin

    2018-01-01

    Failure detectors are one of the fundamental components for maintaining the high availability of vehicular cloud computing. In vehicular cloud computing, lots of RSUs are deployed along the road to improve the connectivity. Many of them are equipped with solar battery due to the unavailability or excess expense of wired electrical power. So it is important to reduce the battery consumption of RSU. However, the existing failure detection algorithms are not designed to save battery consumption RSU. To solve this problem, a new energy-efficient failure detector 2E-FD has been proposed specifically for vehicular cloud computing. 2E-FD does not only provide acceptable failure detection service, but also saves the battery consumption of RSU. Through the comparative experiments, the results show that our failure detector has better performance in terms of speed, accuracy and battery consumption.

  19. Evaluation of high frequency ground motion effects on the seismic capacity of NPP equipments

    International Nuclear Information System (INIS)

    Choi, In Kil; Seo, Jeong Moon; Choun, Young Sun

    2003-04-01

    In this study, the uniform hazard spectrum for the example Korean nuclear power plants sites were developed and compared with various response spectra used in past seismic PRA and SMA. It shows that the high frequency ground motion effects should be considered in seismic safety evaluations. The floor response spectra were developed using the direct generation method that can develop the floor response spectra from the input response spectrum directly with only the dynamic properties of structures obtained from the design calculation. Most attachment of the equipments to the structure has a minimum distortion capacity. This makes it possible to drop the effective frequency of equipment to low frequency before it is severely damaged. The results of this study show that the high frequency ground motion effects on the floor response spectra were significant, and the effects should be considered in the SPRA and SMA for the equipments installed in a building. The high frequency ground motion effects are more important for the seismic capacity evaluation of functional failure modes. The high frequency ground motion effects on the structural failure of equipments that attached to the floor by welding can be reduced by the distortion capacity of welded anchorage

  20. Harmful effects of lightning surge discharge on communications terminal equipments

    International Nuclear Information System (INIS)

    Liang, Sisi; Xu, Xiaoying; Tao, Zhigang; Dai, Yanling

    2013-01-01

    The interference problem of lightning surges on electronic and telecommunication products were examined, and a series of experiments were conducted to analyze the failure situations to find out the mechanisms of failures caused by the lightning surge. In addition, the ways in which lightning surges damaged equipment were deduced. It was found that failure positions were scattered and appeared in groups, and most of them were ground discharge. Internet access transformer had high withstand-voltage under the lightning pulse, and the lightning surge seldom passed through the internet access transformer. The lightning current can release to the ground via the computer network adapter of the terminal user. The study will help to improve the performance of lightning surge protection circuit and protection level.

  1. Seismic soil-structure-equipment interaction analysis of unit 5/6, Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kostov, M [Bulgarian Academy of Sciences, Central Laboratory for Seismic Mechanics and Earthquake Engineering, Sofia (Bulgaria)

    1995-07-01

    This research project is aimed to analyse problems of soil-structure-equipment interaction under seismic excitation in case of Kozloduy NPP. Reevaluation and upgrading of Kozloduy NPP has started after 1977 Vrancea earthquake. New Safe Shutdown Earthquake (SSE) level was defined, upgrading most of structural equipment was performed, seismic instrumentation was installed. New investigations were initiated after 1990 IAEA mission visited the site. A comprehensive site confirmation project was started with a subsequent structural and equipment reevaluation and upgrading. This work deals with Units 5 and 6 of WWER-1000 type only.

  2. Development of Partial Discharging Simulation Test Equipment

    Science.gov (United States)

    Kai, Xue; Genghua, Liu; Yan, Jia; Ziqi, Chai; Jian, Lu

    2017-12-01

    In the case of partial discharge training for recruits who lack of on-site work experience, the risk of physical shock and damage of the test equipment may be due to the limited skill level and improper operation by new recruits. Partial discharge simulation tester is the use of simulation technology to achieve partial discharge test process simulation, relatively true reproduction of the local discharge process and results, so that the operator in the classroom will be able to get familiar with and understand the use of the test process and equipment.The teacher sets up the instrument to display different partial discharge waveforms so that the trainees can analyze the test results of different partial discharge types.

  3. Molecular Structure Laboratory. Fourier Transform Nuclear Magnetic Resonance (FTNMR) Spectrometer and Ancillary Instrumentation at SUNY Geneseo

    Energy Technology Data Exchange (ETDEWEB)

    Geiger, David K [State Univ. of New York (SUNY), Geneseo, NY (United States)

    2015-12-31

    An Agilent 400-MR nuclear magnetic resonance (NMR) spectrometer and ancillary equipment were purchased, which are being used for molecular structure elucidation.  The instrumentation is housed in a pre-existing facility designed specifically for its use. This instrument package is being used to expand the research and educational efforts of the faculty and students at SUNY-Geneseo and is made available to neighboring educational institutions and business concerns.  Funds were also used for training of College personnel, maintenance of the instrumentation, and installation of the equipment.

  4. Maintenance-based prognostics of nuclear plant equipment for long-term operation

    Energy Technology Data Exchange (ETDEWEB)

    Welz, Zachary; Coble, Jamie; Upadhyaya, Belle; Hines, Wes [University of Tennessee, Knoxville (United States)

    2017-08-15

    While industry understands the importance of keeping equipment operational and well maintained, the importance of tracking maintenance information in reliability models is often overlooked. Prognostic models can be used to predict the failure times of critical equipment, but more often than not, these models assume that all maintenance actions are the same or do not consider maintenance at all. This study investigates the influence of integrating maintenance information on prognostic model prediction accuracy. By incorporating maintenance information to develop maintenance-dependent prognostic models, prediction accuracy was improved by more than 40% compared with traditional maintenance-independent models. This study acts as a proof of concept, showing the importance of utilizing maintenance information in modern prognostics for industrial equipment.

  5. Estimated dose to in-tank equipment: Phase 1 waste feed delivery

    International Nuclear Information System (INIS)

    Claghorn, R.D.

    1998-01-01

    This analysis estimates the radiation dose to the equipment that will be submerged in double-shell tank waste. The results of this analysis are intended to be the basis for specifications for in-tank equipment. The scope of this analysis is limited to the new equipment required for the delivery of waste feed to Phase 1 private contractors. Phase 1 refers to the first of a two-phase plan to privatize the remediation of Hanford's tank waste. The focus of this analysis is on waste feed delivery because of the extraordinarily high cost of any failure that would lead to the interruption of a steady flow of feed to the private contractors

  6. The statistical analysis of failure of a MEVATRON77 DX67 linear accelerator over a ten year period

    International Nuclear Information System (INIS)

    Aoyama, Hideki; Inamura, Keiji; Tahara, Seiji; Uno, Hirofumi; Kadohisa, Shigefumi; Azuma, Yoshiharu; Nakagiri, Yoshitada; Hiraki, Yoshio

    2003-01-01

    with each other. The relation between environment and the number of failures, it was observed that in the acceleration and pulse sections, failures increased as climatic temperatures fell. It is necessary to record equipment problems and failure in detail over a long period of time, to perform complete analyses, and to have a good working knowledge of equipment functions. Moreover, it is important to attempt to forecast future failures from observed failure patterns and, if possible, to avoid total failure in advance with prompt maintenance, and to have backup support organized in other equipment and at other institutions if equipment should break down. (author)

  7. Neutron scattering equipments in JAERI. Current status

    International Nuclear Information System (INIS)

    Hamaguchi, Yoshikazu; Minakawa, Nobuaki

    2003-01-01

    24 neutron scattering instruments are installed in the JRR-3M research reactor. Among them JAERI has 12 neutron scattering instruments. Those instruments are HRPD for high-resolution structural analysis, TAS-1 and TAS-2 for elastic and inelastic scattering and for magnetic scattering measurements by the polarized neutron, LTAS for elastic and inelastic scattering measurement at a low energy region, and for neutron device development, PNO for topography and for very small angle scattering measurement in a small Q range, NRG for neutron radiography, RESA for internal strain measurements, SANS for the molecule and semi-macroscopic magnetic structural analysis, BIX-2 and BIX-3 for the biological structural analysis research, and PGA for the research of prompt gamma-ray analysis. The university groups have 12 neutron scattering instruments. Since those instruments were installed at the period when JRR-3M was completed, about 10 years have passed. In order to match the old control systems with the progress of recent computer technologies, and peripheral equipment, numbers of instruments are being renewed. In the neutron guide hall of JRR-3M, the Ni mirror guide tube was replaced by a super mirror guide tube to increase neutron flux. The intensity of 2A flux was increased by a factor of about two. (J.P.N.)

  8. Control of equipment isolation system using wavelet-based hybrid sliding mode control

    Science.gov (United States)

    Huang, Shieh-Kung; Loh, Chin-Hsiung

    2017-04-01

    Critical non-structural equipment, including life-saving equipment in hospitals, circuit breakers, computers, high technology instrumentations, etc., is vulnerable to strong earthquakes, and on top of that, the failure of the vibration-sensitive equipment will cause severe economic loss. In order to protect vibration-sensitive equipment or machinery against strong earthquakes, various innovative control algorithms are developed to compensate the internal forces that to be applied. These new or improved control strategies, such as the control algorithms based on optimal control theory and sliding mode control (SMC), are also developed for structures engineering as a key element in smart structure technology. The optimal control theory, one of the most common methodologies in feedback control, finds control forces through achieving a certain optimal criterion by minimizing a cost function. For example, the linear-quadratic regulator (LQR) was the most popular control algorithm over the past three decades, and a number of modifications have been proposed to increase the efficiency of classical LQR algorithm. However, except to the advantage of simplicity and ease of implementation, LQR are susceptible to parameter uncertainty and modeling error due to complex nature of civil structures. Different from LQR control, a robust and easy to be implemented control algorithm, SMC has also been studied. SMC is a nonlinear control methodology that forces the structural system to slide along surfaces or boundaries; hence this control algorithm is naturally robust with respect to parametric uncertainties of a structure. Early attempts at protecting vibration-sensitive equipment were based on the use of existing control algorithms as described above. However, in recent years, researchers have tried to renew the existing control algorithms or developing a new control algorithm to adapt the complex nature of civil structures which include the control of both structures and non

  9. Improvement of equipment needed for the detection and characterization of nuclear material and radioactive samples at borders

    International Nuclear Information System (INIS)

    Arlt, R.; Kovar, A.; Swoboda, M.; Beck, P.; Duftschmid, K.E.; Lewis, W.

    2001-01-01

    Nuclear radiation measurement instruments and devices for the detection and characterisation of nuclear material and radioactive isotopes at borders play a decisive role in the set of technical measures needed to deal with the problem of illicit trafficking. Therefore the availability of a range of devices with adequate performance at affordable prices is essential. The needed equipment can be classified into the following categories: Detection equipment (border monitors and radiation pagers); Hand held devices for neutron/gamma source search and in-field characterisation of radiation sources by customs inspectors; NDA (non-destructive assay) instruments for in-depth investigation of a seized item by experts either in the field or under laboratory conditions. Instruments and techniques, which use destructive assay methods, are not considered in this paper. The most recent overview on the performance of such instruments is given in the Final Report of ITRAP (Illicit Trafficking Radiation Detection Assessment Program). According to the findings of ITRAP, although in all above mentioned categories equipment is commercially available, deficiencies and shortcomings were identified. In this paper we describe our effort in addressing some of the most essential equipment problems, identified in ITRAP - the sensitivity of border monitors with respect to the detection of nuclear material and the performance and usability of hand held and portable devices needed for in-field characterisation of seized items by customs inspectors

  10. Two-phase flow instrumentation research at RPI

    International Nuclear Information System (INIS)

    Lahey, R.T. Jr.; Krycuk, G.

    1979-01-01

    Novel instrumentation for the measurement of void fraction and phase velocity was developed. An optical digital interferometer and a dual beam x-ray equipment were designed for detection of voids. Pitot tube measurements were made to understand two-phase flow phenomena in liquid phase velocity

  11. Changes of the thermodynamic parameters in failure conditions of the micro-CHP cycle

    Science.gov (United States)

    Matysko, Robert; Mikielewicz, Jarosław; Ihnatowicz, Eugeniusz

    2014-03-01

    The paper presents the calculations for the failure conditions of the ORC (organic Rankine cycle) cycle in the electrical power system. It analyses the possible reasons of breakdown, such as the electrical power loss or the automatic safety valve failure. The micro-CHP (combined heat and power) system should have maintenance-free configuration, which means that the user does not have to be acquainted with all the details of the ORC system operation. However, the system should always be equipped with the safety control systems allowing for the immediate turn off of the ORC cycle in case of any failure. In case of emergency, the control system should take over the safety tasks and protect the micro-CHP system from damaging. Although, the control systems are able to respond quickly to the CHP system equipped with the inertial systems, the negative effects of failure are unavoidable and always remain for some time. Moreover, the paper presents the results of calculations determining the inertia for the micro-CHP system of the circulating ORC pump, heat removal pump (cooling condenser) and the heat supply pump in failure conditions.

  12. Changes of the thermodynamic parameters in failure conditions of the micro-CHP cycle

    Directory of Open Access Journals (Sweden)

    Matysko Robert

    2014-03-01

    Full Text Available The paper presents the calculations for the failure conditions of the ORC (organic Rankine cycle cycle in the electrical power system. It analyses the possible reasons of breakdown, such as the electrical power loss or the automatic safety valve failure. The micro-CHP (combined heat and power system should have maintenance-free configuration, which means that the user does not have to be acquainted with all the details of the ORC system operation. However, the system should always be equipped with the safety control systems allowing for the immediate turn off of the ORC cycle in case of any failure. In case of emergency, the control system should take over the safety tasks and protect the micro-CHP system from damaging. Although, the control systems are able to respond quickly to the CHP system equipped with the inertial systems, the negative effects of failure are unavoidable and always remain for some time. Moreover, the paper presents the results of calculations determining the inertia for the micro-CHP system of the circulating ORC pump, heat removal pump (cooling condenser and the heat supply pump in failure conditions.

  13. CRITICAL ANALYSIS OF THEIR RISK FINANCIAL INSTRUMENTS

    Directory of Open Access Journals (Sweden)

    CARUNTU GENU ALEXANDRU

    2013-12-01

    Full Text Available In the last decade, accounting for financial instruments has experienced a revolution, following the publication of accounting rules on recognition and measurement of these instruments saddle. Need to develop standards for financial instruments appeared on the background of explosion using derivatives and the markets in which they are traded, and as a result of numerous financial scandals that rocked developed countries in the last decade. These were based, among other causes, improper use of derivatives and hiding their disastrous effects of poor management by keeping them off balance and failure to provide related information in the notes of the financial statements.

  14. Use of the virtual instrument technology in complex diagnostics of marine electrical equipment

    Directory of Open Access Journals (Sweden)

    Ivlev M. L.

    2017-12-01

    Full Text Available The assessment of the most informative methods of diagnostics of mechanisms with electric drive has been given; their realization in a measuring complex on the basis of the virtual device has been considered. The comparative analysis of vibration methods for the analysis of current spectra and the thermal method of nondestructive testing has been carried out. It has been stated that methods of vibration diagnostics are more sensitive to defects in the mechanical part of the electric drive (determination of defects in bearing assemblies, misalignment of shafts, imbalance of rotating parts. Analysis of the current spectrum at the early stage has shown the defects of rotor windings, static and dynamic rotor eccentricity. The temperature of the bearing assemblies and the stator (the thermal control method indicates the defects in lubrication and cooling systems. The set of methods of nondestructive control allows increase the completeness and reliability of diagnosis of the mechanism with electric drive. The optimal solution to realize into one measuring instrument all methods of diagnostics is to use the technology of virtual instruments. The list of components for the measuring part of the complex and the functional scheme of the program for processing the results have been given. Spectra of vibration of defective mechanisms have been obtained with the help of the measuring complex based on the virtual instrument. Some recommendations have been given on the introduction of the virtual appliance in the State register of measuring instruments.

  15. Policy instruments for energy conservation: A multidimensional assessment

    International Nuclear Information System (INIS)

    Giraudet, Louis-Gaetan

    2011-01-01

    This thesis evaluates the effectiveness of various forms of taxes, subsidies and regulations implemented to correct for market failures that may prevent energy savings. It builds on various approaches, with gradual complexity. First, a standard micro-economic model is developed to compare the static performances of these instruments. Second, the representation of consumer behaviour is strengthened in a model of the residential energy demand for space heating in France, which allows to identify the dynamic mechanisms by which instruments can correct for the main market failures. Third, an empirical evaluation of 'white certificate' schemes - tradable energy saving obligations imposed on energy operators - is made from the comparison between the British, Italian and French experiences, taking into account national institutions. The following conclusions can be drawn from these various approaches: (i) energy taxes, by encouraging both energy efficiency investment and sufficiency behaviour, are particularly effective; (ii) energy efficiency regulations have a significant impact on the diffusion of efficient technologies; (iii) subsidies to energy efficiency induce a large rebound effect; (iv) depending on the institutional environment in which they operate, white certificate schemes combine different properties of these instruments. Applied to the French residential building sector, the most effective combination of these instruments does not allow to reach the energy saving target set by the Government. (author)

  16. Reactor instrumentation experience at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Soares, A.J.

    1997-01-01

    The Instituto de Pesquisas Energeticas e Nucleares (IPEN) in Sao Paulo started in 1977 development of nuclear instrumentation. In 1982 two groups were established, one responsible for maintenance of electronic equipment and the other, the Nuclear Instrumentation Section (NIS), for new projects, such as a light water moderated critical facility (IPEN/MB-0). The NIS had the responsibility to execute all necessary activities to develop the ''nonconventional'' instrumentation systems: control, protection and radiation monitoring for the IPEN/MB-01 facility. After the commissioning of the critical facility the NIS group started the development of instrumentation systems for a power reactor. As a first step an overall review of the quality assurance programme was implemented. In parallel the development of self powered detectors was carried out. (author). 7 figs

  17. Imaging Sensor Flight and Test Equipment Software

    Science.gov (United States)

    Freestone, Kathleen; Simeone, Louis; Robertson, Byran; Frankford, Maytha; Trice, David; Wallace, Kevin; Wilkerson, DeLisa

    2007-01-01

    The Lightning Imaging Sensor (LIS) is one of the components onboard the Tropical Rainfall Measuring Mission (TRMM) satellite, and was designed to detect and locate lightning over the tropics. The LIS flight code was developed to run on a single onboard digital signal processor, and has operated the LIS instrument since 1997 when the TRMM satellite was launched. The software provides controller functions to the LIS Real-Time Event Processor (RTEP) and onboard heaters, collects the lightning event data from the RTEP, compresses and formats the data for downlink to the satellite, collects housekeeping data and formats the data for downlink to the satellite, provides command processing and interface to the spacecraft communications and data bus, and provides watchdog functions for error detection. The Special Test Equipment (STE) software was designed to operate specific test equipment used to support the LIS hardware through development, calibration, qualification, and integration with the TRMM spacecraft. The STE software provides the capability to control instrument activation, commanding (including both data formatting and user interfacing), data collection, decompression, and display and image simulation. The LIS STE code was developed for the DOS operating system in the C programming language. Because of the many unique data formats implemented by the flight instrument, the STE software was required to comprehend the same formats, and translate them for the test operator. The hardware interfaces to the LIS instrument using both commercial and custom computer boards, requiring that the STE code integrate this variety into a working system. In addition, the requirement to provide RTEP test capability dictated the need to provide simulations of background image data with short-duration lightning transients superimposed. This led to the development of unique code used to control the location, intensity, and variation above background for simulated lightning strikes

  18. DNV launches new recommended practice for design of subsea equipment

    Energy Technology Data Exchange (ETDEWEB)

    Toerstad, Elisabeth Heggelund

    2005-07-01

    The application of modern corrosion-resistant alloys to subsea pipelines and components has led to serious problems of hydrogen embrittlement from the corrosion protection system, resulting in cracks and leaks. The most commonly known incidents of this kind are the duplex hubs on Voinhaven, UK and Garn West and the 13% Cr pipelines on Tune and Aasgard, all at the Norwegian shelf. Understanding the nature of this problem has called for a broad multidisciplinary approach, involving expertise on corrosion and metallurgy as well as structural design and integrity. Competence in probabilistic analyses and risk assessments has also been necessary in order to set acceptance criteria and evaluate probability of failure for existing installations. (Det Norske Veritas (DNV) is now about to issues a Recommended Practise (RP) for design of subsea equipment in duplex steels under Cathodic Protection. The RP is based on knowledge gained through failure investigations, qualification pr grams and research work, and a broad industry consortium has contributed with experience and knowledge. Hydrogen Induced Stress Cracking (HISC) due to hydrogen from the Cathodic Protection (CP) system has been one of the most frequent and costly failure modes for subsea equipment and pipelines in the North Sea over the recent years. Today, the international oil business is looking to Norway for assistance in establishing detailed knowledge about and preventive measures against this failure mode. A significant research work is currently being carried out jointly by DNV, SINTEF and TWI (The Welding Institute), supported by a broad industry consortium - aiming at a better understanding of the HISC (Hydrogen Induced Stress Cracking) mechanism and establishment of test methods which reflect the sensitivity to cracking. DNV has also established a Recommended Practice, which will be issued late 2005. It reflects the experience gained from the failure examinations, fitness for purpose evaluations, research

  19. Operability test procedure [Tank] 241-SY-101 equipment removal system

    International Nuclear Information System (INIS)

    Mast, J.C.

    1994-01-01

    The 241-SY-101 equipment removal system (ERS) consists of components, equipment, instrumentation and procedures that will provide the means to disconnect, retrieve, contain, load and transport the Mitigation Pump Assembly (MPA) from waste Tank 241-SY-101 to the Central Waste Complex (CWC). The Operability Test Procedure (OTP) will test the interfaces between ERS components and will rehearse the procedure for MPA removal and transportation to the extent they can be mocked-up at the CTF (Cold Test Facility). At the conclusion of the OTP, the ERS components and equipment will be removed from the CTF, entered into the Component Based Recall System (CBRS), and stored until needed for actual MPA removal and transportation

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  1. Practices of prolongation of the I and C equipment lifetime

    International Nuclear Information System (INIS)

    Samoylov, O.B.; Pronin, V.S.; Savelov, I.D.; Bogomazov, V.A.; Drumov, V.V.; Chudin, A.G.

    2000-01-01

    The lifetime of nuclear power plants (NPP) always exceeds the operational time of Instrumentation and Control (I and C) systems. Ageing of I and C equipment in NPPs have many aspects. Research of these aspects is being performed in OKB Mechanical Engineering. Under condition of fast development of I and C systems and applying more stringent safety requirements, modernization of the equipment irrespective of its operational condition is getting important. However, an equipment of I and C systems operated in Russia was designed and manufactured applying highest requirements for a reliability of their work during its whole operational time. Therefore, in many cases it is not necessary to replace them in spite of expiration of their specified lifetime. During operation this equipment is maintained in a proper operation condition by a special service procedures stipulated by its development. When the equipment lifetime approaches to its end, lifetime extension for the certain period should be considered. (author)

  2. An instrument for X-ray set quality assurance measurements

    International Nuclear Information System (INIS)

    Willetts, R.J.; West, M.B.; Brydon, J.

    1989-01-01

    This paper describes a prototype electronic instrument for performing quality assurance (QA) measurements on diagnostic radiological equipment with a view to long-term performance assessment on a Regional basis. The instrument is based on a Tandy 200 laptop computer and has been developed primarily to include the assessment of image intensifier/TV systems in a general QA package. It is capable of accepting signals from the following sources: (1) a radiation detector (diode array); (2) a Keithley kV divider (Keithley Instruments, Inc.); (3) the video output of an image intensifier system. (author)

  3. Hybrid instrument applied to human reliability study in event of loss of external electric power in a nuclear power plant

    International Nuclear Information System (INIS)

    Martins, Eduardo Ferraz

    2015-01-01

    The study projects in highly complex installations involves robust modeling, supported by conceptual and mathematical tools, to carry out systematic research and structured the different risk scenarios that can lead to unwanted events from occurring equipment failures or human errors. In the context of classical modeling, the Probabilistic Safety Analysis (PSA) seeks to provide qualitative and quantitative information about the project particularity and their operational facilities, including the identification of factors or scenarios that contribute to the risk and consequent comparison options for increasing safety. In this context, the aim of the thesis is to develop a hybrid instrument (CPP-HI) innovative, from the integrated modeling techniques of Failure Mode and Effect Analysis (FMEA), concepts of Human Reliability Analysis and Probabilistic Composition of Preferences (PCP). In support of modeling and validation of the CPP-HI, a simulation was performed on a triggering event 'Loss of External Electric Power' - PEEE, in a Nuclear Power plant. The results were simulated in a virtual environment (sensitivity analysis) and are robust to the study of Human Reliability Analysis (HRA) in the context of the PSA. (author)

  4. Development of IPRO-ZONE to Determine Component Failure Modes Affected by a Fire Event

    International Nuclear Information System (INIS)

    Kang, Dae Il; Han, Sang Hoon

    2010-01-01

    A Fire PSA requires a PSA analyst to select internal initiating events and to determine component failure modes for fire occurrence event of each fire compartment. The component failure modes caused by a fire depend on the several factors. These factors are whether components and their relating equipment and cables are located at fire initiation and propagation compartments or not, fire effects on control and power cables for components and their relating equipment, designed failure modes of component, success criteria in a PSA model, etc. Up to the present, a PSA analyst has been manually determining component failure modes based on criteria mentioned above. This task is one of the difficult works required for fire PSA expertise. In addition, since it requires much information, a fire PSA analyst may have difficulty in maintaining consistency for determining the component failure modes and documentation for them. After determining the component failure modes, internal PSA basic events corresponding to the component failure modes are selected and fire events are modeled for the selected basic events if required. KAERI has been developing the IPRO-ZONE (interface program for constructing zone effect table) to determine component failure modes affected by a fire, to select the internal PSA basic events, and to generate fire events to be modeled. In this paper, we introduce the overview of the IPRO-ZONE and approaches for determining component failure modes implemented in the IPRO-ZONE

  5. Maintenance or replacement of primary equipments

    International Nuclear Information System (INIS)

    Branchu, J.

    1995-01-01

    The principal materials, such as the primary equipments of a PWR type steam generator, have a finite service life. Framatome, builder of steam generators and maintenance contractor of Electricite de France has developed a methodology for the maintenance or the replacement of primary equipments. The paper describes the methodology followed by Framatome to identify and localize the wear mode and to treat or repair the component. Four failure modes have been considered: crack propagation, rubbing/vibration wear, neutron irradiation and corrosion propagation under permanent stress. A kinetic modelling of wear propagation has been computerized and validated using mechanical tests on Inconel 600 mockups. These analyses have allow to determine the strategy of repair or replacement of vessel heads for each unit. The method is evaluated taking into account the risk assessment, cost, dosimetry, efficiency and time delay involved. (J.S.). 1 fig., 3 photos

  6. Beam instrumentation in the LEP Pre-injector

    International Nuclear Information System (INIS)

    Battisti, S.; Bottollier, J.F.; Frammery, B.; Szeless, B.; Van Rooy, M.

    1987-01-01

    The main purpose of this paper is to review the beam instrumentation of the LEP pre-injector (LPI) including its design philosophy and software. The usefulness of these equipments for the LPI start-up is considered from an operational point of view and encountered problems are mentioned

  7. Development of support system for maintenance and administration of reprocessing plant equipment

    International Nuclear Information System (INIS)

    Iwasaki, Syogo; Taniguchi, Takayuki; Shiraishi, Yoshihiko; Isaka, Kazuo

    1998-01-01

    Each year, maintenance work is carried out for about 10,000 pieces of equipment, including mechanical devices, electric equipment and instruments, at the Tokai Reprocessing Plant. Ninety percent of such maintenance work is preventive maintenance. In order to manage the information about the maintenance work, a computer support system was developed between 1985 and 1992. Twenty-seven thousand pieces of equipment and 180,000 maintenance histories have already been registered in the system. The system has been used for planning inspections and replacement of equipment as well as checking their maintenance histories. Actual usage of the system has shown that some auxiliary functions need to be added. The system will therefore be improved and extended. (author)

  8. Guideline for design and construction radiation monitoring equipments for Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Miyabe, Kenjiro; Ninomiya, Kazushige; Jin, Kazumi; Morifuji, Masayuki; Nemoto, Kazuhiko; Sato, Akira; Kawai, Keiichi

    1999-12-01

    Various kind of radiation monitoring equipment are used in radiation controlled area at each facility of Tokai reprocessing plant. These equipments have been designed and constructed based on the users requirements, and permitted by governmental regulation office. And, design has been carried out in consideration of the adoption of the new technology and our operational experience. Then, it has been used effectively for the radiation control of the facilities. This report summarizes the technical requirements that should be taken into consideration in the design and installation of radiation monitoring equipments. These requirements are fundamentally applicable when the equipments of the new facilities will be designed or the present instruments will be replaced. (author)

  9. HTGR Measurements and Instrumentation Systems

    International Nuclear Information System (INIS)

    Ball, Sydney J.; Holcomb, David Eugene; Cetiner, Mustafa Sacit

    2012-01-01

    This report provides an integrated overview of measurements and instrumentation for near-term future high-temperature gas-cooled reactors (HTGRs). Instrumentation technology has undergone revolutionary improvements since the last HTGR was constructed in the United States. This report briefly describes the measurement and communications needs of HTGRs for normal operations, maintenance and inspection, fuel fabrication, and accident response. The report includes a description of modern communications technologies and also provides a potential instrumentation communications architecture designed for deployment at an HTGR. A principal focus for the report is describing new and emerging measurement technologies with high potential to improve operations, maintenance, and accident response for the next generation of HTGRs, known as modular HTGRs, which are designed with passive safety features. Special focus is devoted toward describing the failure modes of the measurement technologies and assessing the technology maturity.

  10. Instrumentation for Basic Research in Communication and Hearing Protection Systems

    National Research Council Canada - National Science Library

    Ray, Laura

    2004-01-01

    .... The instrumentation provided by this grant consists of an Artificial Head Measurement System, a Low Frequency Acoustic Test Cell, a vibration isolation table, and digital signal processing equipment...

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

    International Nuclear Information System (INIS)

    Syahrudin Yusuf; M Subhan; Ikhsan Shobari; Sutomo Budihardjo

    2010-01-01

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

  12. Behavioural Motives of Acquisition of Solar-driven Equipment

    Directory of Open Access Journals (Sweden)

    Shkurupska Iryna O.

    2013-12-01

    Full Text Available The article identifies needs of the target group, namely structure of motives, which justify making a decision to buy, in order to create efficient marketing strategy of an enterprise, which sell solar-driven equipment in Ukraine. There are five segments in the domestic market of helio-systems: individual consumers, recreation industry, agrarian industry, construction and social spheres. The article allocates 15 motives of acquisition of the solar-driven equipment for these segments, the most important of which are price, availability of solar energy, alternative price and energy saving. Besides, the structure of such motives is determined for each segment individually. In order to choose specific marketing instruments in the policy of promotion of solar-driven equipment, the article identifies differences in the form of goals of use and motives of acquisition between the specified consumer segments. The article reveals certain barriers that interfere with acquisition of solar-driven equipment – low level of trust into helio-systems, conservatism of consumers, absence of free applications for consumers – overcoming which is only possible with the help of certain marketing actions.

  13. High level radioactive waste vitrification process equipment component testing

    International Nuclear Information System (INIS)

    Siemens, D.H.; Heath, W.O.; Larson, D.E.; Craig, S.N.; Berger, D.N.; Goles, R.W.

    1985-04-01

    Remote operability and maintainability of vitrification equipment were assessed under shielded-cell conditions. The equipment tested will be applied to immobilize high-level and transuranic liquid waste slurries that resulted from plutonium production for defense weapons. Equipment tested included: a turntable for handling waste canisters under the melter; a removable discharge cone in the melter overflow section; a thermocouple jumper that extends into a shielded cell; remote instrument and electrical connectors; remote, mechanical, and heat transfer aspects of the melter glass overflow section; a reamer to clean out plugged nozzles in the melter top; a closed circuit camera to view the melter interior; and a device to retrieve samples of the glass product. A test was also conducted to evaluate liquid metals for use in a liquid metal sealing system

  14. Impact of equipment failures and wind correlation on generation expansion planning

    DEFF Research Database (Denmark)

    Pineda, S.; Morales, J.M.; Ding, Y.

    2014-01-01

    the generating company (GENCO) and the system operator. The upper-level problem maximizes the GENCO's expected profit, while the lower-level problem simulates an hourly market-clearing procedure, through which LMPs are determined. The uncertainty pertaining to failures and wind power correlation is characterized......Generation expansion planning has become a complex problem within a deregulated electricity market environment due to all the uncertainties affecting the profitability of a given investment. Current expansion models usually overlook some of these uncertainties in order to reduce the computational...

  15. A Perspective on Equipment Design for Fusion Remote Handling

    International Nuclear Information System (INIS)

    Mills, S.; Haist, B.; Hamilton, D.

    2006-01-01

    For 8 years, JET remote operations have become more capable and confident. Many tasks have been successfully completed, even those never intended to be remote maintenance activities. The general approach to the provision of remote handling equipment at JET has been the preferred use of commercially-off-the-shelf equipment. In the areas of electrical, electronic, software and control this approach has been generally achievable. However, in the area of mechanical equipment it has been more difficult. In particular the RH tooling has been almost entirely bespoke as its requirements are highly sensitive to the design of the JET component being handled and there are many design variations. Hence, JET has required the design and manufacture of over 700 types of bespoke RH equipment. This paper will discuss the experience of introducing and developing remote handling mechanical equipment for JET. The paper will cover the relationship between the remote handling equipment and the JET component design and the potential for improving the design function. A major lesson from the introduction of remote handling to JET has been demonstration of the very close interdependency of the design of JET components with design of remote handling tooling. The JET remote handling manual was originally introduced as the vehicle to ensure remote handling compatibility by the introduction of standards. Experience has shown that in general the remote handling manual approach has been insufficient. Future fusion machines will be much more complex than JET and will demand even greater remote handling compatibility. This paper will discuss possible methods for improving this process. Equipment operating in a high radiation environment must be dependable It may spend part of its time in areas that would be extremely difficult to recover from in the case of failure. The equipment may also have a high duty cycle to minimise shutdown times and probably cannot be manually inspected on a frequent

  16. Design and manufacture NCS instruments for cement factories

    International Nuclear Information System (INIS)

    Nguyen Thanh Tuy; Nguyen Tien Dung; Dang Nguyet Anh; Nguyen Phuc; Khuong Thanh Tuan; Luong Duc Long; Pham Trong Quyen

    2003-01-01

    The ministry project 'Design and manufacture some of NCS instruments for cement factories' is a part of instrumentation for cement production in Vietnam. The objectives of the project include: 1/Design and manufacture the automatic control system for cement raw material mixing, connected to components X-ray analyzer through serial port of PC; 2/Design and manufacture the automatic discharge control system using gamma rays. The instruments, made by the project , for controlling the conveyor belt weighing machine can be easily improved for various types of conveyor belt weighing machines. Their mobility and software equipped can be adapted for requirement of modern cement production technology. The instruments are operating well in some cement factories and they are helping in quality control. (NHA)

  17. Timing criteria for supplemental BWR emergency response equipment

    International Nuclear Information System (INIS)

    Bickel, John H.

    2015-01-01

    The Great Tohuku Earthquake and subsequent Tsunami represented a double failure event which destroyed offsite power connections to Fukushima-Daiichi site and then destroyed on-site electrical systems needed to run decay heat removal systems. The accident could have been mitigated had there been supplemental portable battery chargers, supplemental pumps, and in-place piping connections to provide alternate decay heat removal. In response to this event in the USA, two national response centers, one in Memphis, Tennessee, and another in Phoenix, Arizona, will begin operation. They will be able to dispatch supplemental emergency response equipment to any nuclear plant in the U.S. within 24 hours. In order to define requirements for supplemental nuclear power plant emergency response equipment maintained onsite vs. in a regional support center it is necessary to confirm: (a) the earliest time such equipment might be needed depending on the specific scenario, (b) the nominal time to move the equipment from a storage location either on-site or within the region of a nuclear power plant, and (c) the time required to connect in the supplemental equipment to use it. This paper describes an evaluation process for a BWR-4 with a Mark I Containment starting with: (a) severe accident simulation to define best estimate times available for recovery based on the specific scenario, (b) identify the key supplemental response equipment needed at specific times to accomplish recovery of key safety functions, and (c) evaluate what types of equipment should be warehoused on-site vs. in regional response centers. (authors)

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

    Science.gov (United States)

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

    2012-03-01

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

  19. The failures of root canal preparation with hand ProTaper.

    Science.gov (United States)

    Bătăiosu, Marilena; Diaconu, Oana; Moraru, Iren; Dăguci, C; Tuculină, Mihaela; Dăguci, Luminiţa; Gheorghiţă, Lelia

    2012-07-01

    The failures of root canal preparation are due to some anatomical deviation (canal in "C" or "S") and some technique errors. The technique errors are usually present in canal root cleansing and shaping stage and are the result of endodontic treatment objectives deviation. Our study was made on technique errors while preparing the canal roots with hand ProTaper. Our study was made "in vitro" on 84 extracted teeth (molars, premolars, incisors and canines). The canal root of these teeth were cleansed and shaped with hand ProTaper by crown-down technique and canal irrigation with NaOCl(2,5%). The dental preparation control was made by X-ray. During canal root preparation some failures were observed like: canal root overinstrumentation, zipping and stripping phenomenon, discarded and/or fractured instruments. Hand ProTaper represents a revolutionary progress of endodontic treatment, but a deviation from accepted rules of canal root instrumentation can lead to failures of endodontic treatment.

  20. Finite Element Study on Continuous Rotating versus Reciprocating Nickel-Titanium Instruments.

    Science.gov (United States)

    El-Anwar, Mohamed I; Yousief, Salah A; Kataia, Engy M; El-Wahab, Tarek M Abd

    2016-01-01

    In the present study, GTX and ProTaper as continuous rotating endodontic files were numerically compared with WaveOne reciprocating file using finite element analysis, aiming at having a low cost, accurate/trustworthy comparison as well as finding out the effect of instrument design and manufacturing material on its lifespan. Two 3D finite element models were especially prepared for this comparison. Commercial engineering CAD/CAM package was used to model full detailed flute geometries of the instruments. Multi-linear materials were defined in analysis by using real strain-stress data of NiTi and M-Wire. Non-linear static analysis was performed to simulate the instrument inside root canal at a 45° angle in the apical portion and subjected to 0.3 N.cm torsion. The three simulations in this study showed that M-Wire is slightly more resistant to failure than conventional NiTi. On the other hand, both materials are fairly similar in case of severe locking conditions. For the same instrument geometry, M-Wire instruments may have longer lifespan than the conventional NiTi ones. In case of severe locking conditions both materials will fail similarly. Larger cross sectional area (function of instrument taper) resisted better to failure than the smaller ones, while the cross sectional shape and its cutting angles could affect instrument cutting efficiency.

  1. Methodology for Risk Analysis of Dam Gates and Associated Operating Equipment Using Fault Tree Analysis

    National Research Council Canada - National Science Library

    Patev, Robert C; Putcha, Chandra; Foltz, Stuart D

    2005-01-01

    .... This report summarizes research on methodologies to assist in quantifying risks related to dam gates and associated operating equipment, and how those risks relate to overall spillway failure risk...

  2. Examination of pump failure data in the nuclear power industry

    International Nuclear Information System (INIS)

    Casada, D.

    1996-01-01

    There are several elements that are critical to any program which is used to optimize the availability and reliability of process equipment. Perhaps the most important elements are routine monitoring and predictive maintenance elements. In order to optimize equipment monitoring and predictive maintenance, it is necessary to fundamentally and thoroughly understand the principal failure modes for the equipment and the effectiveness of alternative monitoring methods. While these observations are general in nature, they are certainly true for the open-quotes heartclose quotes of fluid systems - pumps. In recent years, particularly within the last decade, the capabilities and ease of use of previously existing pump diagnostic technologies, such as vibration monitoring and oil analysis, have improved dramatically. Newer technologies, such as thermal imaging, have been found effective at detecting certain undesirable or degraded conditions, such as misalignment and overheated bearings or packing. The ASME Code and NRC regulatory requirements have been, like essentially all similar code and regulatory bodies, conservative in their adoption or endorsement of newer technologies. The requirements prescribed by the Code and endorsed by the NRC have, in their essence, changed only minimally over more than a dozen years. As a follow-on to studies of check valve failure experience in the nuclear industry that have proven useful in identifying the effectiveness of alternative monitoring methods, a study of nuclear industry pump failure data has been conducted. The results of this study, conducted for the NRC by Oak Ridge National Laboratory, are presented. The historical effectiveness of both regulatory required and voluntarily implemented pump monitoring programs are shown. The distribution of pump failures by application, affected area, and level of significance are indicated. Apparent strengths and weaknesses of alternative monitoring methods are discussed

  3. Examination of pump failure data in the nuclear power industry

    Energy Technology Data Exchange (ETDEWEB)

    Casada, D. [Oak Ridge National Lab., TN (United States)

    1996-12-01

    There are several elements that are critical to any program which is used to optimize the availability and reliability of process equipment. Perhaps the most important elements are routine monitoring and predictive maintenance elements. In order to optimize equipment monitoring and predictive maintenance, it is necessary to fundamentally and thoroughly understand the principal failure modes for the equipment and the effectiveness of alternative monitoring methods. While these observations are general in nature, they are certainly true for the {open_quotes}heart{close_quotes} of fluid systems - pumps. In recent years, particularly within the last decade, the capabilities and ease of use of previously existing pump diagnostic technologies, such as vibration monitoring and oil analysis, have improved dramatically. Newer technologies, such as thermal imaging, have been found effective at detecting certain undesirable or degraded conditions, such as misalignment and overheated bearings or packing. The ASME Code and NRC regulatory requirements have been, like essentially all similar code and regulatory bodies, conservative in their adoption or endorsement of newer technologies. The requirements prescribed by the Code and endorsed by the NRC have, in their essence, changed only minimally over more than a dozen years. As a follow-on to studies of check valve failure experience in the nuclear industry that have proven useful in identifying the effectiveness of alternative monitoring methods, a study of nuclear industry pump failure data has been conducted. The results of this study, conducted for the NRC by Oak Ridge National Laboratory, are presented. The historical effectiveness of both regulatory required and voluntarily implemented pump monitoring programs are shown. The distribution of pump failures by application, affected area, and level of significance are indicated. Apparent strengths and weaknesses of alternative monitoring methods are discussed.

  4. Project «Zero Failure Level». Organization, State, Tasks

    International Nuclear Information System (INIS)

    Ugryumov, A.

    2015-01-01

    This paper starts with description of organizational actions and structure of the project. Tree of failures - hierarchical list; VVER-1000 FA failure main features like: change of geometrical form; mechanical damage; leaking FA and post irradiation examination of leaking fuel assemblies VVER-1000 are also presented. At the end author concluded that: 1) Organizational and technical actions are completed. 2) Significant part of works per stage «Determination of current state» is fulfilled. 3) Systematic cause of the main feature of failure – leaking of FA- is the debris damage of fuel rod cladding with foreign objects. 4) It is important to equip NPPs with modern means of FA inspection and means of extraction of foreign objects

  5. Lessons learned from failure analysis

    International Nuclear Information System (INIS)

    Le May, I.

    2006-01-01

    Failure analysis can be a very useful tool to designers and operators of plant and equipment. It is not simply something that is done for lawyers and insurance companies, but is a tool from which lessons can be learned and by means of which the 'breed' can be improved. In this presentation, several failure investigations that have contributed to understanding will be presented. Specifically, the following cases will be discussed: 1) A fire at a refinery that occurred in a desulphurization unit. 2) The failure of a pipeline before it was even put into operation. 3) Failures in locomotive axles that took place during winter operation. The refinery fire was initially blamed on defective Type 321 seamless stainless steel tubing, but there were conflicting views between 'experts' involved as to the mechanism of failure and the writer was called upon to make an in-depth study. This showed that there were a variety of failure mechanism involved, including high temperature fracture, environmentally-induced cracking and possible manufacturing defects. The unraveling of the failure sequence is described and illustrated. The failure of an oil transmission was discovered when the line was pressure tested some months after it had been installed and before it was put into service. Repairs were made and failure occurred in another place upon the next pressure test being conducted. After several more repairs had been made the line was abandoned and a lawsuit was commenced on the basis that the steel was defective. An investigation disclosed that the material was sensitive to embrittlement and the causes of this were determined. As a result, changes were made in the microstructural control of the product to avoid similar problems in future. A series of axle failures occurred in diesel electric locomotives during winter. An investigation was made to determine the nature of the failures which were not by classical fatigue, nor did they correspond to published illustrations of Cu

  6. Re-fabrication and Instrumentation - resume and outlook

    International Nuclear Information System (INIS)

    Kleeman, Hans-Joerg; Oberlaender, Barbara C.

    2005-01-01

    The special technique ''re-fabrication and instrumentation'' applied at the Institute for Energy Technology (IFE) makes further testing and measuring of irradiated fuel rods in the Halden Boiling Water Reactor (HBWR) possible. Machines, necessary for such operations, were designed and produced at IFE in the years 1991-92. Hot Lab-operations called ''re-fabrication'' include all modifications necessary to load an irradiated fuel rod, commercial or experimental, into the Halden reactor for further testing. ''Instrumentation'' includes all operations necessary to fit instruments into an irradiated fuel rod segment to measure for instance the temperature in the centreline of the fuel stack, pressure increase in the fuel rod and/or changes of the rod length during reactor experiments. The machines used are referred to as: ''Cutting and Grinding Unit'' for machining of the canning; ''Freezing and Drilling Unit'' for drilling of the centreline thermocouple hole in the active fuel stack;''Welding and Drying Unit'' a TIG welding machine for the circumferential welds and the seal welding; and a hydraulic ''Encapsulation Bench''. The ''Welding and Drilling Unit'' includes also a ''He-leak test chamber'' and a ''Hydraulic Press''. In addition, different types of PIE methods are used in quality assurance and documenting of the work done with the fuel rod. For example neutron radiography, visual inspection, dimension measurement, free volume measurements, equipment to measure the flow capability through the fuel stack and different function tests of the measuring devices. This paper will give an overview of the work done so far with this equipment and give information about new equipment which will be installed soon to deal with even more complicated test fuel designs. (Author)

  7. IAEA preparations for the year 2000 compliance of safeguards equipment systems

    International Nuclear Information System (INIS)

    Aparo, M.; Barnes, B.; Lewis, W.; Hsiung, Sue

    1999-01-01

    The Department of Safeguards, IAEA, has used equipment systems for acquiring relevant data to support safeguards evaluation and verification activities. Typically an equipment system consists of EPROM (embedded system), a connecting personal computer with instrument software for data acquisition, and may include data evaluation software. Complementing the equipment systems is a collection of general evaluation software systems (application software) which support the analysis of the acquired data. In preparing for the year 2000 compliance of all safeguards systems, SGTS (Safeguards Division of Technical Services) in IAEA, must ascertain the equipment systems and the evaluation software authorised for inspection use can properly operate through the passage of year 2000. We present the year 2000 challenge for these systems, the approach we use to tackle the problem, and the status of our year 2000 project. (author)

  8. Pengukuran Overall Equipment Effectiveness (Oee) Dengan Labview 8.5 Sebagai Pengendali Maintenance

    OpenAIRE

    Syarief, Syafrizal

    2015-01-01

    Total Productive Maintenance (TPM) is a philosophy that aims to maximize the effectiveness of the facilities used in industry, it is applied to analyze problems that occur on any equipment and machinery with a method of calculation of Overall Equipment Effectiveness (OEE) of product quality. Value is determined by OEE Availability, Performance and Yield / Quality. LabVIEW (Laboratory Virtual Instrument Engineering Workbench) software is dedicated to the activities of the interface and control...

  9. Plant equipment services with laser metrology

    International Nuclear Information System (INIS)

    Hayes, J.H.; Kreitman, P.J.

    1995-01-01

    A new industrial metrology process is now being applied to support PWR Nuclear Plant Steam Generator Replacement Projects. The method uses laser tracking interferometry to perform as built surveys of existing and replacement plant equipment. This method provides precision data with a minimum of setup when compared to alternative methods available. In addition there is no post processing required to ascertain validity. The data is obtained quickly, processed in real time and displayed during the survey in the desired coordinate system. These capabilities make this method of industrial measure ideal for various data acquisition needs throughout the power industry, from internal/external equipment templating to area mapping. Laser tracking interferometry is an improvement on the present use of optical instruments and surveying technique. In order to describe the laser tracking interferometry measurement process, previous methods of templating and surveying are first reviewed

  10. Food Sanitation and Safety Self-assessment Instrument for Family Day-Care Homes.

    Science.gov (United States)

    1990

    This self-assessment instrument for family day care providers is designed to help caregivers provide safe food to children. The eight sections of the instrument, presented in checklist format, concern: (1) personal hygiene; (2) purchasing and inspecting of food; (3) food storage; (4) kitchen equipment; (5) food preparation; (6) infant food…

  11. The performance of a prototype device designed to evaluate general quality parameters of X-ray equipment

    International Nuclear Information System (INIS)

    Murata, C.H.; Fernandes, D.C.; Lavínia, N.C.; Caldas, L.V.E; Pires, S.R; Medeiros, R.B.

    2014-01-01

    The performance of radiological equipment can be assessed using non-invasive methods and portable instruments that can analyze an X-ray beam with just one exposure. These instruments use either an ionization chamber or a state solid detector (SSD) to evaluate X-ray beam parameters. In Brazil, no such instruments are currently being manufactured; consequently, these instruments come at a higher cost to users due to importation taxes. Additionally, quality control tests are time consuming and impose a high workload on the X-ray tubes when evaluating their performance parameters. The assessment of some parameters, such as the half-value layer (HVL), requires several exposures; however, this can be reduced by using a SSD that requires only a single exposure. One such SSD uses photodiodes designed for high X-ray sensitivity without the use of scintillation crystals. This sensitivity allows one electron-hole pair to be created per 3.63 eV of incident energy, resulting in extremely high and stable quantum efficiencies. These silicon photodiodes operate by absorbing photons and generating a flow of current that is proportional to the incident power. The aim of this study was to show the response of the solid sensor PIN RD100A detector in a multifunctional X-ray analysis system that is designed to evaluate the average peak voltage (kVp), exposure time, and HVL of radiological equipment. For this purpose, a prototype board that uses four SSDs was developed to measure kVp, exposure time, and HVL using a single exposure. The reproducibility and accuracy of the results were compared to that of different X-ray beam analysis instruments. The kVp reproducibility and accuracy results were 2% and 3%, respectively; the exposure time reproducibility and accuracy results were 2% and 1%, respectively; and the HVL accuracy was ±2%. The prototype's methodology was able to calculate these parameters with appropriate reproducibility and accuracy. Therefore, the prototype can be considered

  12. Annual report of the group for maintenance of electronic equipment; Godisnji izvestaj elektronske grupe

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, B [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    Maintenance and repair of the RA reactor control and safety systems were uniformly distributed during the whole year and were done according to the annual plan. A series of repairs of he electronic equipment as well as exchange of electronic components and elec tonic tubes. The testing and calibration of control and protection circuits were done regularly according to the needs and operation state of the reactor and according to the instructions. Inspections, repairs and reconstructions well as operating characteristics of individual elements as well as complete electronic circuits during 1965 have shown da the systems of control and safety are still in good condition. Somewhat higher number of failures due to aging of electronic tubes is a regular consequence of equipment and instrumentation aging. [Serbo-Croat] Remontni radovi na opremi sistema za upravljanje i sigurnost reaktora RA ravnomerno su rasporedjeni tokom cele godine i obavljaju se prema planu remonta. Izvrsen je citav niz popravki elektronske instrumentacije, kao i zamena komponenti i elektronskih cevi. Sve kontrole ispravnosti i kalibracije lanaca za upravljanje i zastitu reaktora redovno su vrsene prema potrebi i u vezi sa radnim stanjem reaktora prema uputstvu za ove operacije. Pregledi, remonti i popravke kao i radne karakteristike pojedinih elemenata kao i kompletnih instrumentalnih kontrolnih lanaca u toku 1965. godine pokazali su da su sistemi upravljanja i sigurnosne zastite jos u dobrom stanju. Nesto veci broj kvarova usled starenja elektronskih cevi je normalna posledica starenja opreme i instrumentacije.

  13. New instrumentation for the IPR-R1 reactor of CDTN

    International Nuclear Information System (INIS)

    Carvalho, P.V.R. de.

    1992-01-01

    The Nuclear Engineering Institute reactor instrumentation area has developed systems and equipment for reactor operation and safety. In such way, the new I and C for IEN Argonauta reactor and the nuclear instrumentation for IPEN critical facility were built. This paper describes our real work, the new I and C systems for IPR-R1, a Triga type reactor, located at CDTN (Belo Horizonte - MG). (author)

  14. Radiation protection instrumentation. Monitoring equipment. Atmospheric radioactive iodine in the environment

    International Nuclear Information System (INIS)

    1995-01-01

    This international standard applies to portable or installed equipment for the monitoring of radioactive iodine (such as I-131 or I-125) in air in the environment of nuclear installations during normal operation, during design basis events, and in emergency situations. The monitoring involves continuous sample trapping and, where adequate, automatic start of sampling. The document deals with radioactive iodine monitor design, testing procedures, and documentation. Appended tables refer to the reference and normal testing conditions, tests in normal testing conditions, tests during changes of the affecting quantities, and tests of changes in the air circuit. (P.A.)

  15. Radiographic evaluation of corrosion/erosion failures in pressure vessels and pipings in fertilizer industry

    International Nuclear Information System (INIS)

    Sinha, G.S.; Sahay, K.N.; Sundaram, K.V.; Banerji, K.C.

    1977-01-01

    The uses of radiography in combating the corrosion/erosion failures of pressure equipments used in the fertilizer industry are highlighted. Premature failures in fertilizer plants have proved to be very costly. One of the principal agencies responsible for such failures in process industry is corrosion/erosion. Radiography, when supplemented with other NDT-techniques, has been found to be ideal and highly useful method for on-stream inspection and evaluation of corrosion/erosion failures of pressure vessels and pipings. Three case-histories have been presented to illustrate the importance of radiography. (author)

  16. End face seals in high pressure water - learning from those failures

    International Nuclear Information System (INIS)

    Metcalfe, R.

    1976-08-01

    End face seals are complex devices which are used widely in shaft sealing of rotating equipment. In the nuclear industry, working at the limits of present sealing technlogy with a massive economic dependence on reliability, the importance of scrutinizing seal failures and thereby attempting to prevent premature failures from recurring was fully realized. This paper describes Canadian nuclear sealing experience. Failed seal data is presented; practical examples are categorized as to cause and type. (author)

  17. EURATOM, the year 2000 and its impact on the reporting system and instrumentation

    International Nuclear Information System (INIS)

    Chare, P.J.

    1999-01-01

    Presentation includes the Y2K potential problem areas, its impact on the reporting system and instrumentation as well as achievements done so far. The potential problem areas are: reporting system, headquarters system, installed instrumentation and stand alone instrumentation. A complete list of EURATOM equipment is listed. Specific problem areas concerned include data acquisition programmes. Reporting system is Y2K compatible, headquarters systems will be after upgrading, problems concerning instrumentation are identified and will be upgraded in 1999

  18. Life cycle management for equipments in nuclear plants based on reliability and actual conditions

    International Nuclear Information System (INIS)

    Dalin, Wang; Jingquan, Liu; Peng, Liu

    2010-01-01

    Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (authors)

  19. Results of the first tests of the SIDRA satellite-borne instrument breadboard model

    International Nuclear Information System (INIS)

    Dudnik, O.V.; Kurbatov, E.V.; Avilov, A.M.; Titov, K.G.; Prieto, M; Sanchez, S.; Spassky, A.V.; Sylwester, J.; Gburek, S.; Podgorski, P.

    2013-01-01

    In this work, the results of the calibration of the solid-state detectors and electronic channels of the SIDRA satellite borne energetic charged particle spectrometer-telescope breadboard model are presented. The block schemes and experimental equipment used to conduct the thermal vacuum and electromagnetic compatibility tests of the assemblies and modules of the compact satellite equipment are described. The results of the measured thermal conditions of operation of the signal analog and digital processing critical modules of the SIDRA instrument prototype are discussed. Finally, the levels of conducted interference generated by the instrument model in the primary vehicle-borne power circuits are presented.

  20. Effect of autoclave sterilization on the cyclic fatigue resistance of thermally treated Nickel-Titanium instruments.

    Science.gov (United States)

    Zhao, D; Shen, Y; Peng, B; Haapasalo, M

    2016-10-01

    To compare the cyclic fatigue resistance of HyFlex CM, Twisted Files (TF), K3XF, Race, and K3, and evaluate the effect of autoclave sterilization on the cyclic fatigue resistance of these instruments both before and after the files were cycled. Five types of NiTi instruments with similar size 30, .06 taper were selected: HyFlex CM, TF, K3XF, Race and K3. Files were tested in a simulated canal with a curvature of 60° and a radius of 3 mm. The number of cycles to failure of each instrument was determined to evaluate cyclic fatigue resistance. Each type of instruments was randomly divided into four experimental groups: group 1 (n = 20), unsterilized instruments; group 2 (n = 20), pre-sterilized instruments subjected to 10 cycles of autoclave sterilization; group 3 (n = 20), instruments tested were sterilized at 25%, 50% and 75% of the mean cycles to failure as determined in group 1, and then cycled to failure; group 4 (n = 20), instruments cycled in the same manner as group 3 but without sterilization. The fracture surfaces of instruments were examined by scanning electron microscopy (SEM). HyFlex CM, TF and K3XF had significantly higher cyclic fatigue resistance than Race and K3 in the unsterilized group 1 (P Autoclave sterilization significantly increased the MCF of HyFlex CM and K3XF (P Autoclaving extended the cyclic fatigue life of HyFlex CM and K3XF. © 2015 International Endodontic Journal. Published by John Wiley & Sons Ltd.

  1. Reactor instrumentation and control

    International Nuclear Information System (INIS)

    Wach, D.; Beraha, D.

    1980-01-01

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

  2. The study of Influencing Maintenance Factors on Failures of Two gypsum Kilns by Failure Modes and Effects Analysis (FMEA

    Directory of Open Access Journals (Sweden)

    Iraj Alimohammadi

    2014-06-01

    Full Text Available Developing technology and using equipment in Iranian industries caused that maintenance system would be more important to use. Using proper management techniques not only increase the performance of production system but also reduce the failures and costs. The aim of this study was to determine the quality of maintenance system and the effects of its components on failures of kilns in two gypsum production companies using Failure Modes and Effects Analysis (FMEA. Furthermore the costs of failures were studied. After the study of gypsum production steps in the factories, FMEA was conducted by the determination of analysis insight, information gathering, making list of kilns’ component and filling up the FMEA’s tables. The effects of failures on production, how to fail, failure rate, failure severity, and control measures were studied. The evaluation of maintenance system was studied by a check list including questions related to system components. The costs of failures were determined by refer in accounting notebooks and interview with the head of accounting department. It was found the total qualities of maintenance system in NO.1 was more than NO.2 but because of lower quality of NO.1’s kiln design, number of failures and their costs were more. In addition it was determined that repair costs in NO.2’s kiln were about one third of NO.1’s. The low severity failures caused the most costs in comparison to the moderate and low ones. The technical characteristics of kilns were appeared to be the most important factors in reducing of failures and costs.

  3. Quality of care and investment in property, plant, and equipment in hospitals.

    Science.gov (United States)

    Levitt, S W

    1994-02-01

    This study explores the relationship between quality of care and investment in property, plant, and equipment (PPE) in hospitals. Hospitals' investment in PPE was derived from audited financial statements for the fiscal years 1984-1989. Peer Review Organization (PRO) Generic Quality Screen (GQS) reviews and confirmed failures between April 1989 and September 1990 were obtained from the Massachusetts PRO. Weighted least squares regression models used PRO GQS confirmed failure rates as the dependent variable, and investment in PPE as the key explanatory variable. Investment in PPE was standardized, summed by the hospital over the six years, and divided by the hospital's average number of beds in that period. The number of PRO reviewed cases with one or more GQS confirmed failures was divided by the total number of cases reviewed to create confirmed failure rates. Investment in PPE in Massachusetts hospitals is correlated with GQS confirmed failure rates. A financial variable, investment in PPE, predicts certain dimensions of quality of care in hospitals.

  4. Pipework failures - a review of historical incidents

    International Nuclear Information System (INIS)

    Blything, K.W.; Parry, S.T.

    1988-01-01

    A description is presented of the gathering of historical pipework incident data and its analysis to determine the causes and underlying reasons for failure. The following terms of reference were agreed: (a) To review data on failures associated with pipework to establish the principal causes of failure. This should include not only rupture of the pipe itself, but also pipework induced failures, such as severe flange leaks and excessive strains resulting in failure of connected equipment. (b) To suggest an incident classification for pipework systems which will alert design, construction, maintenance, and operating personnel to the need for special care. (c) To advise non-piping specialists of the type of situation which could result in failure if not allowed for in the design, e.g. dynamic and transient conditions. (d) To recommend, possibly as the result of (a) above, areas where present procedures and codes of practice may require amplification. Brief descriptions are given of selected incidents where the consequences are considered to be serious in terms of damage and financial loss. For consequence analysis, the release rate is an important parameter and, where possible, the proportion of incidents in the failure mode categories, leaks, ''ruptures/severances'' are given. Although not one of the agreed objectives, the determination of failure rates was recognised as an important requirement in the risk assessment of pipework systems. The quality of data gathered however was found to be inadequate for any statistical analysis and no failure rate values are given in this report. (author)

  5. Dynamic tension testing equipment for paperboard and corrugated fiberboard

    Science.gov (United States)

    W. D. Godshall

    1965-01-01

    The objective of this work was to develop a method, the testing equipment, and the instrumentation with which dynamic stress-strain information may be obtained for paperboards and built-up corrugated fiberboards as used in corrugated fiberboard containers. Much information is available on the properties of these materials when subjected to static or low rates of...

  6. The function and failure of sensory predictions.

    Science.gov (United States)

    Bansal, Sonia; Ford, Judith M; Spering, Miriam

    2018-04-23

    Humans and other primates are equipped with neural mechanisms that allow them to automatically make predictions about future events, facilitating processing of expected sensations and actions. Prediction-driven control and monitoring of perceptual and motor acts are vital to normal cognitive functioning. This review provides an overview of corollary discharge mechanisms involved in predictions across sensory modalities and discusses consequences of predictive coding for cognition and behavior. Converging evidence now links impairments in corollary discharge mechanisms to neuropsychiatric symptoms such as hallucinations and delusions. We review studies supporting a prediction-failure hypothesis of perceptual and cognitive disturbances. We also outline neural correlates underlying prediction function and failure, highlighting similarities across the visual, auditory, and somatosensory systems. In linking basic psychophysical and psychophysiological evidence of visual, auditory, and somatosensory prediction failures to neuropsychiatric symptoms, our review furthers our understanding of disease mechanisms. © 2018 New York Academy of Sciences.

  7. The Preliminary Prototype of Medium Dose Rate Brachytherapy Equipment

    Directory of Open Access Journals (Sweden)

    A. Satmoko

    2013-08-01

    Full Text Available A preliminary prototype of a brachytherapy equipment has been constructed. The work started by developing conceptual design, followed by basic design and detailed design. In the conceptual design, design requirements are stated. In the basic design, technical specifications for main components are determined. In detailed design, general drawings are discussed. The prototype consists of three main systems: a mechanical system, an instrumentation system, and a safety system. The mechanical system assures the movement mechanism of the isotope source position beginning from the standby position until the applicators. It consists of three main modules: a position handling module, a container module, and a channel distribution module. The position handling module serves to move the isotope source position. As shielding, the second module is to store the source when the equipment is in standby position. The prototype provides 12 output channels. The channel selection is performed by the third module. The instrumentation system controls the movement of source position by handling motor operations. It consists of several modules. A microcontroller module serves as a control center whose task includes both controlling motors and communicating with computer. A motor module serves to handle motors. 10 sensors, including their signal conditionings, are introduced to read the environment conditions of the equipment. LEDs are used to display these conditions. In order to facilitate the operators’ duty, communication via RS232 is provided. The brachytherapy equipment can therefore be operated by using computer. Interface software is developed using C# language. To complete both mechanical and instrumentation systems performance, a safety system is developed to make sure that the safety for operator and patients from receiving excessive radiation. An interlock system is introduced to guard against abnormal conditions. In the worst case, a manual intervention

  8. Prediction of the time-dependent failure rate for normally operating components taking into account the operational history

    International Nuclear Information System (INIS)

    Vrbanic, I.; Simic, Z.; Sljivac, D.

    2008-01-01

    The prediction of the time-dependent failure rate has been studied, taking into account the operational history of a component used in applications such as system modeling in a probabilistic safety analysis in order to evaluate the impact of equipment aging and maintenance strategies on the risk measures considered. We have selected a time-dependent model for the failure rate which is based on the Weibull distribution and the principles of proportional age reduction by equipment overhauls. Estimation of the parameters that determine the failure rate is considered, including the definition of the operational history model and likelihood function for the Bayesian analysis of parameters for normally operating repairable components. The operational history is provided as a time axis with defined times of overhauls and failures. An example for demonstration is described with prediction of the future behavior for seven different operational histories. (orig.)

  9. Nuclear power plants. Electrical equipment of the safety system. Qualification

    International Nuclear Information System (INIS)

    2001-01-01

    This International Standard applies to electrical parts of safety systems employed at nuclear power plants, including components and equipment of any interface whose failure could affect unfavourably properties of the safety system. The standard also applies to non-electrical safety-related interfaces. Furthermore, the standard describes the generic process of qualification certification procedures and methods of qualification testing and related documentation. (P.A.)

  10. Validity and reliability of a home environment inventory for physical activity and media equipment

    Directory of Open Access Journals (Sweden)

    Pereira Mark A

    2008-04-01

    Full Text Available Abstract Background Little is known about how the home environmental supports physical activity and screen media usage. The purpose of this study was to develop and test the reliability and validity of a self-report instrument to comprehensively reflect the availability and accessibility of physical activity and screen media equipment in the home environment. Methods Ten families participated in the initial field testing to provide feedback for instrument development. Thirty one adult participants, each of whom had at least one child 10–17 years old, completed two Physical Activity and Media Inventory (PAMI instruments. The first PAMI was completed simultaneously, but independently, with a research assistant to assess validity. A second PAMI was completed by the participant one week later to assess reliability. Results The adult participants were mostly mothers/female guardians, mean age 38 ± 7.2 years, mostly Caucasian (52%, college educated (65%, living in single family homes (74%. Test-retest reliability was acceptable to strong for all summary variables (physical activity equipment, ICC = 0.76 to 0.99; media equipment, ICC = 0.72 to 0.96. For validation, reports from participants and research assistants were strongly correlated (physical activity, 0.67 – 0.98; media, 0.79 – 0.96. Compared to participants, research assistants reported a greater percentage of physical activity equipment as "in plain view and easy to get to" and a smaller percentage of items as "put away and difficult to get to". Conclusion Our results indicate strong evidence for the reliability and validity of the variables calculated from the PAMI. This self report inventory may be useful in assessing the availability of physical activity and screen media equipment in the home environment and could be used in conjunction with other home assessment tools (food availability, parenting styles and feeding practices to identify obesogenic home environments.

  11. A comparison of nickel-titanium rotary instruments manufactured using different methods and cross-sectional areas: ability to resist cyclic fatigue.

    Science.gov (United States)

    Oh, So-Ram; Chang, Seok-Woo; Lee, Yoon; Gu, Yu; Son, Won-Jun; Lee, Woocheol; Baek, Seung-Ho; Bae, Kwang-Shik; Choi, Gi-Woon; Lim, Sang-Min; Kum, Kee-Yeon

    2010-04-01

    This study examined the effect of the manufacturing methods (ground, electropolished, and twisted) and the cross-sectional area (CSA) of nickel-titanium (NiTi) rotary instruments on their cyclic fatigue resistance. A total of 80 NiTi rotary instruments (ISO 25/.06 taper) from 4 brands (K3, ProFile, RaCe, and TF) were rotated in a simulated root canal with pecking motion until fracture. The number of cycles to failure (NCF) was calculated. The CSA at 3 mm from the tip of new instruments of each brand was calculated. The correlation between the CSA and NCF was evaluated. All fractured surfaces were analyzed using a scanning electron microscope to determine the fracture mode. The TF instruments were the most resistant to fatigue failure. The resistance to cyclic failure increased with decreasing CSA. All fractured surfaces showed the coexistence of ductile and brittle properties. The CSA had a significant effect on the fatigue resistance of NiTi rotary instruments. Copyright 2010 Mosby, Inc. All rights reserved.

  12. The new generation of detection and identification equipment

    International Nuclear Information System (INIS)

    Schultz, F.; Guerin, M.; Fort, Ph.

    2009-01-01

    The authors address the highly sensitive detection issue with real time identification of the risk nature, a problem which occurs every time a source is only fleetingly present (a pedestrian, a vehicle or an object on a conveyor belt passing by). They briefly present a range of instruments specially designed for this purpose, the SPIR-Ident instruments. These equipment use one or several large sensors, digital multichannel analyzers (one per sensor) and neutron and gamma measurements. Spectra are continuously processed, stabilized, linearized and normalized, and finally analyzed by an algorithm. The authors evoke the performance characterization and a return on experience after a 6 month-use for the control of passengers and luggage in airport

  13. Application of a truncated normal failure distribution in reliability testing

    Science.gov (United States)

    Groves, C., Jr.

    1968-01-01

    Statistical truncated normal distribution function is applied as a time-to-failure distribution function in equipment reliability estimations. Age-dependent characteristics of the truncated function provide a basis for formulating a system of high-reliability testing that effectively merges statistical, engineering, and cost considerations.

  14. Synergistic behaviour of nuclear radiation, temperature-humidity extremes and LOCA situation on safety and safety-related equipment in Indian nuclear power plants

    International Nuclear Information System (INIS)

    Kulkarni, R.D.; Bora, J.S.; Prakash, Ravi; Agarwal, Vivek; Sundersingh, V.P.

    2002-01-01

    Full text: The general philosophy for the instrumentation in nuclear power plants is based on the use of equipment/instruments which are capable of continuous satisfactory operation over a long period of time with minimum attention. Long term reliability under varying service conditions is of prime importance. The reliability of nuclear power plant depends on the reliability of safety and safety-related electronic instruments/ equipment used for performing the crucial tasks. The electrical and electronic systems/ circuits/ components of the equipment used in reactor safety systems (e.g. reactor protection system, emergency core cooling system, etc.) and reactor safety-related systems (e.g. reactor containment isolation and cooling system, reactor shutdown system, etc.) are responsible for safe and reliable operation of a nuclear power plant. The performance of reactor safety and safety-related equipment/instruments viz. pressure and differential pressure transmitter, amplifier for ion chamber, etc. has been evaluated under synergistic atmosphere including LOCA to find out the critical link in the circuits and subsequent modifications are suggested. The mathematical representation of the generated database has been done to estimate the life span of the instruments and accordingly the guidelines has been prepared for the operational staff to avoid the forced outage of the plant. All the details are included and mathematical models are presented to predict the future performances

  15. Discussion forum on electron beam instruments AERE Harwell

    International Nuclear Information System (INIS)

    Bainbridge, J.E.

    1980-08-01

    The purpose of this catalogue is to provide a source of information on the equipment available at AERE Harwell, to the nuclear and non-nuclear scientist. The original aim, that is, is to provide data on electron/proton beam instruments has been revised to include optical devices and ancillary preparatory equipment. The intention is to enable prospective users to have a contact who can provide further detailed information, although it must be recognised that work on certain projects completely fills the time available. This publication has been updated, first catalogue published in January 1975, to August 1980 and it is the intention that it should form part of a similar publication which incorporates details of similar equipment available throughout the UKAEA. (author)

  16. Energy paradox and political intervention: A stochastic model for the case of electrical equipments

    International Nuclear Information System (INIS)

    Jridi, Omar; Jridi, Maher; Barguaoui, Saoussen Aguir; Nouri, Fethi Zouheir

    2016-01-01

    This paper develops a model that explains the delay of decisions to adopt profitable energy-saving investments. This problem is known as the energy paradox. The model rationalizes the profitability requirements raised by the irreversibility, the uncertainty and the decrease of costs as a result of learning by doing. In this context, the wait gives investors more visibility and more lower investment costs, which gives them an option value. The representative agent has an interest to postpone its energy saving decision until future benefits increase and equalize its required option value. Formally, we internalize these explanatory factors in a stochastic model where the updated energy saving benefits follows a geometric Brownian motion. To affirm the capacity of the model, we generate simulation results for two equipments for electrical uses. Beyond that, we extend the model to simulate the effects of energy policy instruments to promote adoption of such equipments. Simulations prove that the taxation of energy prices is likely to be more effective than the subsidy for energy-saving equipments. It is also found that the combination of these instruments amplifies the adoption of energy-saving equipments and generates very favorable economic and environmental externalities. - Highlights: •We develop a stochastic model that explains and solves the energy paradox. •Agent postpones the energy-saving investments to maximize its option value. •Option value is fueled by uncertainty, irreversibility and learning by doing. •Subsidies of these investments are less effective than energy taxation. •Mixed instrument policy solves this paradox and generates favorable externalities.

  17. Effects of Common Cause Failure on Electrical Systems

    International Nuclear Information System (INIS)

    Pepper, Kevin

    2015-01-01

    The essential electrical systems of reactor designs have developed progressively with an increased focus on the use of redundant, segregated and independent safety system equipment 'trains'. In this arrangement, essential safety functions associated with safe shutdown and cooling of the reactor are replicated on near identical electrical systems with each of the trains of safety system equipment supported by a fully rated standby generator. Development in designs has seen the number of trains increased to enable maintenance to be undertaken with reactors at power, improving the economics of the units whilst maintaining nuclear safety. This paper provides a background to common cause failure and provides examples where supporting guidance and international experience is available. It also highlights the regulatory guidance available to UK licensees. Recent examples of common cause failures on plant in the UK are presented together with an issue identified during the recent Generic Design Assessment review of new reactor designs within the UK. It was identified that one design was claiming a very low probability of failure associated with the loss of a single break and no-break voltage level, orders of magnitude below the target figure within ONR's Safety Assessment Principles. On closer scrutiny it was established that a significant safety function provided from identical low voltage switchboards would be lost in the event of a common cause failure affecting these boards. The paper will explain the action that has been taken by the requesting party to improve the resilience of the design and how this impacts on the ONR reliability targets for reactor designs within the UK. (authors)

  18. Radiation protection instrumentation. Monitoring equipment. Radioactive aerosols in the environment

    International Nuclear Information System (INIS)

    1996-01-01

    This international standard applies to portable or installed equipment for continuous monitoring of radioactive aerosols in the environment in normal and emergency conditions. Monitoring involves continuous sampling and, where desirable, automatic start of sampling. The document applies particularly to the following assignments: (i) determination of the volume activity of radionuclides in the form of aerosols, either per time unit, along with its time changes, or in the integral form over a longer time period such as 24 h, and measurement of the volume sampled; (ii) triggering a warning alarm signal if the preset volume activity or time integral of the volume activity of aerosols has been exceeded. The document deals with radioactive aerosol monitor design, testing procedures, and documentation. Appended tables refer to the reference and normal testing conditions, tests in normal testing conditions, tests during changes of the affecting quantities, and tests of the air circuit. (P.A.)

  19. Equipment for functional testing of the ALADIN TXA pulsed laser head

    Science.gov (United States)

    Emanuele, Stucchi; Franco, Trespidi; Enzo, Nava

    2017-11-01

    It is described a measurement instrument, used as Optical Ground Support Equipment, capable of performing the characterization of a pulsed laser beam. The instrument was developed for the functional testing of the EQM and FMs of the ALADIN laser transmitter (TXA). The performed measurements are: beam shaping, M2 measurement, beam angular stability, energy and wavelength measurements, pulse duration, polarization, pulse shape and spectral characterization, optical frequency stability measurement. The measurement system can work in automatic mode performing several measurements and providing automatic report generation.

  20. MC and A instrumentation catalog

    Energy Technology Data Exchange (ETDEWEB)

    Neymotin, L. [ed.] [Brookhaven National Lab., Upton, NY (United States); Sviridova, V. [ed.] [All-Russian Research Inst. of Automatics, Moscow (Russian Federation)

    1998-06-01

    In 1981 and 1985, two editions of a catalog of non-destructive nuclear measurement instrumentation, and material control and surveillance equipment, were published by Brookhaven National Laboratory (BNL). The last edition of the catalog included one hundred and twenty-five entries covering a wide range of devices developed in the US and abroad. More than ten years have elapsed since the publication of the more recent Catalog. Devices described in it have undergone significant modifications, and new devices have been developed. Therefore, in order to assist specialists in the field of Material Control and Accounting (MC and A), a new catalog has been created. Work on this instrumentation catalog started in 1997 as a cooperative effort of Brookhaven National Laboratory (BNL), operated by Brookhaven Science Associates under contract to the US Department of Energy, and the All-Russian Research Institute of Automatics (VNIIA), subordinate institute of the Atomic Energy Ministry of the Russian Federation, within the collaborative US-Russia Material Protection, Control, and Accounting (MPC and A) Program. Most of the equipment included in the Catalog are non-destructive assay (NDA) measurement devices employed for purposes of accounting, confirmation, and verification of nuclear materials. Other devices also included in the Catalog are employed in the detection and deterrence of unauthorized access to or removal of nuclear materials (material control: containment and surveillance). Equipment found in the Catalog comprises either: (1) complete devices or systems that can be used for MC and A applications; or (2) parts or components of complete systems, such as multi-channel analyzers, detectors, neutron generators, and software. All devices are categorized by their status of development--from prototype to serial production.

  1. MC and A instrumentation catalog

    International Nuclear Information System (INIS)

    Neymotin, L.; Sviridova, V.

    1998-01-01

    In 1981 and 1985, two editions of a catalog of non-destructive nuclear measurement instrumentation, and material control and surveillance equipment, were published by Brookhaven National Laboratory (BNL). The last edition of the catalog included one hundred and twenty-five entries covering a wide range of devices developed in the US and abroad. More than ten years have elapsed since the publication of the more recent Catalog. Devices described in it have undergone significant modifications, and new devices have been developed. Therefore, in order to assist specialists in the field of Material Control and Accounting (MC and A), a new catalog has been created. Work on this instrumentation catalog started in 1997 as a cooperative effort of Brookhaven National Laboratory (BNL), operated by Brookhaven Science Associates under contract to the US Department of Energy, and the All-Russian Research Institute of Automatics (VNIIA), subordinate institute of the Atomic Energy Ministry of the Russian Federation, within the collaborative US-Russia Material Protection, Control, and Accounting (MPC and A) Program. Most of the equipment included in the Catalog are non-destructive assay (NDA) measurement devices employed for purposes of accounting, confirmation, and verification of nuclear materials. Other devices also included in the Catalog are employed in the detection and deterrence of unauthorized access to or removal of nuclear materials (material control: containment and surveillance). Equipment found in the Catalog comprises either: (1) complete devices or systems that can be used for MC and A applications; or (2) parts or components of complete systems, such as multi-channel analyzers, detectors, neutron generators, and software. All devices are categorized by their status of development--from prototype to serial production

  2. Standard practice for evaluating performance characteristics of ultrasonic Pulse-Echo testing instruments and systems without the use of electronic measurement instruments

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2011-01-01

    1.1 This practice describes procedures for evaluating the following performance characteristics of ultrasonic pulse-echo examination instruments and systems: Horizontal Limit and Linearity; Vertical Limit and Linearity; Resolution - Entry Surface and Far Surface; Sensitivity and Noise; Accuracy of Calibrated Gain Controls. Evaluation of these characteristics is intended to be used for comparing instruments and systems or, by periodic repetition, for detecting long-term changes in the characteristics of a given instrument or system that may be indicative of impending failure, and which, if beyond certain limits, will require corrective maintenance. Instrument characteristics measured in accordance with this practice are expressed in terms that relate to their potential usefulness for ultrasonic testing. Instrument characteristics expressed in purely electronic terms may be measured as described in E1324. 1.2 Ultrasonic examination systems using pulsed-wave trains and A-scan presentation (rf or video) may be ev...

  3. Modification of evaluation response spectrum by ductility of equipment anchorage

    International Nuclear Information System (INIS)

    Choi, I. G.; Jun, Y. S.; Su, J. M.

    2003-01-01

    The failure mode of welded anchorage is assumed as brittle in the seismic capacity evaluation of nuclear power plant equipments. But the welded anchorage has some ductile capacity. This limited displacement capacity can cause the reduction of the effective frequency of high frequency equipments and the increase of the inelastic energy absorption capacity due to the nonlinear behavior. In this study, the uniform hazard spectrum for Korean nuclear power plant site was modified using the response spectrum reduction factor developed by EPRI. The spectral acceleration for various damping ratio was determined by the theoretical method based on the random vibration theory. In conclusion, the high frequency components of evaluation response spectra were greatly reduced due to the consideration of welded anchorage ductility. This reduced response spectra can be used for the development of in-structure response spectra used in the seismic capacity evaluation of high frequency equipments

  4. Questionnaire report of safety control on instrument in nuclear medicine laboratory

    International Nuclear Information System (INIS)

    1987-01-01

    A questionaire survey concerning the safety of equipment and facilities used in nuclear medicine laboratories was made in order to clarify the incidence of accidents during nuclear medicine testing. The questionaire consists of two parts. One part contains questions regarding the testing personnel, facilities, equipment and maintenance and management of the equipment. The other part deals with accidents that had occurred within the areas under management, potential risks that may cause accidents, measures to improve safety management, troubles with and failure of equipment, and requests and opinions directed to equipment manufactures. It is concluded from results of the survey that to raise the safety of equipment, so-called man-machine interfaces should be improved by increasing the durability of equipment and performance of the personnel operating the equipment while reducing the physical and mental effects on the persons subjected to testing. Systematic educational measures, including lecture meetings and training courses, are required to raise the consciousness of personnel. Such education and training should cover safety handling techniques, including those for checking of equipment and for instructing and helping the persons under testing. (Nogami, K.)

  5. SuperAGILE onboard electronics and ground test instrumentation

    International Nuclear Information System (INIS)

    Pacciani, Luigi; Morelli, Ennio; Rubini, Alda; Mastropietro, Marcello; Porrovecchio, Geiland; Costa, Enrico; Del Monte, Ettore; Donnarumma, Immacolata; Evangelista, Yuri; Feroci, Marco; Lazzarotto, Francesco; Rapisarda, Massimo; Soffitta, Paolo

    2007-01-01

    In this paper we describe the electronics of the SuperAGILE X-ray imager on-board AGILE satellite and the instrumentation developed to test and improve the Front-End and digital electronics of the flight model of the imager. Although the working principle of the instrument is very well established, and the conceptual scheme simple, the budget and mechanical constraints of the AGILE small mission made necessary the introduction of new elements in SuperAGILE, regarding both the mechanics and the electronics. In fact the instrument is contained in a ∼44x44x16cm 3 volume, but the required performance is quite ambitious, leading us to equip a sensitive area of ∼1350cm 2 with 6144 Silicon μstrips detectors with a pitch of 121μm and a total length of ∼18.2cm. The result is a very light and power-cheap imager with a good sensitivity (∼15mCrab in 1 day in 15-45keV), high angular resolution (6arcmin) and gross spectral resolution. The test-equipment is versatile, and can be easily modified to test FEE based on self-triggered, data-driven and sparse-readout ASICs such as XA family chips

  6. Mapping of the radiation field of a mammography equipment using molybdenum and rhodium filters

    International Nuclear Information System (INIS)

    Barreira, Jacqueline S.; Campos, Daniela; Vivolo, Vitor

    2014-01-01

    The use of X rays for diagnostic radiology is very common and important to Medicine, including mammographic diagnosis focusing decreasing of the doses applied to the patients and preserving high quality of the diagnostic image. A quality control program of the irradiation systems it is very necessary. The Instruments Calibration Laboratory (LCI) of IPEN perform calibration in dosemeters used in radiation dosimetry (in diagnostic radiology) for many years. The objective of that paper is determining the point of greatest intensity of the beam issued by the mammography equipment. Exposures were made with filters Rhodium and Molybdenum. That mapping is important before applied a routine quality control program of the mammography equipment and the calibration of instruments in the diagnosis. (author)

  7. Pulsed neutron source and instruments at neutron facility

    Energy Technology Data Exchange (ETDEWEB)

    Teshigawara, Makoto; Aizawa, Kazuya; Suzuki, Jun-ichi; Morii, Yukio; Watanabe, Noboru [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-11-01

    We report the results of design studies on the optimal target shape, target - moderator coupling, optimal layout of moderators, and neutron instruments for a next generation pulsed spallation source in JAERI. The source utilizes a projected high-intensity proton accelerator (linac: 1.5 GeV, {approx}8 MW in total beam power, compressor ring: {approx}5 MW). We discuss the target neutronics, moderators and their layout. The sources is designed to have at least 30 beam lines equipped with more than 40 instruments, which are selected tentatively to the present knowledge. (author)

  8. Upgrade of Instrumentation for Purdue Reactor PUR-1

    International Nuclear Information System (INIS)

    Revankar, S.T.; Merritt, E.; Bean, R.

    2000-01-01

    The major objective of this program was to upgrade and replace instruments and equipment that significantly improve the performance, control and operational capability of the Purdue University nuclear reactor (PUR-1). Under this major objective two projects on instrument upgrade were implemented. The first one was to convert the vacuum tube control and safety amplifiers (CSA) to solid state electronics, and the other was to upgrade the electrical and electronic shielding. This report is the annual report and gives the efforts and progress achieved on these two projects from July 1999 to June 2000

  9. Development on experimental VHTR instrumentation

    International Nuclear Information System (INIS)

    Wakayama, N.; Ara, K.; Terada, H.; Yamagishi, H.; Tomoda, T.

    1982-06-01

    This paper describes developmental works on the instrumentation of the Experimental VHTR. In the area of the nuclear instrumentation for the reactor control, high temperature fission counter-chambers have been developed. These withstood the accelerated irradiation life tests at 600 deg. C, the long term in-reactor operating test at 600 deg. C and the 800 deg. C-operating tests for several hundred hours in a simulated accident condition. Platinum-Molybdenum alloy thermocouples have been studied as a neutron-irradiation-resistant high-temperature thermocouple for the in-core temperature distribution monitoring of the VHTR in the temperature range between 1000 deg. C and 1350 deg. C. The instability problems of the Pt-5% Mo/Pt-0.1% Mo thermocouple seem to be overcome by introducing a double sheath structure and adopting a better material to the inner sheath. A local failure and abnormality monitoring method for the HTR fuel is also studied using a gas-sweeping irradiation rig for the CPF compacts. This study aims mainly at the development of a method to compensate for the dependency of the FP-release rate on the fuel temperature, the neutron flux density, the burn-up and others, in order to increase the detection sensitivity of fuel failures. (author)

  10. General presentation of the instrumentation area of IPEN (Instituto de Pesquisas Energeticas e Nucleares)

    International Nuclear Information System (INIS)

    Anon.

    The area of electronic instrumentation of IPEN (Instituto de Pesquisas Energeticas e Nucleares), is presented. The activities of AIE (Electronic Instrumentation Area) is constituted basically in a technical attendance to the IPEN research centers and sometimes to industry that needs maintenance in nuclear equipments. (E.G.) [pt

  11. Automation of a thermal expansion instrument

    Energy Technology Data Exchange (ETDEWEB)

    Holland, L.L.

    1979-03-01

    Automation of a thermal expansion instrument using a minicomputer system and with analog-to-digital converter inputs and flip-flop relay outputs is described. The necessary hardware link and the software were developed to allow equipment control, data acquisition, data reduction, and report generation by the minicomputer. The design of the automation allows non-programmers to run the experiment, reduce the data, and generate the report.

  12. Distributions of component failure rates, estimated from LER data

    International Nuclear Information System (INIS)

    Atwood, C.L.

    1985-01-01

    Past analyses of Licensee Event Report (LER) data have noted that component failure rates vary from plant to plant, and have estimated the distributions by two-parameter γ distributions. In this study, a more complicated distributional form is considered, a mixture of γs. This could arise if the plants' failure rates cluster into distinct groups. The method was applied to selected published LER data for diesel generators, pumps, valves, and instrumentation and control assemblies. The improved fits from using a mixture rather than a single γ distribution were minimal, and not statistically significant. There seem to be two possibilities: either explanatory variables affect the failure rates only in a gradual way, not a qualitative way; or, for estimating individual component failure rates, the published LER data have been analyzed to the limit of resolution

  13. Economical and organizational aspects of radiopulmonology instrumentation

    International Nuclear Information System (INIS)

    Chikirdin, Eh.G.; Astrakhantsev, F.A.

    1986-01-01

    It is shown that the introduction of X-ray endoscopic rooms (radiology treatment rooms) equipped with appropriate installations into pulmonologic departments provides more valid diagnosis of carcinoma of the lungs, the cost of examinations being increased only by 15.7%. The latter can be compensated for with improved instrumentation of both preventive and general X-ray rooms

  14. Nuclear instrument maintenance and technical training in Nuclear Energy Unit

    International Nuclear Information System (INIS)

    Mohamad Nasir Abdul Wahid

    1987-01-01

    Instrument maintenance service is a necessity in a Nuclear Research Institute, such as the Nuclear Energy Unit (NEU) to ensure the smooth running of our research activities. However, realising that maintenance back-up service for either nuclear or other scientific equipment is a major problem in developing countries such as Malaysia, NEU has set up an Instrumentation and Control Department to assist in rectifying the maintenance problem. Beside supporting in house activities in NEU, the Instrumentation and Control Department (I and C) is also geared into providing services to other organisations in Malaysia. This paper will briefly outline the activities of NEU in nuclear instrument maintenance as well as in technical training. (author)

  15. Instrumentation and measurement method for the ATLAS test facility

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Byong Jo; Chu, In Chul; Eu, Dong Jin; Kang, Kyong Ho; Kim, Yeon Sik; Song, Chul Hwa; Baek, Won Pil

    2007-03-15

    An integral effect test loop for pressurized water reactors (PWRs), the ATLAS is constructed by thermal-hydraulic safety research division in KAERI. The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400 which is a Korean evolution type nuclear reactors. A total 1300 instrumentations is equipped in the ATLAS test facility. In this report, the instrumentation of ATLAS test facility and related measurement methods were introduced.

  16. Failure Rate Prediction of Active Component Using PM Basis Database

    International Nuclear Information System (INIS)

    Kim, J. S.; Kim, H. W.; Park, J. S.; Jung, S. G.

    2011-01-01

    The safety security and efficient management of NPPs (Nuclear Power Plants) have been increased after the accident of TEPCO's Fukushima nuclear power stations. The needs for the safety and efficiency are becoming more important because about 90 percent of the NPPs all over the world are more than 20 operation years old. The preventive maintenance criteria need to be flexible, considering long-term development of the equipment performance and preventive maintenance. The PMBD (Preventive Maintenance Basis Database) program was widely used for optimization of the preventive maintenance criteria. PMBD program contains all kinds of failure mechanisms for each equipment that may occur in the power plant based on RCM(Reliability-Centered Maintenance) and numerically calculate the variation of reliability and failure rate based on PM interval changes. In this study, propriety evaluation of preventive maintenance task, cycle, technical basis for cost effective preventive maintenance strategy and an appropriate evaluation were suggested by the case application of PMBD for major components in the NPPs

  17. A novel approach to determine the effect of irrigation on temperature and failure of Ni-Ti endodontic rotary files

    Science.gov (United States)

    Mousavi, Sayed Ali; Kargar-Dehnavi, Vida; Mousavi, Sayed Amir

    2012-01-01

    Background: Nickel-titanium (Ni-Ti) rotary instrument files are important devices in Endodontics in root canal preparation. Ni-Ti file breakage is a critical and problematic issue and irrigation techniques were applied to decrease risk of file failure root. The aim of the present study was to compare the temperature gradient change of different irrigation solutions with Ni-Ti rotary instrument system during root canal preparation and also to define their effects on the file failure. Materials and Methods: A novel computerized instrumentation was utilized and thirty standard (ProFile #25/.04) files were divided into three groups and subjected to a filing in the root canal test. Changes in temperature on teeth under constant instrumental conditions with custom-designed computerized experimental apparatus were measured by using a temperature sensor bonded to the apical hole. A rotary instrument for canal preparation in three series of solution was used and the changes in temperature after each solution were compared. Finally, the file failure results were mentored according to each step of test. Comparisons were performed between group status clinically by using ANOVA (t) test, once the sample showed up normal and differences of Pinstruments, which were immersed in 5% NaOCl, when compared with the water group (Pinstruments immersed in water, when compared with the no solution group (Pinstruments. Conclusion: By immersing the file in 5% NaOCl, the temperature gradient decreased and instrument failure was reduced. PMID:23087732

  18. Electrical failure during cardiopulmonary bypass: an evaluation of incidence, causes, management and guidelines for preventative measures.

    LENUS (Irish Health Repository)

    Hargrove, M

    2012-02-03

    The incidence of electrical failure during cardiopulmonary bypass (CPB) has been reported to occur in approximately 1 per 1000 cases. While the resultant morbidity and mortality is low, electrical failure is a life-threatening scenario. We report three major electrical failures during CPB in a patient population of 3500 over a 15-year period. These cases involved mains failure and generator shut down, mains failure and generator power surge, and failure of the uninterruptable power supply (UPS), which caused protected sockets to shut down. Protocols for preventative maintenance, necessary equipment, battery backup and guidelines for the successful management of such accidents during CPB are discussed.

  19. Reliability technology principles and practice of failure prevention in electronic systems

    CERN Document Server

    Pascoe, Norman

    2011-01-01

    A unique book that describes the practical processes necessary to achieve failure free equipment performance, for quality and reliability engineers, design, manufacturing process and environmental test engineers. This book studies the essential requirements for successful product life cycle management. It identifies key contributors to failure in product life cycle management and particular emphasis is placed upon the importance of thorough Manufacturing Process Capability reviews for both in-house and outsourced manufacturing strategies. The readers? attention is also drawn to the ma

  20. Application range affected by software failures in safety relevant instrumentation and control systems of nuclear power plants; Auswirkungsbereiche von Softwarefehlern in sicherheitstechnisch wichtigen Einrichtungen von Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Jopen, Manuela; Mbonjo, Herve; Sommer, Dagmar; Ulrich, Birte

    2017-03-15

    This report presents results that have been developed within a BMUB-funded research project (Promotion Code 3614R01304). The overall objective of this project was to broaden the knowledge base of GRS regarding software failures and their impact in software-based instrumentation and control (I and C) systems. To this end, relevant definitions and terms in standards and publications (DIN, IEEE standards, IAEA standards, NUREG publications) as well as in the German safety requirements for nuclear power plants were analyzed first. In particular, it was found that the term ''software fault'' is defined differently and partly contradictory in the considered literature sources. For this reason, a definition of software fault was developed on the basis of the software life cycle of software-based I and C systems within the framework of this project, which takes into account the various aspects relevant to software faults and their related effects. It turns out that software failures result from latent faults in a software-based control system, which can lead to a non-compliant behavior of a software-based I and C system. Hereby a distinction should be made between programming faults and specification faults. In a further step, operational experience with software failures in software-based I and C systems in nuclear facilities and in nonnuclear sector was investigated. The identified events were analyzed with regard to their cause and impacts and the analysis results were summarized. Based on the developed definition of software failure and on the COMPSIS-classification scheme for events related to software based I and C systems, the COCS-classification scheme was developed to classify events from operating experience with software failures, in which the events are classified according to the criteria ''cause'', ''affected system'', ''impact'' and ''CCF potential''. This

  1. Stress corrosion cracking of equipment materials in domestic pressurized water reactors and the relevant safety management

    International Nuclear Information System (INIS)

    Sun Haitao

    2015-01-01

    International and domestic research and project state about stress corrosion cracking of nuclear equipments and materials (including austenitic stainless steel and nickel based alloys) in pressurized water reactor are discussed, and suggestions on how to prevent, mitigate ana deal with the stress corrosion cracking issues in domestic reactors are given in this paper based on real case analysis and study ondomestic nuclear equipment and material stress corrosion cracking failure. (author)

  2. Solar Energy Research Center Instrumentation Facility

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Thomas, J.; Papanikolas, John, P.

    2011-11-11

    SOLAR ENERGY RESEARCH CENTER INSTRUMENTATION FACILITY The mission of the Solar Energy Research Center (UNC SERC) at the University of North Carolina at Chapel Hill (UNC-CH) is to establish a world leading effort in solar fuels research and to develop the materials and methods needed to fabricate the next generation of solar energy devices. We are addressing the fundamental issues that will drive new strategies for solar energy conversion and the engineering challenges that must be met in order to convert discoveries made in the laboratory into commercially available devices. The development of a photoelectrosynthesis cell (PEC) for solar fuels production faces daunting requirements: (1) Absorb a large fraction of sunlight; (2) Carry out artificial photosynthesis which involves multiple complex reaction steps; (3) Avoid competitive and deleterious side and reverse reactions; (4) Perform 13 million catalytic cycles per year with minimal degradation; (5) Use non-toxic materials; (6) Cost-effectiveness. PEC efficiency is directly determined by the kinetics of each reaction step. The UNC SERC is addressing this challenge by taking a broad interdisciplinary approach in a highly collaborative setting, drawing on expertise across a broad range of disciplines in chemistry, physics and materials science. By taking a systematic approach toward a fundamental understanding of the mechanism of each step, we will be able to gain unique insight and optimize PEC design. Access to cutting-edge spectroscopic tools is critical to this research effort. We have built professionally-staffed facilities equipped with the state-of the-art instrumentation funded by this award. The combination of staff, facilities, and instrumentation specifically tailored for solar fuels research establishes the UNC Solar Energy Research Center Instrumentation Facility as a unique, world-class capability. This congressionally directed project funded the development of two user facilities: TASK 1: SOLAR

  3. Program plan for environmental qualification of mechanical and dynamic (including seismic) qualification of mechanical and electrical equipment program (EDQP)

    International Nuclear Information System (INIS)

    Weidenhamer, G.H.

    1986-06-01

    The equipment qualification program described in this plan is intended to provide the technical basis for resolving uncertainties in existing equipment qualification standards. In addition, research results are contributing to the resolution of safety issues GI-23, GI-87, USI-A44, titled, ''Reactor Coolant Pump Seal Failure,'' ''Failure of HPCI Steam Line Without Isolation,'' and ''Station Blackout,'' respectively. Also, research effort is being directed at providing information on the behavior of containment isolation valves under severe accident environments. Although the results of the latter research will not contribute to resolving uncertainties in qualification standards, it has proven cost effective to obtain this information under this program

  4. Role of scanning electron microscope )SEM) in metal failure analysis

    International Nuclear Information System (INIS)

    Shaiful Rizam Shamsudin; Hafizal Yazid; Mohd Harun; Siti Selina Abd Hamid; Nadira Kamarudin; Zaiton Selamat; Mohd Shariff Sattar; Muhamad Jalil

    2005-01-01

    Scanning electron microscope (SEM) is a scientific instrument that uses a beam of highly energetic electrons to examine the surface and phase distribution of specimens on a micro scale through the live imaging of secondary electrons (SE) and back-scattered electrons (BSE) images. One of the main activities of SEM Laboratory at MINT is for failure analysis on metal part and components. The capability of SEM is excellent for determining the root cause of metal failures such as ductility or brittleness, stress corrosion, fatigue and other types of failures. Most of our customers that request for failure analysis are from local petrochemical plants, manufacturers of automotive components, pipeline maintenance personnel and engineers who involved in the development of metal parts and component. This paper intends to discuss some of the technical concepts in failure analysis associated with SEM. (Author)

  5. Instruments of Transformative Governance

    DEFF Research Database (Denmark)

    Borrás, Susana

    production and distribution channels. PDPs aim at overcoming current market and government failures by pooling resources in the attempt to solve this global social challenge. Thus, PDPs are a case of instruments of transformative research and innovation, operating in a transnational governance context....... They exhibit three novelties: they address strategic long-term problems in a holistic manner, set substantive output-oriented goals, and are implemented through new organizational structures. After characterizing the different types of current PDPs and the context in which they emerged, the paper examines...

  6. Two viewpoints for software failures and their relation in probabilistic safety assessment of digital instrumentation and control systems

    International Nuclear Information System (INIS)

    Kim, Man Cheol

    2015-01-01

    As the use of digital systems in nuclear power plants increases, the reliability of the software becomes one of the important issues in probabilistic safety assessment. In this paper, two viewpoints for a software failure during the operation of a digital system or a statistical software test are identified, and the relation between them is provided. In conventional software reliability analysis, a failure is mainly viewed with respect to the system operation. A new viewpoint with respect to the system input is suggested. The failure probability density functions for the two viewpoints are defined, and the relation between the two failure probability density functions is derived. Each failure probability density function can be derived from the other failure probability density function by applying the derived relation between the two failure probability density functions. The usefulness of the derived relation is demonstrated by applying it to the failure data obtained from the software testing of a real system. The two viewpoints and their relation, as identified in this paper, are expected to help us extend our understanding of the reliability of safety-critical software. (author)

  7. Development of pre-startup equipment for light water reactors

    International Nuclear Information System (INIS)

    Ram, Rajit; Borkar, S.P.; Dixit, M.Y.; Das, Debashis; Patil, R.K.

    2010-01-01

    Light water reactor (LWR) core typically has high excess reactivity as compared to Pressurized Heavy Water Reactor (PHWR). Unlike PHWR, where online refueling is done, LWR is operated for a long period to achieve maximum fuel burn-up before refueling. Since the reactivity is always reducing with burn-up of the core, the positions of control rods at criticality are always changing in a single direction, i.e. away from the core. Therefore it is possible to start the LWR even if the nuclear instrumentation is not online, provided the criticality position of control rods is known for previous operation. However, for the very first startup, the criticality position of control rods is required to be determined. A special nuclear instrumentation system, called Pre-startup equipment (PSE) is developed using two numbers of in-core detectors along with the processing electronics. The PSE enables operators to determine the criticality position of control rods for the first startup at zero power. The same equipment can also be used during loading of fuel assemblies. This paper discusses the features and architecture of PSE, its individual circuit blocks and specifications. (author)

  8. Cardiac Depression Scale: Mokken scaling in heart failure patients

    Directory of Open Access Journals (Sweden)

    Ski Chantal F

    2012-11-01

    Full Text Available Abstract Background There is a high prevalence of depression in patients with heart failure (HF that is associated with worsening prognosis. The value of using a reliable and valid instrument to measure depression in this population is therefore essential. We validated the Cardiac Depression Scale (CDS in heart failure patients using a model of ordinal unidimensional measurement known as Mokken scaling. Findings We administered in face-to-face interviews the CDS to 603 patients with HF. Data were analysed using Mokken scale analysis. Items of the CDS formed a statistically significant unidimensional Mokken scale of low strength (H0.8. Conclusions The CDS has a hierarchy of items which can be interpreted in terms of the increasingly serious effects of depression occurring as a result of HF. Identifying an appropriate instrument to measure depression in patients with HF allows for early identification and better medical management.

  9. Regulation EM-GT-8. Guidance for quality control of mammography equipment

    International Nuclear Information System (INIS)

    2015-01-01

    Objective: To provide practical guidance of technical procedures for carrying out quality control in mammography equipment. Scope: This guide applies to mammography equipment. A number of methods which require the appointed instrumentation described, some of which can be implemented in radiology services own country given the low complexity of themselves and others that require specific equipment and can be performed by specialized groups external to these units. The guide does not constitute a mandatory, however, the parameters evaluated according to the tests described therein and their tolerances form the basis of regulations that establish the CCEEM about these teams. Overview: The success of mammographic studies depends on obtaining high-quality images combined with a low rate of patient dose. To ensure this objective the establishment of quality assurance programs on all aspects involving these services is necessary. This guide provides a number of quality control procedures aimed at x-ray equipment, which must be performed at least on an annual basis or when some maintenance occurs at x-ray equipment.

  10. Quality of care and investment in property, plant, and equipment in hospitals.

    Science.gov (United States)

    Levitt, S W

    1994-01-01

    OBJECTIVE. This study explores the relationship between quality of care and investment in property, plant, and equipment (PPE) in hospitals. DATA SOURCES. Hospitals' investment in PPE was derived from audited financial statements for the fiscal years 1984-1989. Peer Review Organization (PRO) Generic Quality Screen (GQS) reviews and confirmed failures between April 1989 and September 1990 were obtained from the Massachusetts PRO. STUDY DESIGN. Weighted least squares regression models used PRO GQS confirmed failure rates as the dependent variable, and investment in PPE as the key explanatory variable. DATA EXTRACTION. Investment in PPE was standardized, summed by the hospital over the six years, and divided by the hospital's average number of beds in that period. The number of PRO reviewed cases with one or more GQS confirmed failures was divided by the total number of cases reviewed to create confirmed failure rates. PRINCIPAL FINDINGS. Investment in PPE in Massachusetts hospitals is correlated with GQS confirmed failure rates. CONCLUSIONS. A financial variable, investment in PPE, predicts certain dimensions of quality of care in hospitals. PMID:8113054

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

    Science.gov (United States)

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

    2004-01-01

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

  12. Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

    International Nuclear Information System (INIS)

    Cunningham, J.; Shank, J.

    2004-01-01

    To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner

  13. Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

    Energy Technology Data Exchange (ETDEWEB)

    J. Cunningham and J. Shank

    2004-11-01

    To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I&C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner.

  14. Equipment line-up developed for structuring programmed digital systems important to safety

    International Nuclear Information System (INIS)

    Remus, L.; Colling, J.M.; Buisson, J.

    1986-01-01

    The use of the programmed digital techniques in systems important to safety led to developing equipment line-ups which allow to procedure, through using a restricted number of sub-assemblies, a variety of facilities capable of performing diversified functions. Upon remembering the requirements that such equipment are required to meet (quality assurance both at the design and production stages, qualification, testing opportunities, etc.) the equipments produced by MERLIN GERIN are described in this paper. Such equipments include a whole set of printed circuit boards, plug-in units with self-engaging connectors and the related cabinets to accomodate them. The following systems are made up of such equipments: Digital integrated protection system; Rod control and monitoring system; Reactor power distribution monitoring equipment. This equipment line-up has been gradually complemented and is still further expanding both as a result of the component further development or for the purpose of meeting new requirements or applications (new digital neutron instrumentation, local area networks). Experience gained thus far provides us with the capability of working out in a short time programmed systems for further applications in the nuclear power field

  15. Electricity Breakdown Management for Sarawak Energy: Use of Condition-Based Equipment for Detection of Defective Insulator

    Science.gov (United States)

    Tan, J. K.; Abas, N.

    2017-07-01

    Managing electricity breakdown is vital since an outage causes economic losses for customers and the utility companies. However, electricity breakdown is unavoidable due to some internal or external factors beyond our control. Electricity breakdown on overhead lines tend occur more frequently because it is prone to external disturbances such as animal, overgrown vegetation and defective pole top accessories. In Sarawak Energy Berhad (SEB), majority of the network are composed of overhead lines and hence, is more prone to failure. Conventional method of equipment inspection and fault finding are not effective to quickly identify the root cause of failure. SEB has engaged the use of corona discharge camera as condition-based monitoring equipment to carry out condition based inspection on the line in order to diagnose the condition of the lines prior to failure. Experimental testing has been carried out to determine the correlation between the corona discharge count and the level of defect on line insulator. The result shall be tabulated and will be used as reference for future scanning and diagnostic on any defect on the lines.

  16. Human reliability analysis for In-Tank Precipitation alignment and startup of emergency purge ventilation equipment

    International Nuclear Information System (INIS)

    Olsen, L.M.

    1993-08-01

    This report documents the methodology used for calculating the human error probability for establishing air based ventilation using emergency purge ventilation equipment on In-Tank Precipitation (ITP) processing tanks 48 and 49 after a failure of the nitrogen purge system following a seismic event. The analyses were performed according to THERP (Technique for Human Error Rate Prediction). The calculated human error probabilities are provided as input to the Fault Tree Analysis for the ITP Nitrogen Purge System. The analysis assumes a seismic event initiator leading to establishing air based ventilation on the ITP processing tanks 48 and 49. At the time of this analysis only the tanks and the emergency purge ventilation equipment are seismically qualified. Consequently, onsite and offsite power is assumed to be unavailable and all operator control actions are to be performed locally on the tank top. Assumptions regarding procedures, staffing, equipment locations, equipment tagging, equipment availability, and training were made and are documented in this report. The human error probability for establishing air based ventilation using the emergency purge ventilation equipment on In-Tank Precipitation processing tanks 48 and 49 after a failure of the nitrogen purge system following a seismic event is 4.2E-6 (median value on the lognormal scale). It is important to note that this result is predicated on the implementation of all of the assumptions listed in the ''Assumptions'' section of this report. This analysis was not based on the current conditions in ITP. The analysis is to be used as a tool to aid ITP operations personnel in achieving the training, procedural, and operational goals outlined in this document

  17. Instrumentation for Scientific Computing in Neural Networks, Information Science, Artificial Intelligence, and Applied Mathematics.

    Science.gov (United States)

    1987-10-01

    include Security Classification) Instrumentation for scientific computing in neural networks, information science, artificial intelligence, and...instrumentation grant to purchase equipment for support of research in neural networks, information science, artificail intellignece , and applied mathematics...in Neural Networks, Information Science, Artificial Intelligence, and Applied Mathematics Contract AFOSR 86-0282 Principal Investigator: Stephen

  18. Leasing instruments of high-rise construction financing

    Science.gov (United States)

    Aleksandrova, Olga; Ivleva, Elena; Sukhacheva, Viktoria; Rumyantseva, Anna

    2018-03-01

    The leasing sector of the business economics is expanding. Leasing instruments for high-rise construction financing allow to determine the best business behaviour in the leasing economy sector, not only in the sphere of transactions with equipment and vehicles. Investments in high-rise construction have a multiplicative effect. It initiates an active search and leasing instruments use in the economic behaviour of construction organizations. The study of the high-rise construction sector in the structure of the leasing market participants significantly expands the leasing system framework. The scheme of internal and external leasing process factors influence on the result formation in the leasing sector of economy is offered.

  19. SU-F-T-247: Collision Risks in a Modern Radiation Oncology Department: An Efficient Approach to Failure Modes and Effects Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Schubert, L; Westerly, D; Vinogradskiy, Y; Fisher, C; Liu, A [University of Colorado Denver, Aurora, CO (United States); Aldridge, J [University of Colorado Hospital, Aurora, CO (United States)

    2016-06-15

    Purpose: Collisions between treatment equipment and patients are potentially catastrophic. Modern technology now commonly involves automated remote motion during imaging and treatment, yet a systematic assessment to identify and mitigate collision risks has yet to be performed. Failure modes and effects analysis (FMEA) is a method of risk assessment that has been increasingly used in healthcare, yet can be resource intensive. This work presents an efficient approach to FMEA to identify collision risks and implement practical interventions within a modern radiation therapy department. Methods: Potential collisions (e.g. failure modes) were assessed for all treatment and simulation rooms by teams consisting of physicists, therapists, and radiation oncologists. Failure modes were grouped into classes according to similar characteristics. A single group meeting was held to identify implementable interventions for the highest priority classes of failure modes. Results: A total of 60 unique failure modes were identified by 6 different teams of physicists, therapists, and radiation oncologists. Failure modes were grouped into four main classes: specific patient setups, automated equipment motion, manual equipment motion, and actions in QA or service mode. Two of these classes, unusual patient setups and automated machine motion, were identified as being high priority in terms severity of consequence and addressability by interventions. The two highest risk classes consisted of 33 failure modes (55% of the total). In a single one hour group meeting, 6 interventions were identified. Those interventions addressed 100% of the high risk classes of failure modes (55% of all failure modes identified). Conclusion: A class-based approach to FMEA was developed to efficiently identify collision risks and implement interventions in a modern radiation oncology department. Failure modes and interventions will be listed, and a comparison of this approach against traditional FMEA methods

  20. SU-F-T-247: Collision Risks in a Modern Radiation Oncology Department: An Efficient Approach to Failure Modes and Effects Analysis

    International Nuclear Information System (INIS)

    Schubert, L; Westerly, D; Vinogradskiy, Y; Fisher, C; Liu, A; Aldridge, J

    2016-01-01

    Purpose: Collisions between treatment equipment and patients are potentially catastrophic. Modern technology now commonly involves automated remote motion during imaging and treatment, yet a systematic assessment to identify and mitigate collision risks has yet to be performed. Failure modes and effects analysis (FMEA) is a method of risk assessment that has been increasingly used in healthcare, yet can be resource intensive. This work presents an efficient approach to FMEA to identify collision risks and implement practical interventions within a modern radiation therapy department. Methods: Potential collisions (e.g. failure modes) were assessed for all treatment and simulation rooms by teams consisting of physicists, therapists, and radiation oncologists. Failure modes were grouped into classes according to similar characteristics. A single group meeting was held to identify implementable interventions for the highest priority classes of failure modes. Results: A total of 60 unique failure modes were identified by 6 different teams of physicists, therapists, and radiation oncologists. Failure modes were grouped into four main classes: specific patient setups, automated equipment motion, manual equipment motion, and actions in QA or service mode. Two of these classes, unusual patient setups and automated machine motion, were identified as being high priority in terms severity of consequence and addressability by interventions. The two highest risk classes consisted of 33 failure modes (55% of the total). In a single one hour group meeting, 6 interventions were identified. Those interventions addressed 100% of the high risk classes of failure modes (55% of all failure modes identified). Conclusion: A class-based approach to FMEA was developed to efficiently identify collision risks and implement interventions in a modern radiation oncology department. Failure modes and interventions will be listed, and a comparison of this approach against traditional FMEA methods